ML16089A388: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(8 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML16089A388
| number = ML16089A388
| issue date = 03/22/2016
| issue date = 03/22/2016
| title = Surry, 2014-301Section 7
| title = 301Section 7
| author name =  
| author name =  
| author affiliation = NRC/RGN-I/DNMS
| author affiliation = NRC/RGN-I/DNMS
Line 12: Line 12:
| document type = License-Operator, Part 55 Examination Related Material
| document type = License-Operator, Part 55 Examination Related Material
| page count = 59
| page count = 59
| revision = 0
}}
}}
=Text=
{{#Wiki_filter:ES-201                                    Examination Preparation Checklist                                Form ES-201-1 Facility:          Surry                                          Date of Examination:          7/2114    8/5/14 Examinations Developed by:                  cit /              NRC    (circle one)
Chief Target Task Description (Reference)                                    Examiners Date*
Initials
    -180        1. Examination administration date confirmed (C.1.a; C.2.a and b)
    -120        2. NRC examiners and facility contact assigned (C.1.d; C.2.e)
    -120        3. Facility contact briefed on security and other requirements (C.2.c)
    -120        4. Corporate notification letter sent (C.2.d)
[-90]          [5. Reference material due (C.1.e; C.3.c; Attachment 2)]                                (
      -75        6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-3d-S. ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)
      -70        7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)
      -45        8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)
    -30          9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)
      -14        10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)
      -14        11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)
      -14        12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g)
      -7        13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)
      -7        14. Final applications reviewed; examination approval and waiver letters sent (C.2.i; Attachment 4; ES-204)
      -7        15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)
      -7        16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)
* Target dates are keyed to the examination date identified in the corporate 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 to examinations prepared by the NRC.
                                                    £x4M                                    fA/v ES-201                                    Examination Outline Quality Checklist                                  Form ES-201-2 Facility:
5_jR                                      Date of Examination:
TuL1        c.//
Initials Item                                                    Task Description
: 1.      a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
R        b. Assess whether the outline was systematically and randomly prepared in accordance with I          Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.                          (17 T
T E
: c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.                    (/9
: d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.            M i4 N
: 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, S            and major transients.
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 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          from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
: c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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                  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 T            (3) no tasks are duplicated from the applicants audit test(s)
(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 (3) no more than one task is repeated from the last two NRC licensing examinations
: c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
: 4.      a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.                                                                  2)7  it E      b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.                                7
: c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.        7 R            Check for duplication and overlap among exam sections.                                                        41:4
: d.                                                                                                          1 L      e. Check the entire exam for balance of coverage.
: f. Assess whether the exam fits the appropriate job level (RO or SRO).
: a. Author
: b. Facility Reviewer (*)
If
: c. NRC Chief Examiner (#)              1I4              -  .4ArRt
: d. NRC Supervisor                      ,tAL4Ot4 i WlPLLMJ1/
Note:                    # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
                -  WR/77EA)              &4m
ES-401, Rev. 9                                      PWR Examination Outline                                        Form ES-401-2 Facility:                            Date of Exam:
Tier              Group JI                RO K/A Category Points                              SRO-Only Points FKKKKKAAAAG[                                                      A2          G*      JTotal
                                                                                        *jTotal 11234561234                                                                            L___
: 1.          J        i          3  3f3                      33                3    18          3          3          6 Emergency &
Abnormal Plant
[
[
2                II          N/A 1
N/A 9          2          2          4 Evolutions LTie1Tota1s            5 1                    4    4            5    27          5          5          10 1          32      2    3332                3322              28          3          2          5
                          *2            11111110111                                          10                      2          3 piant Systems            Tier Totals      4  3  3    4    4  4    3    3  4    3  3    38          if          4          8
: 3. GenericKnowledgeandAbilities Categories
                                                  ]    1        2          3        4      10      1    2      3      4      7 3      2          2        3                2    2      2      1
: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the PTier Totals@
in each K/A 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 4 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
: 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.
: 7. *The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section 0.1 .b of ES-401 for the applicable KAs.
: 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics=importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
: 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43..
ES-401, REV 9                                              TIGI PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA          NAME/SAFETY FUNCTION:                        IR    1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 007EK1 .02  Reactor Trip  Stabilization  Recovery  3.4  3.8      H H H H H H H H H H          Shutdown margin
            /1 008AA1 .06  Pressurizer Vapor Space Accident / 3    3.6  3.6                                    Control of PZR level 009EK3.05  Small Break LOCA / 3                      3.4  3.8                                    CCWS radiation alarm 011 EA2.l 0 Large Break LOCA /3                      4.5  4.7                                  Verification of adequate core cooling 015AK3.0l  RCP Malfunctions /4                      2.5  3.1 LI                                Potential damage from high winding and/or bearing temperatures 022AK1 03    Loss of Rx Coolant Makeup / 2            3    3.4 H H    Relationship between charging flow and PZR level 025AA1 .11  Loss of RHR System / 4                  2.9  3    H H H H H H            H H H H    Reactor building sump level indicators 026AA2.01    Loss of Component Cooling Water / 8      2.9  3.5  H H H H H H H            H H H    Location of a leak in the CCWS 029EK2.06    ATWS / 1                                2.9  3.1  H      H H H H H H H H H          Breakers, relays, and disconnects.
040AG2.2.3  Steam Line Rupture    - Excessive Heat  3.8  3.9  LI H H H H H H H H H              (multi-unit license) Knowledge of the design, procedural Transfer / 4                                                                          and operational differences between units.
054AK3.01    Loss of Main Feedwater / 4              4.1  4.4  H H      H H H H H H H H        Reactor and/or turbine trip, manua( and automatic Page 1 of 2                                              10/04/2013 9:30AM
ES-401, REV 9                                            TIGI PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA            NAME / SAFETY FUNCTION:                  IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 056AA2.54    Loss of Off-site Power/6              2.9  3                                    Breaker position (remote and local)
ElElEl 062AA1.01    Loss ofNuclearSvcWater/4              3.1    3.1                                  Nuclear service water temperature indications ElElElEl 065AG2.l.32  LossoflnstrumentAir/8                3.8    4.0                                  Ability to explain and apply all system limits and El El El El El El ElElEI precautions.
077AK2.01    Generator Voltage and Electric Grid  3.1    3.2                                  Motors Disturbances I 6
[]    El El El El El ElElElEl weO4EG2.4.3  LOCA Outside Containment /                                                        Ability to identify post-accident instrumentation.
El El El El El El El EJElE WE05EK2.2    Inadequate Heat Transfer Loss of      3.9  4.2                                  Facilitys heat removal systems, including primary Secondary Heat Sink / 4 El    El El El El El ElElElEl coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
WE1 1 EK1 .3 Loss of Emergency Coolant Recirc. / 4 3.6  4.0                                  Annunciators and conditions indicating signals, and El remedial actions associated with the (Loss of Emergency Coolant Recir).
Page 2 of 2                                              10/04/2013 9:30AM
ES-401, REV 9                                          TIG2 PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA            NAME I SAFETY FUNCTION:                IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO OO1AG2.1 .20 Continuous Rod Withdrawal I 1        4.6  4.6 H H H      H H H H H H          Ability to execute procedure steps.
036AA1.04    Fuel Handling Accident/8            3.1  3.7                                  Fuel handling equipment during an incident 037AK3.06    Steam Generator Tube Leak) 3        3.6    4.1 H H      H H H H H H H H        Normal operating precautions to preclude or minimize SGTR 051AA2.02    Loss of Condenser Vacuuml4          3.9    4.1                                  Conditions requiring reactorand/orturbine trip 059AK1.0l    Accidental Liquid RadWaste Rel. / 9 2.7    3.1                                Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 074EG2.4.21  mad. Core Cooling /4                4.0  4.6  H H H H H H H H H H            Knowledge of the parameters and logic used to assess the status of safety functions WEO3EK2.1    LOCA Cooldown      Depress. /4      3.6  4.0  H    H H H H H H H H H          Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE14EK2.l    Loss of CTMT Integrity / 5          3.4  3.7  H    H H H H H H H H H          Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WEI 5EK1 .2  Containment Flooding /5            2.7  2.9    H H H H H H H H H H          Normal, abnormal and emergency operating procedures associated with (Containment Flooding).
Page 1 of 1                                                10/04/2013 9:30AM
ES-401, REV 9                                  T2GI PWR EXAMINATION OUTLINE                                                      FORM ES-401-2 KA        NAME I SAFETY FUNCTION:            IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G    TOPIC:
RO    SRO 003G2.4.50 Reactor Coolant Pump            4.2  4.0                                    Ability to verify system alarm setpoints and operate controls Li    J identified in the alarm response manual.
004A2.26    Chemical and Volume Control    2.8  3.0                                    Low VCT pressure LI 0041(5.06  Chemical and Volume Control    3.0    3.3                                    Concept of boron worth or inverse boron worth Li [] Li fl (reactivity, pcmlppm) 005K5.09    Residual Heat Removal          3.2    3.4                                    Dilution and boration considerations 006K4.ll    EmergencyCoreCooling          3.9    4.2                                    ResetofSlS Li LI 007A1 .02  Pressurizer Relief/Quench Tank 2.7    2.9                                j  Maintaining quench tank pressure J
007K5.02    Pressurizer Relief/Quench Tank 3.1    34                                    Method of forming a steam bubble in the PZR Li Li Li Li IJ Li Li Li Li Li Li 008K3.03    Component Cooling Water        4.1  4.2                                    RCP Li Li      Li Li Li Li Li Li Li [1 O1OK1.06    PressurizerPressureControl    2.9  3.1                                    CVCS Li Li Li Li Li Li Li Li Li 0101(4.01  PressurizerPressureControl    2.7  2.9                                    Sprayvalvewarm-up Li Li Li      Li Li Li Li Li Li Li 012K6.ll    Reactor Protection            2.9  2.9                                    Trip setpoint calculators Li Li Li LI Li          []
Page 1 of 3                                                10/04/2013 9:30AM
ES-401, REV 9                                          T2GI PWR EXAMINATION OUTLINE                                                          FORM ES-401-2 KP          NAME / SAFETY FUNCTION:                  IR      Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G      TOPIC:
RO    SRO 01 3K2.0l  Engineered Safety Features Actuation  3.6  3.8  LI                                    ESFAS/safeguards equipment control LI LI LI LI LI LI C] C] LI 013K6.0l    Engineered Safety Features Actuation  2.7  3.1  C] C] C]                              Sensors and detectors C]      C]      C]
022A3.01    Containment Cooling                  4.1    4.3                                        Initiation of safeguards mode of operation C] LI LI LI LI LI LI LI        LI LI 026A4.05    Containment Spray                    3.5  3.5                                        Containment spray reset switches LI LI LI LI LI LI LI LI LI        LI 026K4.09    Containment Spray                    3.7    4.1                                        Prevention of path for escape of radioactivity from LI LI LI    LI LI LI LI LI LI LI containment to the outside (interlock on RWST isolation after swapover) 039A3.02    Main and Reheat Steam                3.1    3.5                                        Isolation of the MRSS LI LI LI C] LI LI LI LI        LI LI 059K3.03    Main Feedwater                      3.5    3.7.                                      S/GS LI LI ] LI LI LI LI LI LI LI LI 061K6.02    Auxiliary/Emergency Feedwater        2.6    2.7                                        Pumps LI C] LI LI LI        LI LI LI LI LI 062A1 .01  AC Electrical Distribution          3.4    3.8                                        Significance of DIG load limits LI LI LI LI LI LI ] LI LI LI LI 063G2.1 .31 DC Electrical Distribution          4.6    4.3                                        Ability to locate control room switches, controls and LI C] LI LI LI LI LI LI LI LI indications and to determine that they are correctly reflecting the desired plant lineup.
063K1.03    DC Electrical Distribution          2.9    3.5                                        Battery charger and          battery LI LI LI LI LI LI LI LI LI C]
Page 2 of 3                                                      10/04/2013 9:30 AM
ES-401, REV 9                                T2GI PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME/SAFETY FUNCTION:            IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 064K1 .03  Emergency Diesel Generator    3.6  4.0                                  Diesel fuel oil supply system LI 073A2.02  Process Radiation Monitoring  2.7  3.2                                  Detector failure LI LI LI LI LI LI LI    LI LI LI 076K2.08  Service Water                3.1  3.3                                  ESF-actuated MOVs LI    LI LI LI LI LI LI LI LI LI 078A4.01  InstrumentAir                3.1    3.1                                  Pressure gauges LI LI LI LI LI LI LI LI LI ] LI 103A2.04  Containment                  3.5    3.6                                  Containment evacuation (including recognition of the alarm)
LI LI LI LI LI LI LI    LI LI LI 103A3.01  Containment                  3.9    4.2                                  Containment isolation LI LI LI LI LI LI LI LI    LI LI Page 3 of 3                                              10/04/2013 9:30 AM
ES-401, REV 9                                  T2G2 PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA        NAME / SAFETY FUNCTION:          IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 015A4.02  Nuclear Instrumentation      3.9  39                                    NIS indicators El 016K1.08  Non-nuclearlnstrumentation    3                                            PZRPCS El El El El El El El El El El 027K2.O1  Containment Iodine Removal    3.1  3.4                                    Fans 028K5.03  Hydrogen Recombiner and Purge 2.9  3.6                                    Sources of hydrogen within containment Control 033K3.02  Spent Fuel Pool Cooling      2.8  3.2                                    Area and ventilation radiation monitoring systems El 034K6.02  Fuel Handling Equipment      2.6  3.3                                    Radiation monitoring systems 071A3.Ol  Waste Gas Disposal            2.6  2.7                                    HRPS El El El El El El El El      El El 072G2.l.28 Area Radiation Monitoring    4.1  4.1                                    Knowledge of the purpose and function of major system El El El El El El El El El El components and controls.
079K4.O1  Station Air                  2.9  3.2                                    Cross-connect with lAS El El El    El El El El El El El 086A1 .01  Fire Protection              2.9  3.3                                    Fire header pressure El El El El El El      El El El El Page 1 of 1                                              10/04/2013 9:30 AM
ES-401, REV 9                                T3 PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME I SAFETY FUNCTION:        IR      Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO G2.l.29    Conduct of operations      4.1  4.0                                    Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
G2.l.40    Conduct of operations      2.8  3.9                                    Knowledge of refueling administrative requirements G2.1 .5    Conduct of operations      2.9  3.9                                  Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
G2.2.13    Equipment Control          4.1  4.3                                  Knowledge of tagging and clearance procedures.
G2.2.2    Equipment Control          4.6  4.1                                  Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
G2.3.5    Radiation Control          2.9  2.9                                  Ability to use radiation monitoring systems G2.3.7    Radiation Control          3.5  3.6                                  Ability to comply with radiation work permit requirements J
during normal or abnormal conditions G2.4.1    Emergency Procedures/Plans 4.6  4.8                                    Knowledge of EOP entry conditions and immediate action steps.
G2.4.32    Emergency Procedures/Plans 3.6  4.0                                    Knowledge of operator response to loss of all annunciators.
G2.4.4    Emergency Procedures/Plans 4.5  4.7                                    Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Page 1 of 1                                              10/04/2013 9:30 AM
ES-401, REV 9                                          SRO TIGI PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA            NAME I SAFETY FUNCTION:                    IR    Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 009EA2.39      Small Break LOCA I 3                                                            Adequate core cooling 022AA2.0l      Loss of Rx Coolant Makeup /2          3.2  3.8                                Whether charging line leak exists 027AA2.lO      Pressurizer Pressure Control System  3.3    3.6 jrj                            PZR heater energized/de-energized condition Malfunction / 3 057AG2.1 .28  Loss of Vital AC Inst. Bus 16        4.1    4.1                                Knowledge of the purpose and function of major system components and controls.
well EG2.l .32 Loss of Emergency Coolant Recirc. / 4 3.8    4.0                                Ability to explain and apply all system limits and precautions.
wel2EG2.4.4    Steam Line Rupture Excessive Heat    4.5    4.7                                Ability to recognize abnormal indications for system Transfer I 4                                                                    operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Page 1 of 1                                                  10/04/2013 9:30AM
ES-401, REV 9                                    SRO TIG2 PWR EXAMINATION OUTLINE                                                      FORM ES-401-2 KA          NAME I SAFETY FUNCTION:              IR    Ki K2 1(3 K4 K5 K6 Al A2 A3 A4 C  TOPIC:
RO    SRO 024AG2.l.23 Emergency Boration / 1            4.3  4.4                                  Ability to perform specific system and integrated plant procedures during all modes of plant operation.
033AG2.2.44 Loss of Intermediate Range NI / 7 4.2  4.4                                  Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions WEO1 EA2.l  Rediagnosis / 3                  3.2  4                                    Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
WE16EA2.2  High Containment Radiation / 9    3.0  3.3                                  Adherence to appropriate procedures and operation LI LI LI LI LI LI LI    LI LI LI within the limitations in the facilitys license and amendments.
Page 1 of 1                                                  10/04/2013 9:30AM
ES-401, REV 9                                      SRO T2GI PWR EXAMINATION OUTLINE                                                FORM ES-401-2 KA        NAME I SAFETY FUNCTION:                  IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 004G2.2.22 Chemical and Volume Control          4.0  4.7                                Knowledge of limiting conditions for operations and safety limits.
013A2.03  Engineered Safety Features Actuation 4.4  4.7                                Rapid depressurization 059A2.0l  Main Feedwater                      3.4  3.6                                Feedwater actuation of AFW system 061G2.4.49 Auxiliary/Emergency Feedwater        4.6  4.4                                Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
078A2.01  Instrument Air                      2.4  2.9                                Air dryer and filter malfunctions Page 1 of 1                                              10/04/2013 9:30AM
ES-401, REV 9                            SRO T2G2 PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME I SAFETY FUNCTION:        IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 017G2.4.47 In-core Temperature Monitor 4.2  4.2                                Ability to diagnose and recognize trends in an accurate J
and timely manner utilizing the appropriate control room reference material.
056A2.04  Condensate                  2.6  2.8                                Loss of condensate pumps 075G2.2.44 Circulating Water          4.2  4.4                                Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Page 1 of 1                                                10/04/2013 9:30AM
ES-401, REV 9                              SRO T3 PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME/SAFETY FUNCTION:          IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO G2.l.25    Conduct of operations      3.9  4.2                                Ability to interpret reference materials such as graphs,
[
monographs and tables which contain performance data.
G2.l .32  Conduct of operations      3.8    4.0                                Ability to explain and apply all system limits and precautions.
G2.2.13    Equipment Control          4.1    4.3                                Knowledge of tagging and clearance procedures.
D L D          L fl G2.2.18    Equipment Control          2.6    3.8                                Knowledge of the process for managing maintenance D LI LI LI LI LI LI activities during shutdown operations.
G2.3.ll    Radiation Control          3.8    4.3                                Ability to control radiation releases G2.3.12    Radiation Control          3.2    3.7                                Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.28    Emergency Procedures/Plans 3.2  4.1                                  Knowledge of procedures relating to emergency response to sabotage.
Page 1 of 1                                                10/04/2013 9:30AM
ES-301                              Administrative Topics Outline                                    Form ES-301-1 Facility: __Surry_________________________                              Date of Examination: __7/21/14_____
Examination Level: RO                                                    Operating Test Number: _SR14-301_
Administrative Topic            Type                      Describe activity to be performed (see Note)                Code*
Quadrant Power Tilt Ratio Conduct of Operations                  R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Conduct of Operations Perform a review of OPT-FW-006 Equipment Control                      R/M K/A:G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control                      R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Obtain Required Information IAW EPIP-2.01 Emergency Procedures/Plan              R/N      K/A: G2.4.39 Knowledge of RO responsibilities in emergency plan implementation. RO: 3.9 / SRO: 3.8.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301                              Administrative Topics Outline                                    Form ES-301-1 Facility: ___Surry_______________________                                Date of Examination: _7/21/14_____
Examination Level:          SRO                                          Operating Test Number: _SR14301__
Administrative Topic            Type                      Describe activity to be performed (see Note)                Code*
Quadrant Power Tilt Ratio Conduct of Operations                  R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations                  S/M K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8
                                                  / SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control                      R/M K/A: G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO:
4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control                      R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Classify and Determine PAR for General Emergency Emergency Procedures/Plan              R/N      K/A: G2.4.41 Knowledge of the emergency action level thresholds and classifications. RO: 2.9 / SRO: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301                              Control Room/In-Plant Systems Outline                          Form ES-301-2 Facility: ___Surry _____________________                                Date of Examination: _7/21/14______
Exam Level: RO                                                          Operating Test No.: _SR14301______
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function
: a. Respond to Control Rod Withdrawal                                              M/S/A                    1
: b. Perform an Alternate Dilute                                                    N/S                      2
: c. Configure Containment Spray IAW ECA-1.1                                        D/S/EN/L                  5
: d. Re-establish Normal Letdown Following SI                                      D/S/A/L                  3
: e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2                        D/S                      4S
: f. Remove SR NIs From Service During a Reactor Startup                            M/S/L                    7
: g. Respond to a Low Level Transient                                              D/S                      8
: h. Respond to a #3 EDG Start Failure                                              N/A/S                    6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Locally Transfer Individual Components to the Aux Shutdown                    D/L/E                    8 Panel
: j. Isolate Service Water to MER #3                                                D/A/L/E                  3
: k. Locally Swap U-2 AFW to Fire Water                                            M/A/L/E/R                4S
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                  Criteria for RO / SRO-I / SRO-U RO                  Actual          Criteria Met (A)lternate path                                                  4-6                    5                YES (D)irect from bank                                                9                    6                YES (E)mergency or abnormal in-plant                                  1                    3                YES (EN)gineered safety feature (L)ow-Power / Shutdown                                            1                    6                YES (N)ew or (M)odified from bank including 1(A)                      2                    5                YES (P)revious 2 exams (randomly selected)                            3                    0                YES (R)CA                                                              1                    1                YES (S)imulator / (C)ontrol room
ES-301                              Control Room/In-Plant Systems Outline                          Form ES-301-2 Facility: __Surry ______________________                                Date of Examination: _7/21/14______
Exam Level: SRO-I                                                        Operating Test No.: _SR14301______
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*          Safety Function
: a. Respond to Control Rod Withdrawal                                              M/S/A                    1
: b. Perform an Alternate Dilute                                                    N/S                      2
: c. Configure Containment Spray IAW ECA-1.1                                        D/S/EN/L                5
: d. Re-establish Normal Letdown Following SI                                        D/S/A/L                  3
: e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2                        D/S                    4S
: f. Remove SR NIs From Service During a Reactor Startup                            M/S/L                    7
: g. Respond to a Low Level Transient                                                D/S                      8 h.
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Locally Transfer Individual Components to the Aux Shutdown                      D/L/E                    8 Panel
: j. Isolate Service Water to MER #3                                                D/A/L/E                  3
: k. Locally Swap U-2 AFW to Fire Water                                              M/A/L/E/R              4S
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                  Criteria for RO / SRO-I / SRO-U SROI                  Actual        Criteria Met (A)lternate path                                                  4-6                    4                YES (D)irect from bank                                                8                    6                YES (E)mergency or abnormal in-plant                                  1                    3                YES (EN)gineered safety feature (L)ow-Power / Shutdown                                            1                    6                YES (N)ew or (M)odified from bank including 1(A)                      2                    4                YES (P)revious 2 exams (randomly selected)                            3                    0                YES (R)CA                                                            1                    1                YES (S)imulator / (C)ontrol room
ES-301                              Control Room/In-Plant Systems Outline                          Form ES-301-2 Facility: _Surry________________________                                Date of Examination: _7/21/14______
Exam Level: SRO-U                                                        Operating Test No.: _SR14301______
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function
: a. Respond to Control Rod Withdrawal                                              M/S/A                    1
: b. Perform an Alternate Dilute                                                    N/S                      2
: c. Configure Containment Spray IAW ECA-1.1                                        D/S/EN/L                  5 d.
e.
f.
g.
h.
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Locally Transfer Individual Components to the Aux Shutdown                    D/L/E                    8 Panel j.
: k. Locally Swap U-2 AFW to Fire Water                                            M/A/L/E/R                4S
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                  Criteria for RO / SRO-I / SRO-U SROUI                Actual          Criteria Met (A)lternate path                                                  2-3                    2                YES (D)irect from bank                                                4                    2                YES (E)mergency or abnormal in-plant                                  1                    2                YES (EN)gineered safety feature                                      1                    1                YES (L)ow-Power / Shutdown                                            1                    2                YES (N)ew or (M)odified from bank including 1(A)                      1                    3                YES (P)revious 2 exams (randomly selected)                            2                    0                YES (R)CA                                                            1                    1                YES (S)imulator / (C)ontrol room
ES-301                                              Operating Test QuaUty Checklist                                      Form ES-301-3 Facility:      Surry                  Date of Examination: Week of 7/21 & 7/28/14            Operating Test Number: SR3Ot-2014 Initials
: 1. General Criteria a        b*    c#
: a.            The operating test conforms with the previously approved outline: changes are consistent with                .
sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution),
: b.            There is no day-to-day repetition between this and other operating tests to be administered during this examination.
: c.            The operating test shall not duplicate items from the applicants audit test(s). (see Section 0. 1.
a.)                PC      A.
: d.            Overlap with the written examination and between different parts of the operating test is within        -p.,
acceptable limits.
: e.            It appears that the operating test will differentiate between competent and less-than-com petent applicants at the designated license level.
: 2. Walk-Through Criteria                                                  --        --
: a.          Each JPM includes the following, as applicable:
* 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
* operationally important specific performance criteria that include:
detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important obseivations 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 sequence of steps, if applicable
: 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 distribution, bank use, repetition from the last 2 NRC examinations) specified                f on those forms and Form ES-201-2.
: 3. Simulator Criteria                                                -_        --
The associated simulator operating tests (scenario sets) have been reviewed in accordance with                            j Form ES-301-4 and a copy is attached.
Printed Name I Signature                                        Date
: a. Author                              Michael R. Meyer!                      1                                      ?
: b. Facility Reviewer()                Rich Philpot!                                                                        1,-I.
7/
: c. NRC Chief Examiner (#)              David Lan                                                                                V C1i-r
: d. NRC Supervisor
                                                                      /                                                7(n  (
NOTE:              The facility signature is not applicable for NRC-developed tests.
              #    Independent NRC reviewer initial items in Column c: chief examiner concurrence required.
ES-301                                    Simulator Scenario Quality Checklist                                    Form ES3O1-4 Facility: Surry        Date of Exam; Week of 8/21 & 8)28/14 Scenano Numbers: 1/ 2/ 3/4/5              Operating Test No.: SR3OI-2014 QUALITATIVE ATTRIBUTES                                                        Inibals a    b*      c#
: 1.        The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.
: 2.        The scenarios consist mostly of related events.                                                              ?)
: 3.          Each event description consists of
              . the point in the scenario when it is to be initiated a    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)                                                            V a    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.                                            7i-    (j,  -
: 8.      Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
: 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.
: 8.      The simulator modeling is not altered.                                                                      7\    (      .:;z
: 9.      The scenarios have been validated, 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.
L    i_.
: 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 of ES-301,                            2i            .t(
11,        All individual operator competencies can be evaluated, as verified using Form ES-301-6 12.
(submit the form along with the simulator scenarios).
Each applicant will be significantly involved in the minimum number of transients and events 22    L.      i specified on Form ES-301-5 (submit the form with the simulator scenarios).                                rN
: 13.      The level of difficulty is appropriate to support licensing decisions for each crew position.
jj Target Quantitative Attributes (Per Scenario; See Section DSd)                        Actual Attributes      --            --
: 1.      Total malfunctions (58)                                                                  6/ 6/ 5/ 5 Q
: 2.        Malfunctions after EOP entry (12)                                                        3/2/3) 2                ic
: 3.      Abnormal events (24)                                                                      4/51 5! 5
: 4.        Major transients (12)                                                                    1/ 1/ 1/ 1 22.. iL.
: 5.        EOPs entered/requiring substantive actions (12)                                          2/1! 1/ 2          71,  (      7, 6.
EOP contingenctes requiring substantive actions (02) 1/ 1/ 1/0          7    flt i-
: 7.      Critical tasks (23)                                                                      2/2/ 3/ 2                (
ES-301                        Transient and Event Checklist                        Form ES-301-5 Facility:                            Date of Exam:                  Operating Test No.:
A        E                                      Scenarios P        V        1                3                4                5          T      M P        E                                                                        O      I L        N      CREW          CREW              CREW              CREW          T      N I        T  POSITION        POSITION          POSITION          POSITION        A I
M C            S    A  B    S      A    B    S    A    B      S    A    B    L    U A        T  R    T  O    R      T    O    R    T    O    R    T    O          M(*)
N        Y  O    C  P    O      C    P    O    C    P    O    C    P R    I  U T        P E
RO        RX        5                5                6                1          1,1,  1  1  0 1,1 SRO-I    NOR                                                                        0    1  1  1 I/C        2,6              2,                2,4,              3,5        2,3,  4  4  2 SRO-U                                4,                6                ,6,        3,4 6                                  8 MAJ        7,8              8,                7,8              7          2,2,  2  2  1 9                                              2,1 TS                                                                        0    0  2  2 RX                                                                        0    1  1  0 RO        NOR            1,5              5                  6                1    2,1,  1  1  1 1,1 SRO-I    I/C            3,4,            3,7,9              3,5,9            2,4,  4,3,  4  4  2 6,9                                                  ,8    3,3 SRO-U    MAJ            7,8              8,9                7,8              7    2,2,  2  2  1 2,1 TS                                                                        0    0  2  2 RO        RX  5              5                  6                1                1,1,  1  1  0 1,1 SRO-I    NOR  1                                                                    1,0,  1  1  1 0,0 SRO-U    I/C  2,3,4          2,3,4,            2,3,4,            2,3,4,            5,6,  4  4  2
              ,6,9          6,7,9              5,6,9            5,6,8            6,6, MAJ  7,8                    8,        7,8              7                2,2,  2  2  1 9                                              2,2 TS  1,2,3          3,4,6              2,3,5,            2,5              3,3,  0  2  2 7                  6                                  4,4 RO        RX  5              5                  6                1                1,1,  1  1  0 1,1 SRO-I    NOR  1                                                                    1,0,  1  1  1 0,0 SRO-U    I/C  2,3,4          2,3,4,            2,3,4,            2,3,4,            5,6,  4  4  2
              ,6,9          6,7,9              5,6,9            5,6,8            6,6, MAJ  7,8                    8,        7,8              7                2,2,  2  2  1 9                                              2,0 TS  1,2,3          3,4,6,            2,3,5,            2,5              3,4,  0  2  2 7                  6                                  4,2
ES-301                                  Competencies Checklist                                Form ES-301-6 Facility: Surry Power Station    Date of Examination: 7/21/14          Operating Test No.: SR301-2014 APPLICANTS RO                      SRO-I                      SRO-U Competencies SCENARIO                  SCENARIO                    SCENARIO 1      3      4    5    1      3      4      5      1      3    4    5 Interpret/Diagnose            2,3,4  2,3,4  2,3,4 2,3,4 2,3,4  2,3,4  2,3,4, 2,3,4, 2,3,4  2,3,4 2,3,4 2,3,4,
                                ,5,6  ,5,6,  ,5,6,  ,5,6  ,5  ,5,6,  5,6,7,  5,6    ,5  ,5,6, ,5,6,  5,6 Events and Conditions                  8,9    7,8                8,9      8                    8    7,8 Comply With and                  All    All    All    All  All  All    All    All    All    All  All  All Use Procedures (1)
Operate Control                ALL    ALL    2,3,4 ALL  2,5,6  N/A    2,4,6, 1,3,5,  N/A    N/A  N/A  N/A
                                              ,5,6,        ,7,8          7,8  6,7,8 Boards (2)                                    7,8,9 Communicate                    ALL    ALL    All    All  All  All    All    All    All    All  All  All and Interact Demonstrate                    N/A    N/A    N/A  N/A    All  All    All    All    All    All  All  All Supervisory Ability (3)
Comply With and                N/A    N/A    N/A  N/A  1,2,3  3,4,6  2,3,5,  2,5  1,2,3  3,4,6 2,3,5  2,5
                                                                    ,7      6            ,4          ,6 Use Tech. Specs. (3)
Notes:
(1)      Includes Technical Specification compliance for an RO.
(2)      Optional for an SRO-U.
(3)      Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
ES-401                                    Written Examination Quality Checklist                                  Form ES-401-6 Facility Surry Power Station                                                Date of Exam:          Exam Level: RO    X  SRO  X Initial Item Description                                                a    b*      c
: 1.          Questions and answers are technically accurate and applicable to the facility.
: 2.          a.            NRC K/As are referenced for all questions.
: b.            Facility learning objectives are referenced as available.
: 3.          SRO questions are appropriate in accordance with Section D.2,d of ES401                                    (ZP
: 4.          The samphng process was random and systematic (If more than 4 RO or 2 SRO questions                Nose 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:
the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started: or X 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                    19/0        25/28    56172 question_distribution(s)_at_right.
: 7.          Between 50 and 60 percent of the questions on the RO                Memory            C/A exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly 45/16          55/84 selected K/As support the higher cognitive levels: enter the actual RO I SRO question distribution(s) at right.
: 8.          References/handouts provided do not give away answers or aid in the elimination of distractors.
: 9.          Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.                                                                                  i      L
: 10.          Question psychometric quality and format meet the guidelines in ES Appendix B.                      .-.
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.                                        f Printed Name / Signature                                Date
: a. Author                                            MichaelR Meyer /
: b. Facility Reviewer (*)                            Rich Philpot /        .      iLj
: c. NRC Chief Examiner (#)                            David Lanyi_/              O
: d. NRC Regional Supervisor                              .I-4  IAA&#xe7;\jy.
                                                                                  /      ..                                )
Note:          The facility reviewers initialslsignature are not applicable for NRC-developed examinations.
Independent NRC reviewer initial items in Column c; chief examiner concurrence required, Note 1: Sample Plan provided by Chief Examiner Ken Schaaf, and amended by Chief Examiner Amanda Toth.
ES-401                                                Written Examination Review Worksheet                                                      Form ES-401-9
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus                Dist.        Link          units ward K/A Only 1    H    2                          X                                              N  E  001AG2.1.20, Continuous Rod With-drawal / 1, Ability to execute procedure steps.
K/A is met.
D is not plausible. Without any idea that there might be a stuck rod, why would anyone EB.
6/04/14 Make look like D except normal boraton. For B add IAW GOP 6/18/14 SAT as revised.
2    H    3                          X                                              N  E  003G2.4.50, Reactor Coolant Pump / 4P, Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
K/A is met.
I think the way the answers are written, C and D are not plausible.
Rearrange the answers like the ARP would do it.
C. Trip the Reactor and initiate 1-E-0; Go to 1-AP-9.02, Loss of RCP Seal Cooling. STOP the affected RCP and after 5 minutes CLOSE Pressurizer Spray Valve from Loop A..
D. Go to 1-AP-9.00, RCP Abnormal Conditions. Initiate an orderly shutdown, then CLOSE Pressurizer Spray Valve from Loop A.
STOP the affected RCP.
6/4/14 Based upon the above indications, what AP should be entered? Should the reactor be tripped or not?
6/18/14 SAT as revised.
036AA1.04, Fuel Handling Accident / 8, Ability to operate and / or 3    F    2            X                                                            B  E monitor the following as they apply to the Fuel Handling Incidents:
Fuel handling equipment during an incident.
K/A is met.
Change the second bullet to state that the Fuel Handlers have stopped withdrawing the assembly from the core while doing a visual exam. Make it clear that it is still in the core.
Is this something you expect your ROs to know?
6/4/14 Add cavity level. Fuel fully withdrawn. AP-22.00 or AP-22.01? Then choice A and C but in vertical position.
6/18/14 SAT as revised.
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                  Explanation Focus                Dist.        Link          units ward K/A Only 4  H    3                                                                            S  004K5.06, Chemical and Volume Control / 1 & 2, Knowledge of the operational implications of the following, Concept of boron worth or inverse boron worth (reactivity, pcm/ppm).
K/A is met.
Do you expect your ROs to know the note about how to set the integrator without the procedure?
Although you have 4 different valuesfor the second answer, I see that it is really only 2 (-2 from calculation or -4 from calculation).
5  F    2                                                                        B  S  005K5.09, Residual Heat Removal / 4, Knowledge of the operational implications of the following concepts as they apply the RHRS:
Dilution and boration considerations.
K/A is met.
Reword B to state a calculation is performed to ensure RHR volume combined with RCS volume will not dilute below minimum required boron.
6  H    2                                                                        N  S  006K4.11, Emergency Core Cooling / 3, Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Reset of SIS.
K/A is met.
7  H    3                          X                                              B  E  007A1.02, Pressurizer Relief/Quench Tank / 5, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:,Maintaining quench tank pressure.
K/A is met Change the second question to read The lowest pressure Change fourth bullet to state  63% and slowly rising 6/4/14. SAT as revised.
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus                Dist.        Link          units ward K/A Only 8  H    3    X                                                                  N  U  007EK1.02, Reactor Trip - Stabilization - Recovery / 1, Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Shutdown margin.
K/A is met.
Change stem to read Which one of the following data sets describes the required boron concentration to maintain Shutdown Margin in the time period between 0 to 36 hours following the reactor trip? Assume no further operator actions other than maintaining RCS temperature?
As written A and C could both be correct. Both would provide adequate SDM. Without specific values to calculate SDM.
This might work if you specified the minimum required boron concentration.
6/4/14 Change question to ask if boration is required at 12 and 36 hours.
6/18/14 SAT as revised.
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
: 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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
: 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
: 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
: 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
ES-401                                                                      2                                                                Form ES-401-9
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 9  F    2                        X                                              B  E  027K2.01, Containment Iodine Removal / 5, Knowledge of bus power supplies to the following:, Fans K/A is met.
This is fine as long there is no ability to operate these fans locally. It looks like ND-88.4-LP-6 says that they can be operated at their individual breakers.
6/4/14 Sat as revised. First bullet states only leak has been identified.
008AA1.06, Pressurizer Vapor Space Accident/ 3, Ability to operate 10  H    3    X      X          X                                              M  U and / or monitor the following as they apply to the Pressurizer Vapor Space Accident: Control of PZR level.
K/A is met.
This is strange as written. The question asks what you should do and the aswers have things you shouldnt do.
How about you ask which pumps should be operating and your answers can be: None, B Charging, B LHSI, Both.
6/4/14. Remove 5 minutes. Comma after lowered.
6/18/14 SAT as revised.
11  F    2                        X                                              N  E  008K3.03, Component Cooling Water / 8, Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:,
RCP.
K/A is met.
Not very discerning. A better question would be WOOTF, if any, with answers of None, A, B&C, All.
6/4/14. Move if any to after RCPs.
6/18/14 SAT as revised.
009EK3.05, Small Break LOCA / 3, Knowledge of the reasons for the 12  F    3    X                                                                N  E following responses as the apply to the small break LOCA:, CCWS radiation alarm.
K/A is met.
Change question to read is the most likely cause.
6/4/14. Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 13  H    2                        X                                              B  U  010K1.06, Pressurizer Pressure Control / 3, Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems, CVCS.
K/A is met.
C is the only plausible answer. If there is only one valve in AUTO in the system, any operator is going to chose that to adjust something.
I dont have a copy of OP-RC-003. Is there a preocedural method to control the system in manual?
6/4/14. Add limits on discrimantors.
6/24/14 SAT as revised.
14  F    2                                                                      B  S  010K4.01, Pressurizer Pressure Control / 3, Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for the following, Spray valve warm-up.
K/A is met.
011EA2.10, Large Break LOCA / 3, Ability to determine or interpret 15  H    2    X                                                                N  E the following as they apply to a Large Break LOCA: Verification of adequate core cooling.
K/A is met.
Change the cue to read and cannot be manually started.
Delete the initial conditions. They are redundant..
6/4/14 Sat as revised.
16  H    3                                                              X        N  U  012K6.11, Reactor Protection / 7, Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Trip setpoint calculators.
K/A is NOT met.
This is close, but the K/A requires a loss or malfunction of the trip setpoint calculator. Change this to cause a failure in the pressure instrument input and it will meet the K/A.
Can the fourth bullet read failed high?
6/4/14 Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 17  H    3    X                  X                                              B  E  013K2.01, Engineered Safety Features Actuation / 2, Knowledge of bus power supplies to the following: ESFAS/safeguards equipment control.
K/A is met.
Change question to read WOOTF states a reason that a specific sequence is recommended by 1-AP-10.06, Loss of DC Power, when restoring power following a loss of a DC Bus?
Change answer C to To allow early restoration of letdown.
6/4/14 Sat as revised.
18  H    4    X                                                                N  E  013K6.01, Engineered Safety Features Actuation / 2, Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors.
K/A is met.
Add if any to the stem of the question.
Correct answer D Si to SI (typo).
6/4/14 Sat as revised.
19  F    3                                                                      M  S  015A4.02, Nuclear Instrumentation / 7, Ability to manually operate and/or monitor in the control room: NIS indicators.
K/A is met.
20  H    3                                                                      M  E  015AK3.01, RCP Malfunctions /I 4, Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) : Potential damage from high winding and/or bearing temperatures.
K/A is met.
Clean up the answers by breaking the answers in two. For example:
RCP Motor Upper Thrust bearing temperature is 195 oF and Rising; Annunciator RCP Frame Danger is lit.
6/4/14 Sat as revised.
21  H    3                                                                      B  S  016K1.08, Non nuclear Instrumentation / 7, Knowledge of the ph.ysical connections and/or cause effect relationships between the NNIS and the following systems: PZR PCS.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 22  F    2    X                                                                N  E  022A3.01, Containment Cooling / 5, Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation.
K/A is mostly met.
Question needs reworded. It is too complex as written.
Which ONE of the following describes:
: 1) The status of Containment Air Recirculation Fans. AND
: 2) Which Recirculation Spray Pumps are operated to maintain containment pressure less than 13 psia after containment pressure has been returned to less than atmospheric pressure.
6/4/14 SAT as revised.
23  H    3    X                                                                M  E  022AK1.03, Loss of Rx Coolant Makeup / 2, Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: Relationship between charging flow and PZR level.
K/A is met.
Change the stem to say  The following is observed:
Then put the alarms at the top of the bulleted list.
6/4/14 Sat as revised.
24  H    3    X                                                                N  E  025AA1.11, Loss of RHR System / 4, Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: Reactor building sump level indicators.
K/A is met.
An initial RCS pressure needs to be listed.
6/4/14 Initial pressure should be 300 psig. No trend required.
6/18/14 SAT as revised..
25  H    3                                                                      N  S  026A4.05, Containment Spray / 5, Ability to manually operate and/or monitor in the control room: Containment spray reset switches.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 26  H    3                                                                      B  U  026AA2.01, Loss of Component Cooling Water / 8, Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS.
K/A is met.
Too similar to RO question 12.
Are there any CC auto isolations at Surry? If so, use that tack.
Otherwise look for potential sump indications.
If you use this question instead of 12, give an RCS pressure and temperature in the initial conditions, but dont tell them that they are not on RHR yet.
6/4/14. Sat as revised.
27  F    2                                                                      B  S  026K4.09, Containment Spray / 5, Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover).
K/A is met.
28  H    3    X                                                                B  E  007K5.02, Pressurizer Relief/Quench Tank / 5, Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR.
K/A is met.
Do you normally use pressurizer heaters to support RCS heatup below 195 &deg;F? If so, please specify which heaters are energized in the IC. Otherwise have the IC state that the heaters are off.
6/4/14. Sat as revised.
29  F    2    X                                                                M  E  028K5.03, Hydrogen Recombiner and Purge Control / 5, Knowledge of the operational implications of the following concepts as they apply to the HRPS: Sources of hydrogen within containment.
K/A is met.
Remove Answer the following questions from the stem.
Is the term Zircaloy Hydriding use at Surry?
6/4/14 Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 30  F    2    X                                                                B  E  029EK2.06, ATWS / 1, Knowledge of the interrelations between the breakers, relays, and disconnects following an ATWS.
K/A is met.
Change B to Open Closed Open If you wnted to then you could eliminate RTB A from the answers.
Could the question be rewritten as An inadvertent actuation of RPS A occurred?
6/4/14. Sat as revised.
31  H    2    X      X          X                                              N  E/U 033K3.02, Spent Fuel Pool Cooling /, Knowledge of the effect that a loss or malfunction of the Spent Fuel Pool Cooling System will have on the following: Area and ventilation radiation monitoring systems.
K/A is met.
How far below the low level alarm will the pool drain? Typically Ive seen syphon holes in the drain lines of SFPs. Once there, no further drainage will occur and rad levels at the crane will stanilize.
Also, how high would you expect rad level to get?
Im OK with this questioon if the conditions really could exist. Just make the last bullet become a standalone statement.
Also is it relevent that both ubits are at 100%. If so correct the grammar in the first line to state Units 1 and 2 are. Otherwise Unit 1 is 6/4/14 Sat as revised.
034K6.02, Fuel Handling Equipment / 8, Knowledge of the effect of a 32  F    2                                                                      N  S loss or malfunction on the following will have on the Fuel Handling System : Radiation monitoring systems.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 33  H    3    X                                                                N  E  004A2.26, Chemical and Volume Control / 1 & 2, Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low VCT pressure.
K/A is met.
Is it relevant that both units are at 100%? I think that stating Unit 1 is at 100% would be adequate.
Make the pressure in the stem at 16 psig and slowly lowering. This way the second part is testing that the applicant knows that there is a rupture in the VCT that requires isolating.
6/4/14. Sat as revised.
037AK3.06, Steam Generator Tube Leak./3, Knowledge of the 34  H    3                                                              X        N  S reasons for the following responses as they apply to the Steam Generator Tube Leak: Normal operating precautions to preclude or minimize SGTR.
K/A is NOT met.
The question should deal with normal operating precautions to preclude or minimize SGTR. Possibly chemistry or differential pressure or temperatures.
Also remove the statement Based on the indications answer the following questions: That is self-evident.
6/4/14. After further review question was SAT as written.
35  H    3                                                                      B  S  039A3.02, Main and Reheat Steam / 4S, Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS.
K/A is met.
36  F    2                                                              X        N  S  040AG2.2.3, Steam Line Rupture - Excessive Heat Transfer / 4, (multi-unit license) Knowledge of the design, procedural, and operational differences between units.
K/A appears to be met.
Are these valves unique to Unit 2? For example, if I wanted to crosstie Unit 1 to Unit 2, would these same valves be accessed? If so this meets the K/A.
If the above is true, could we put a fire in the U2 turbine buiding, keep the evacuation, then have U2 loose its charging pumps?
6/4/14. After further review question was SAT as written.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 37  H    3                        X                                              M  E  051AA2.02, Loss of Condenser Vacuum/4, Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.
K/A is met.
Change question to read WOOOTF shall be done first IAW 1-AP-14.00? This wil make the hoggers more plausible.
6/4/14. Sat as revised.
38  H    3    X                                                                B  E  054AK3.01, Loss of Main Feedwater /4, Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Reactor and/or turbine trip manual and automatic.
K/A is met.
Make the first two bullets Initial Conditions.
The next section should be The following occurs:
Bulletize the rest, state that the alarms lock in or words to that effect.
Remove the first question and reword the second to ask What is the reason for the action(s) required by 1-AP-21.00? If you ask the first question, the answers make some of the distractors less plausible.
6/5/14 Going back to 2X2. Which describes actions IAW AP-21.
Second part A and B. by maintaining SG water levels.
6/18/14 SAT as revised.
056AA2.54, Loss of Off-site Power / 6, Ability to determine and 39                                  X                                                E interpret the following as they apply to the Loss of Offsite Power:
Breaker position (remote and local).
K/A is met.
Make the D answer all running. This is plausible because it matches the breaker indications.
6/5/14. Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 059AK1.01, Acciental Liquid Rad Waste Rel, / 9, Knowledge of the 40  F    2    X                                                        X        N  U operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: Types & radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant.
K/A is NOT met.
This K/A isnt looking to determine if a source is contaminated or not, but rather what type of radiation (alpha, beta, gamma) and their units of intensity.
6/5/14 neutron and alpha can/cannot be detected in this room.
Correct answer.
6/18/14 SAT as revised.
41  F    2                                                              X        M  U  059K3.03, Main Feedwater / 4S, Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/Gs.
K/A is NOT met.
This case is looking for some failure in the main feed system, not S/G level control. Look at something like a heater tube failures affect.
6/5/14 load is reduced to 85% IAW procedure. Is further load reduction required? Following the load reduction, SG press be ___
than the was at 100%.
6/19/14 Correct typo in Initial Conditions. Either capitalize feedwater or dont. Cant have it both wways. Otherwise SAT.
6/25/14 SAT as revised.
42  H    3                                                                      M  S  061K6.02, Auxiliary/Emergency Feedwater / 4S, Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps.
K/A is met.
43  F    3                                                                      B  S  062A1.01, AC Electrical Distribution / 6, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Significance of D/G load limits.
K/A is met.
This is fine if these values are expected to be memorized by the applicants.
6/5/14. SAT. Required knowledge.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 44  H    3                                                                      N  E  062AA1.01, Loss of Nuclear Svc Water / 4, Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): Nuclear service water temperature indications.
K/A is met.
Make first bullet current tense.
Make the third bullet the second bullet.
6/5/14 Remove DRP info. Is Cont Pressure vs Water Temp .. met?
6/19/14. SAT as revised.
45  H    3                                                                      N  S  063G2.1.31, DC Electrical Distribution / 6, Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
K/A is mostly met.
46  H    3                        X                                              N  E  063K1.03, DC Electrical Distribution / 6, Knowledge of the physical connections and/or cause effect relationships between the DC electrical system and the following systems: Battery charger and battery.
K/A is met.
Change distractors to as follows A. Unit 1 A and Unit 2 B.
B. Unit 1 B and Unit 2 B.
C. Unit 2 A and Unit 2 B D. Unit 2 B only.
With the 2J bus de-energized, the 2B battery discharge is just about given.
6/4/14 SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 47  F    2                        X                                              N  E  064K1.03, Emergency Diesel Generator / 6, Knowledge of the physical connections and/or cause effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system.
K/A is met.
D is not plausible. If the fuel racks close off all fuel, how can the EDG idle?
6/4/14. Put automatic between specific and actions in first question.
6/19/14. SAT as revised.
48  H    2                        X                                              M  E  065AG2.1.32, Loss of Instrument Air / 8, Ability to explain and apply all system limits and precautions.
K/A is met.
B is a subset of A, therefore this would cause applicants to stay away from both answers.
6/5/14. Make two by two. Is immediate entry required? Is reactor trip required 6/19/14. SAT as revised.
071A3.02, Waste Gas Disposal / 9, Ability to monitor automatic 49  H    3                                                                      N  S operation of the Waste Gas Disposal System including: Pressure-regulating system for waste gas vent header.
K.A is met.
50  F    2                                                                      N  S  072G2.1.28, Area Radiation Monitoring / 6, Knowledge of the purpose and function of major system components and controls.
K/A is met.
51  H    3                                                                      N  S  073A2.02, Process Radiation Monitoring / 7, Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 52  F    3                                                                      M  S  074EG2.4.21, Inad Core Cooling /4, Knowledge of the parameters and logic used to assess the status of safety functions.
K/A is met.
If you have feedback that the 2 column format is better, continue to use it. Otherwise just have bulleted sentences.
53  H    3                                                                      N  S  076K2.08, Service Water / 4S, Knowledge of bus power supplies to the ESF-actuated MOVs.
K/A is met.
54  H    3            X                                                          N  S  077AK2.01, Generator Voltage and Electric Grid Disturbances / 6, Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and motors.
K/A is met.
If system voltage is at its max and you are maximizing VARs in, arent you lowering a higher than normal voltage? If so, is the answer still correct?
6/5/14. This is how the system will respond. SAT.
55  H    3                                                                      N  S  078A4.01, Instrument Air / 8, Ability to manually operate and/or monitor in the control room:Pressure gauges.
K/A is met.
56  H    3    X                                                                N  E  079K4.01, Station Air / 8, Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with lAS.
K/A is met.
Make Bullet 5 as a stand alone (non-bulleted) sentence.
Label the last 3 bullets as current condition.
6/5/14. Two by two. Location of leak. Is U2 IAC running?. Put leak on SAC discharge.
6/19/14. SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 57  F    2                                            X                        B  S  086A1.01, Fire Protection / 8, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: Fire header pressure.
K/A is met.
Do you expect your operators to know that FP-37 is on the diesel fire pump and FP-36 is on the motor driven? If this is answered yes by the Facility Rep, then this question is SAT.
6/5/14 SAT. This is requijred knowledge.
58  F    3                                                                      M  S  103A2.04, Containment / 5, Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Containment evacuation (including recognition of the alarm).
K/A is met.
59  H    3                                                                      M  S  103A3.01, Containment / 5, Ability to monitor automatic operation of the containment system, including: Containment isolation.
K/A is met.
60  F    2                                                        .              N  S  G2.1.29, Conduct of operations, Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
K/A is met.
61  F    3                                                                      N  S  G2.1.40, Conduct of operations, Knowledge of refueling administrative requirements.
K/A is met.
62  F    3                                                                      M  S  G2.1.5, Conduct of operations, Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
K/A is met.
63  F    2                                                                      M  S  G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 64  F    2                                                                      N  S  G2.2.2, Equipment Control, Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
K/A is met.
65  F    1                                            X                        B  U  G2.3.5, Radiation Control, Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
K/A is met.
A is not plausible and D is barely plausible. This is a general rad worker question. LOD =1.
6/5/14 Use N-16 monitor.
6/19/14 As written, 10% is never wrong for the first part of the question. Need to rephrase to something like the minimum power level at whichthey can be relied upon.
6/25/14 SAT as revised.
66  F    1                                                                      N  U  G2.3.7, Radiation Control, Ability to comply with radiation work permit requirements during normal or abnormal conditions.
K/A is met.
Why would any person who has worked in nuclear power pick B
anything but D. Perhaps use a survey map with an RWP and see if they can figure out if they can do a task. LOD=1.
6/5/14. Bank question used.. SAT as revised.
67  F    3                                                                      N  E  G2.4.1, Emergency Procedures/Plans, Knowledge of EOP entry conditions and immediate action steps.
K/A is met.
Modify second question to read All of the methods provided in this procedure to secure steam flow to the Main Turbine from the Control Room?
6/5/14. Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 68  F    3                                                                      N  E  G2.4.32, Emergency Procedures/Plans, Knowledge of operator response to loss of all annunciators.
K/A is met.
: 1) Change second question to read Upon power restoration what is the minimum acceptable method to perform a functional check in order to confirm that alarming conditions in the field will actuate the appropriate alarm?
6/5/14. SAT as revised.
69  H    3                                                                      N  S  G2.4.4, Emergency Procedures/Plans, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
K/A is met.
70  H    2                                                                      N  S  WE03EK2.1, LOCA Cooldown Depress /4, Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
K/A is met.
71  H    3                                                                      N  E  WE04EG2.4.3, LOCA Outside Containment / 3, Ability to identify post-accident instrumentation.
K/A is met.
In the question, replace the comma with an and and the and would with a to.
6/4/14. SAT as reivsed.
72  H    3                                                                      M  S  WE05EK2.2, Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4, Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facilitys heat removal 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.
K/A is met.
Make all of the bullets except the last one part of the initial conditions.
Make the last bullet a stand alone statement.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 73  H    3                                                                      N  S  WE11EK1.3, Loss of Emergency Coolant Recirc./ 4, Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Annunciators and conditions indicating signals and remedial actions associated with the (Loss of Emergency Coolant Recirc).
K/A is met.
WE14EK2.1, Knowledge of the interrelations between the (High 74  H    3                                                                      N  S Containment Pressure) and the following: / 5 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
K/A is met.
75  F    2                                                                      N  E  WE15EK1.2, Containment Flooding / 5, Normal, abnormal and emergency operating procedures associated with (Containment Flooding).
K/A is met.
Following a Design Basis LOCA, the MINIMUM containment sump level to enter FR-Z.2, Response to Containment Flooding is
_____1)_____ feet, and entry is a(n) _____2) _____ Path.
Change a __ to a(n)___.
6/4/14. First part remains the same. Second pressure would be a red path to FR-Z.1.
6/19/14. SAT as revised.
ES-401                                                Written Examination Review Worksheet                                                    Form ES-401-9
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus                Dist.        Link          units ward K/A Only 76  H    2            X                                                            M  S  004G2.2.22, Chemical and Volume Control / 1 & 2, Knowledge of limiting conditions for operations and safety limits.
K/A is met.
Why do you feel it is necessary to provide a drawing? This should be part of system knowledge.
6/4/14. SAT as is.
77  H    3                          X                                              M  S  009EA2.39, Small Break LOCA / 3, Ability to determine or interpret adequate core cooling as it applies to a small break LOCA.
K/A is met.
Is A credible? If you dont meet RCP trip criteria, it is almost always due to subcooling. If you dont have subcooling, why would you stop SI?
78  H    3                                                                        M  S  013A2.03, Engineered Safety Features Actuation / 2, Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Rapid depressurization K/A is mostly met.
79  H    3                                                                        N  S  017G2.4.47, in-core Temperature Monitor / 7, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
K/A is met.
022AA2. 01, Loss of Rx Coolant Makeup I 2, Ability to determine 80  H    3                                                                        M  S and interpret the following as they apply to the Loss of Reactor Coolant Makeup: (CFR 43.5/ 45.13) Whether charging line leak exists.
K/A is met.
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus                Dist.        Link          units ward K/A Only 81  H    3                          X                                              N  E  024AG2.1.23, Emergency Boration/I 1, Ability to perform specific system and integrated plant procedures during all modes of plant operation.
K/A is met.
You have four different second part answers. If this answer is known, it makes the first part irrelevent and therefore would not meet the K/A. Why not choose the Delta flux answer associated with transients and the rod insertion associated with reactor trip and have a true 2 by 2 answer?
6/4/2014 Sat as revised.
82  H    2                          X                                              M  E  027AA2.10, Pressurizer Pressure Control System Malfunction / 3, Ability to determine and Interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR heater energized/de-energized condition.
K/A is met.
Is it necessary to tell them that the Master Controller output goes to 0%? This should be testable knowledge.
Change the second part answer to read will not be solid when critical.
6/4/14 Added comma after operation in question.
6/17/14 SAT as revised.
83  H    2                                                                      X  N  U  033AG2.2.44, Loss of Intermediate Range NI / 7, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
K/A is met.
Question is NOT at SRO level. The removal of fuses is RO knowledge. Knowing that you must verify permissive light within one hour is RO knowledge.
6/4/14 Control Power fuses would/ would not be removed and make the second part ask what AP-4.0 requires.
6/17/14 SAT as revised.
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
: 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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
: 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
: 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
: 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
ES-401                                                                      2                                                              Form ES-401-9
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 84  H    2                                                                      N  S  014A2.05, Rod Position Indication / 1, Ability to (a) predict the impacts of a reactor trip on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
K/A is met.
85  H    3                                                                      N  S  057AG2.1.28, Loss of Vital AC Inst. Bus/ 6, Knowledge of the purpose and function of major system components and controls.
K/A is met.
059A2.01, Main Feedwater / 4S, Ability to (a) predict the impacts of 86  H    3                        X                                              N  E feedwater actuation of AFW system on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
K/A is met.
Change 2nd distractor to 24 hours. This is more plausible as action 22 of the AFW TS.
Is this how you want to ask the question? An alternative could be What LCO is entered? With the answers as Table 3.7-2, Action 24.
48 hours to restore. And Table 3.7-2, Action 22. 24 hours to restore.
6/4/14 Change first part to ask if TS entry is required. Provide TS 3.e and Action 24.
6/17/14 SAT as revised.
87  H    3                                                                      N  S  061G2.4.47, Auxiliary/Emergency Feedwater, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 88  H    2            X                                                          N  E  075G2.2.44, Circulating Water / 8, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
K/A is met.
You need a value and trend for intake canal leve to ensure single answer.
6/4/14 Change 25 ft and lowering.
6/17/14 SAT as revised.
078A2.01, Instrument Air /, Ability to (a) predict the impacts of the 89  H    3                                                              X        N  U following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions.
K/A is NOT met.
Need to use procedures to control or mitigate. In this case I would suggest using 1-AOP-27.00. You can ask about the need to secure RHR pumps, or about alternate cooling methods , or isolating containment.
6/4/14. SAT as rewritten.
90  H    3                                                                      M  S  G2.1.25, Conduct of operations, Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
K/A is met.
91  H    3                        X                                              N  E  G2.1.32, Conduct of operations, Ability to explain and apply all system limits and precautions.
K/A is met.
There is a subset issue here. An applicant can claim that since 68%
is less than 75%, it is always correct. So he may answer correctly without knowing the information. More clearly phrase the question to ask what the TS states.
6/4/14. What is the max time to be less than 68%. 1 hour or 30 min.
6/17/14 SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 92  F    2                        X                                              M  E  G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.
K/A is met.
Remove because of a shortage of personnel from answer D.
6/14/04. Sat as rewritten.
93  H    3                                                                      N  S  G2.2.18, Equipment Control, Knowledge of the process for managing maintenance activities during shutdown operations.
K/A is met.
94  F    2                        X                                              N  E  G2.3.11, Radiation Control, Ability to control radiation releases.
K/A is met.
Change the second part to the following:
the dose to an individual standing _________________.
: 1) at the exclusion area boundary will not exceed 0.5 rem TEDE over a 2 hour period.
: 2) in an unrestricted area will not exceed 0.002 rem in any one hour.
This second part is a Part 20 requirement that does not apply in this case.
6/4/14 Sat as rewritten.
G2.3.12, Radiation Control, Knowledge of radiological safety 95  F    2                                                              X        N  E principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
K/A is not reall met.
Since there are four different answers fo the second part of the question, the first part is not relevent. Suggest that you delete the 24 hour and 4 hour answers from the second part. This would be an adequate question then.
6/4/14 Added maximum prior to the word time in question 2. No press release is planned to be issued.
6/17/14 SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 96    H    2            X                                                          N  E  G2.4.28, Emergency Procedures/Plans, Knowledge of procedures relating to emergency response to sabotage.
K/A is met.
I believe that 0-AOP-36.00 requires both units be tripped upon breaching the fences. If so, let the applicants know that the applicable portions of the AOP are in progess with no issues.
6/4/14 Sat as rewritten.
97    F    3                                                                          S  WE11EG2.1.32, Loss of Emergency Coolant Recirc. /4, Ability to explain and apply all system limits and precautions.
K/A is met.
98    H    3                                                                          S  WE12EG2.4.4, Steam Line Rupture - Excessive Heat Transfer /4, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
K/A is met.
99    H    2                                                                      B  S  WE16EA2.2, High Containment Radiation / 9, Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
K/A is met.
100  H    3                                                                      N  S  WE01EA2.1, Rediagnosis / 3, Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
K/A is met.
ES-403                              Written Examination Grading                    Form ES-403-1 Quality Checklist Facility: Surry                        Date of Exam: 08/05/14      Exam Level: ROj SROE Initials Item Description                              a      b      c
: 1.      Clean answer sheets copied before grading                          -2    ,ii4
: 2.      Answer key changes and question deletions justified and documented                                                                  AX
: 3.      Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)
: 4.      Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail
: 5.      All other failing examinations checked to ensure that grades are justified
: 6.      Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature                        Date
: a. Grader                          Newton Lacy
: b. Facility Reviewer(*)            N/A
: c. NRC Chief Examiner (*)          David Lanyi /
                                                                              /        /7/fy
: d. NRC Supervisor (*)
(*)      The facility reviewers signature is not applicable for e nations graded by the NRC; two independent NRC reviews are required.
ES-403, Page 6 of 6
                                                    &#xa3;x4M                                    fA/v ES-201                                    Examination Outline Quality Checklist                                  Form ES-201-2 Facility:
5_jR                                      Date of Examination:
TuL1        c.//
Initials Item                                                    Task Description
: 1.      a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
R        b. Assess whether the outline was systematically and randomly prepared in accordance with I          Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.                          (17 T
T E
: c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.                    (/9
: d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.            M i4 N
: 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, S            and major transients.
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 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          from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
: c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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                  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 T            (3) no tasks are duplicated from the applicants audit test(s)
(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 (3) no more than one task is repeated from the last two NRC licensing examinations
: c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
: 4.      a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.                                                                  2)7  it E      b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.                                7
: c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.        7 R            Check for duplication and overlap among exam sections.                                                        41:4
: d.                                                                                                          1 L      e. Check the entire exam for balance of coverage.
: f. Assess whether the exam fits the appropriate job level (RO or SRO).
: a. Author
: b. Facility Reviewer (*)
If
: c. NRC Chief Examiner (#)              1I4              -  .4ArRt
: d. NRC Supervisor                      ,tAL4Ot4 i WlPLLMJ1/
Note:                    # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
                -  WR/77EA)              &4m
ES-201                                    Examination Preparation Checklist                                Form ES-201-1 Facility:          Surry                                          Date of Examination:          7/2114    8/5/14 Examinations Developed by:                  cit /              NRC    (circle one)
Chief Target Task Description (Reference)                                    Examiners Date*
Initials
    -180        1. Examination administration date confirmed (C.1.a; C.2.a and b)
    -120        2. NRC examiners and facility contact assigned (C.1.d; C.2.e)
    -120        3. Facility contact briefed on security and other requirements (C.2.c)
    -120        4. Corporate notification letter sent (C.2.d)
[-90]          [5. Reference material due (C.1.e; C.3.c; Attachment 2)]                                (
      -75        6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-3d-S. ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)
      -70        7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)
      -45        8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)
    -30          9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)
      -14        10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)
      -14        11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)
      -14        12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g)
      -7        13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)
      -7        14. Final applications reviewed; examination approval and waiver letters sent (C.2.i; Attachment 4; ES-204)
      -7        15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)
      -7        16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)
* Target dates are keyed to the examination date identified in the corporate 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 to examinations prepared by the NRC.
                                                    &#xa3;x4M                                    fA/v ES-201                                    Examination Outline Quality Checklist                                  Form ES-201-2 Facility:
5_jR                                      Date of Examination:
TuL1        c.//
Initials Item                                                    Task Description
: 1.      a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
R        b. Assess whether the outline was systematically and randomly prepared in accordance with I          Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.                          (17 T
T E
: c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.                    (/9
: d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.            M i4 N
: 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, S            and major transients.
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 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          from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
: c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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                  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 T            (3) no tasks are duplicated from the applicants audit test(s)
(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 (3) no more than one task is repeated from the last two NRC licensing examinations
: c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
: 4.      a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.                                                                  2)7  it E      b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.                                7
: c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.        7 R            Check for duplication and overlap among exam sections.                                                        41:4
: d.                                                                                                          1 L      e. Check the entire exam for balance of coverage.
: f. Assess whether the exam fits the appropriate job level (RO or SRO).
: a. Author
: b. Facility Reviewer (*)
If
: c. NRC Chief Examiner (#)              1I4              -  .4ArRt
: d. NRC Supervisor                      ,tAL4Ot4 i WlPLLMJ1/
Note:                    # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
                -  WR/77EA)              &4m
ES-401, Rev. 9                                      PWR Examination Outline                                        Form ES-401-2 Facility:                            Date of Exam:
Tier              Group JI                RO K/A Category Points                              SRO-Only Points FKKKKKAAAAG[                                                      A2          G*      JTotal
                                                                                        *jTotal 11234561234                                                                            L___
: 1.          J        i          3  3f3                      33                3    18          3          3          6 Emergency &
Abnormal Plant
[
[
2                II          N/A 1
N/A 9          2          2          4 Evolutions LTie1Tota1s            5 1                    4    4            5    27          5          5          10 1          32      2    3332                3322              28          3          2          5
                          *2            11111110111                                          10                      2          3 piant Systems            Tier Totals      4  3  3    4    4  4    3    3  4    3  3    38          if          4          8
: 3. GenericKnowledgeandAbilities Categories
                                                  ]    1        2          3        4      10      1    2      3      4      7 3      2          2        3                2    2      2      1
: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the PTier Totals@
in each K/A 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 4 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
: 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.
: 7. *The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section 0.1 .b of ES-401 for the applicable KAs.
: 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics=importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
: 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43..
ES-401, REV 9                                              TIGI PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA          NAME/SAFETY FUNCTION:                        IR    1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 007EK1 .02  Reactor Trip  Stabilization  Recovery  3.4  3.8      H H H H H H H H H H          Shutdown margin
            /1 008AA1 .06  Pressurizer Vapor Space Accident / 3    3.6  3.6                                    Control of PZR level 009EK3.05  Small Break LOCA / 3                      3.4  3.8                                    CCWS radiation alarm 011 EA2.l 0 Large Break LOCA /3                      4.5  4.7                                  Verification of adequate core cooling 015AK3.0l  RCP Malfunctions /4                      2.5  3.1 LI                                Potential damage from high winding and/or bearing temperatures 022AK1 03    Loss of Rx Coolant Makeup / 2            3    3.4 H H    Relationship between charging flow and PZR level 025AA1 .11  Loss of RHR System / 4                  2.9  3    H H H H H H            H H H H    Reactor building sump level indicators 026AA2.01    Loss of Component Cooling Water / 8      2.9  3.5  H H H H H H H            H H H    Location of a leak in the CCWS 029EK2.06    ATWS / 1                                2.9  3.1  H      H H H H H H H H H          Breakers, relays, and disconnects.
040AG2.2.3  Steam Line Rupture    - Excessive Heat  3.8  3.9  LI H H H H H H H H H              (multi-unit license) Knowledge of the design, procedural Transfer / 4                                                                          and operational differences between units.
054AK3.01    Loss of Main Feedwater / 4              4.1  4.4  H H      H H H H H H H H        Reactor and/or turbine trip, manua( and automatic Page 1 of 2                                              10/04/2013 9:30AM
ES-401, REV 9                                            TIGI PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA            NAME / SAFETY FUNCTION:                  IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 056AA2.54    Loss of Off-site Power/6              2.9  3                                    Breaker position (remote and local)
ElElEl 062AA1.01    Loss ofNuclearSvcWater/4              3.1    3.1                                  Nuclear service water temperature indications ElElElEl 065AG2.l.32  LossoflnstrumentAir/8                3.8    4.0                                  Ability to explain and apply all system limits and El El El El El El ElElEI precautions.
077AK2.01    Generator Voltage and Electric Grid  3.1    3.2                                  Motors Disturbances I 6
[]    El El El El El ElElElEl weO4EG2.4.3  LOCA Outside Containment /                                                        Ability to identify post-accident instrumentation.
El El El El El El El EJElE WE05EK2.2    Inadequate Heat Transfer Loss of      3.9  4.2                                  Facilitys heat removal systems, including primary Secondary Heat Sink / 4 El    El El El El El ElElElEl coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
WE1 1 EK1 .3 Loss of Emergency Coolant Recirc. / 4 3.6  4.0                                  Annunciators and conditions indicating signals, and El remedial actions associated with the (Loss of Emergency Coolant Recir).
Page 2 of 2                                              10/04/2013 9:30AM
ES-401, REV 9                                          TIG2 PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA            NAME I SAFETY FUNCTION:                IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO OO1AG2.1 .20 Continuous Rod Withdrawal I 1        4.6  4.6 H H H      H H H H H H          Ability to execute procedure steps.
036AA1.04    Fuel Handling Accident/8            3.1  3.7                                  Fuel handling equipment during an incident 037AK3.06    Steam Generator Tube Leak) 3        3.6    4.1 H H      H H H H H H H H        Normal operating precautions to preclude or minimize SGTR 051AA2.02    Loss of Condenser Vacuuml4          3.9    4.1                                  Conditions requiring reactorand/orturbine trip 059AK1.0l    Accidental Liquid RadWaste Rel. / 9 2.7    3.1                                Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 074EG2.4.21  mad. Core Cooling /4                4.0  4.6  H H H H H H H H H H            Knowledge of the parameters and logic used to assess the status of safety functions WEO3EK2.1    LOCA Cooldown      Depress. /4      3.6  4.0  H    H H H H H H H H H          Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE14EK2.l    Loss of CTMT Integrity / 5          3.4  3.7  H    H H H H H H H H H          Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WEI 5EK1 .2  Containment Flooding /5            2.7  2.9    H H H H H H H H H H          Normal, abnormal and emergency operating procedures associated with (Containment Flooding).
Page 1 of 1                                                10/04/2013 9:30AM
ES-401, REV 9                                  T2GI PWR EXAMINATION OUTLINE                                                      FORM ES-401-2 KA        NAME I SAFETY FUNCTION:            IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G    TOPIC:
RO    SRO 003G2.4.50 Reactor Coolant Pump            4.2  4.0                                    Ability to verify system alarm setpoints and operate controls Li    J identified in the alarm response manual.
004A2.26    Chemical and Volume Control    2.8  3.0                                    Low VCT pressure LI 0041(5.06  Chemical and Volume Control    3.0    3.3                                    Concept of boron worth or inverse boron worth Li [] Li fl (reactivity, pcmlppm) 005K5.09    Residual Heat Removal          3.2    3.4                                    Dilution and boration considerations 006K4.ll    EmergencyCoreCooling          3.9    4.2                                    ResetofSlS Li LI 007A1 .02  Pressurizer Relief/Quench Tank 2.7    2.9                                j  Maintaining quench tank pressure J
007K5.02    Pressurizer Relief/Quench Tank 3.1    34                                    Method of forming a steam bubble in the PZR Li Li Li Li IJ Li Li Li Li Li Li 008K3.03    Component Cooling Water        4.1  4.2                                    RCP Li Li      Li Li Li Li Li Li Li [1 O1OK1.06    PressurizerPressureControl    2.9  3.1                                    CVCS Li Li Li Li Li Li Li Li Li 0101(4.01  PressurizerPressureControl    2.7  2.9                                    Sprayvalvewarm-up Li Li Li      Li Li Li Li Li Li Li 012K6.ll    Reactor Protection            2.9  2.9                                    Trip setpoint calculators Li Li Li LI Li          []
Page 1 of 3                                                10/04/2013 9:30AM
ES-401, REV 9                                          T2GI PWR EXAMINATION OUTLINE                                                          FORM ES-401-2 KP          NAME / SAFETY FUNCTION:                  IR      Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G      TOPIC:
RO    SRO 01 3K2.0l  Engineered Safety Features Actuation  3.6  3.8  LI                                    ESFAS/safeguards equipment control LI LI LI LI LI LI C] C] LI 013K6.0l    Engineered Safety Features Actuation  2.7  3.1  C] C] C]                              Sensors and detectors C]      C]      C]
022A3.01    Containment Cooling                  4.1    4.3                                        Initiation of safeguards mode of operation C] LI LI LI LI LI LI LI        LI LI 026A4.05    Containment Spray                    3.5  3.5                                        Containment spray reset switches LI LI LI LI LI LI LI LI LI        LI 026K4.09    Containment Spray                    3.7    4.1                                        Prevention of path for escape of radioactivity from LI LI LI    LI LI LI LI LI LI LI containment to the outside (interlock on RWST isolation after swapover) 039A3.02    Main and Reheat Steam                3.1    3.5                                        Isolation of the MRSS LI LI LI C] LI LI LI LI        LI LI 059K3.03    Main Feedwater                      3.5    3.7.                                      S/GS LI LI ] LI LI LI LI LI LI LI LI 061K6.02    Auxiliary/Emergency Feedwater        2.6    2.7                                        Pumps LI C] LI LI LI        LI LI LI LI LI 062A1 .01  AC Electrical Distribution          3.4    3.8                                        Significance of DIG load limits LI LI LI LI LI LI ] LI LI LI LI 063G2.1 .31 DC Electrical Distribution          4.6    4.3                                        Ability to locate control room switches, controls and LI C] LI LI LI LI LI LI LI LI indications and to determine that they are correctly reflecting the desired plant lineup.
063K1.03    DC Electrical Distribution          2.9    3.5                                        Battery charger and          battery LI LI LI LI LI LI LI LI LI C]
Page 2 of 3                                                      10/04/2013 9:30 AM
ES-401, REV 9                                T2GI PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME/SAFETY FUNCTION:            IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 064K1 .03  Emergency Diesel Generator    3.6  4.0                                  Diesel fuel oil supply system LI 073A2.02  Process Radiation Monitoring  2.7  3.2                                  Detector failure LI LI LI LI LI LI LI    LI LI LI 076K2.08  Service Water                3.1  3.3                                  ESF-actuated MOVs LI    LI LI LI LI LI LI LI LI LI 078A4.01  InstrumentAir                3.1    3.1                                  Pressure gauges LI LI LI LI LI LI LI LI LI ] LI 103A2.04  Containment                  3.5    3.6                                  Containment evacuation (including recognition of the alarm)
LI LI LI LI LI LI LI    LI LI LI 103A3.01  Containment                  3.9    4.2                                  Containment isolation LI LI LI LI LI LI LI LI    LI LI Page 3 of 3                                              10/04/2013 9:30 AM
ES-401, REV 9                                  T2G2 PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA        NAME / SAFETY FUNCTION:          IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 015A4.02  Nuclear Instrumentation      3.9  39                                    NIS indicators El 016K1.08  Non-nuclearlnstrumentation    3                                            PZRPCS El El El El El El El El El El 027K2.O1  Containment Iodine Removal    3.1  3.4                                    Fans 028K5.03  Hydrogen Recombiner and Purge 2.9  3.6                                    Sources of hydrogen within containment Control 033K3.02  Spent Fuel Pool Cooling      2.8  3.2                                    Area and ventilation radiation monitoring systems El 034K6.02  Fuel Handling Equipment      2.6  3.3                                    Radiation monitoring systems 071A3.Ol  Waste Gas Disposal            2.6  2.7                                    HRPS El El El El El El El El      El El 072G2.l.28 Area Radiation Monitoring    4.1  4.1                                    Knowledge of the purpose and function of major system El El El El El El El El El El components and controls.
079K4.O1  Station Air                  2.9  3.2                                    Cross-connect with lAS El El El    El El El El El El El 086A1 .01  Fire Protection              2.9  3.3                                    Fire header pressure El El El El El El      El El El El Page 1 of 1                                              10/04/2013 9:30 AM
ES-401, REV 9                                T3 PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME I SAFETY FUNCTION:        IR      Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO G2.l.29    Conduct of operations      4.1  4.0                                    Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
G2.l.40    Conduct of operations      2.8  3.9                                    Knowledge of refueling administrative requirements G2.1 .5    Conduct of operations      2.9  3.9                                  Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
G2.2.13    Equipment Control          4.1  4.3                                  Knowledge of tagging and clearance procedures.
G2.2.2    Equipment Control          4.6  4.1                                  Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
G2.3.5    Radiation Control          2.9  2.9                                  Ability to use radiation monitoring systems G2.3.7    Radiation Control          3.5  3.6                                  Ability to comply with radiation work permit requirements J
during normal or abnormal conditions G2.4.1    Emergency Procedures/Plans 4.6  4.8                                    Knowledge of EOP entry conditions and immediate action steps.
G2.4.32    Emergency Procedures/Plans 3.6  4.0                                    Knowledge of operator response to loss of all annunciators.
G2.4.4    Emergency Procedures/Plans 4.5  4.7                                    Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Page 1 of 1                                              10/04/2013 9:30 AM
ES-401, REV 9                                          SRO TIGI PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA            NAME I SAFETY FUNCTION:                    IR    Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 009EA2.39      Small Break LOCA I 3                                                            Adequate core cooling 022AA2.0l      Loss of Rx Coolant Makeup /2          3.2  3.8                                Whether charging line leak exists 027AA2.lO      Pressurizer Pressure Control System  3.3    3.6 jrj                            PZR heater energized/de-energized condition Malfunction / 3 057AG2.1 .28  Loss of Vital AC Inst. Bus 16        4.1    4.1                                Knowledge of the purpose and function of major system components and controls.
well EG2.l .32 Loss of Emergency Coolant Recirc. / 4 3.8    4.0                                Ability to explain and apply all system limits and precautions.
wel2EG2.4.4    Steam Line Rupture Excessive Heat    4.5    4.7                                Ability to recognize abnormal indications for system Transfer I 4                                                                    operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Page 1 of 1                                                  10/04/2013 9:30AM
ES-401, REV 9                                    SRO TIG2 PWR EXAMINATION OUTLINE                                                      FORM ES-401-2 KA          NAME I SAFETY FUNCTION:              IR    Ki K2 1(3 K4 K5 K6 Al A2 A3 A4 C  TOPIC:
RO    SRO 024AG2.l.23 Emergency Boration / 1            4.3  4.4                                  Ability to perform specific system and integrated plant procedures during all modes of plant operation.
033AG2.2.44 Loss of Intermediate Range NI / 7 4.2  4.4                                  Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions WEO1 EA2.l  Rediagnosis / 3                  3.2  4                                    Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
WE16EA2.2  High Containment Radiation / 9    3.0  3.3                                  Adherence to appropriate procedures and operation LI LI LI LI LI LI LI    LI LI LI within the limitations in the facilitys license and amendments.
Page 1 of 1                                                  10/04/2013 9:30AM
ES-401, REV 9                                      SRO T2GI PWR EXAMINATION OUTLINE                                                FORM ES-401-2 KA        NAME I SAFETY FUNCTION:                  IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 004G2.2.22 Chemical and Volume Control          4.0  4.7                                Knowledge of limiting conditions for operations and safety limits.
013A2.03  Engineered Safety Features Actuation 4.4  4.7                                Rapid depressurization 059A2.0l  Main Feedwater                      3.4  3.6                                Feedwater actuation of AFW system 061G2.4.49 Auxiliary/Emergency Feedwater        4.6  4.4                                Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
078A2.01  Instrument Air                      2.4  2.9                                Air dryer and filter malfunctions Page 1 of 1                                              10/04/2013 9:30AM
ES-401, REV 9                            SRO T2G2 PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME I SAFETY FUNCTION:        IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 017G2.4.47 In-core Temperature Monitor 4.2  4.2                                Ability to diagnose and recognize trends in an accurate J
and timely manner utilizing the appropriate control room reference material.
056A2.04  Condensate                  2.6  2.8                                Loss of condensate pumps 075G2.2.44 Circulating Water          4.2  4.4                                Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Page 1 of 1                                                10/04/2013 9:30AM
ES-401, REV 9                              SRO T3 PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME/SAFETY FUNCTION:          IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO G2.l.25    Conduct of operations      3.9  4.2                                Ability to interpret reference materials such as graphs,
[
monographs and tables which contain performance data.
G2.l .32  Conduct of operations      3.8    4.0                                Ability to explain and apply all system limits and precautions.
G2.2.13    Equipment Control          4.1    4.3                                Knowledge of tagging and clearance procedures.
D L D          L fl G2.2.18    Equipment Control          2.6    3.8                                Knowledge of the process for managing maintenance D LI LI LI LI LI LI activities during shutdown operations.
G2.3.ll    Radiation Control          3.8    4.3                                Ability to control radiation releases G2.3.12    Radiation Control          3.2    3.7                                Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.28    Emergency Procedures/Plans 3.2  4.1                                  Knowledge of procedures relating to emergency response to sabotage.
Page 1 of 1                                                10/04/2013 9:30AM
ES-301                              Administrative Topics Outline                                    Form ES-301-1 Facility: __Surry_________________________                              Date of Examination: __7/21/14_____
Examination Level: RO                                                    Operating Test Number: _SR14-301_
Administrative Topic            Type                      Describe activity to be performed (see Note)                Code*
Quadrant Power Tilt Ratio Conduct of Operations                  R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Conduct of Operations Perform a review of OPT-FW-006 Equipment Control                      R/M K/A:G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control                      R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Obtain Required Information IAW EPIP-2.01 Emergency Procedures/Plan              R/N      K/A: G2.4.39 Knowledge of RO responsibilities in emergency plan implementation. RO: 3.9 / SRO: 3.8.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301                              Administrative Topics Outline                                    Form ES-301-1 Facility: ___Surry_______________________                                Date of Examination: _7/21/14_____
Examination Level:          SRO                                          Operating Test Number: _SR14301__
Administrative Topic            Type                      Describe activity to be performed (see Note)                Code*
Quadrant Power Tilt Ratio Conduct of Operations                  R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations                  S/M K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8
                                                  / SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control                      R/M K/A: G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO:
4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control                      R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Classify and Determine PAR for General Emergency Emergency Procedures/Plan              R/N      K/A: G2.4.41 Knowledge of the emergency action level thresholds and classifications. RO: 2.9 / SRO: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301                              Control Room/In-Plant Systems Outline                          Form ES-301-2 Facility: ___Surry _____________________                                Date of Examination: _7/21/14______
Exam Level: RO                                                          Operating Test No.: _SR14301______
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function
: a. Respond to Control Rod Withdrawal                                              M/S/A                    1
: b. Perform an Alternate Dilute                                                    N/S                      2
: c. Configure Containment Spray IAW ECA-1.1                                        D/S/EN/L                  5
: d. Re-establish Normal Letdown Following SI                                      D/S/A/L                  3
: e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2                        D/S                      4S
: f. Remove SR NIs From Service During a Reactor Startup                            M/S/L                    7
: g. Respond to a Low Level Transient                                              D/S                      8
: h. Respond to a #3 EDG Start Failure                                              N/A/S                    6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Locally Transfer Individual Components to the Aux Shutdown                    D/L/E                    8 Panel
: j. Isolate Service Water to MER #3                                                D/A/L/E                  3
: k. Locally Swap U-2 AFW to Fire Water                                            M/A/L/E/R                4S
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                  Criteria for RO / SRO-I / SRO-U RO                  Actual          Criteria Met (A)lternate path                                                  4-6                    5                YES (D)irect from bank                                                9                    6                YES (E)mergency or abnormal in-plant                                  1                    3                YES (EN)gineered safety feature (L)ow-Power / Shutdown                                            1                    6                YES (N)ew or (M)odified from bank including 1(A)                      2                    5                YES (P)revious 2 exams (randomly selected)                            3                    0                YES (R)CA                                                              1                    1                YES (S)imulator / (C)ontrol room
ES-301                              Control Room/In-Plant Systems Outline                          Form ES-301-2 Facility: __Surry ______________________                                Date of Examination: _7/21/14______
Exam Level: SRO-I                                                        Operating Test No.: _SR14301______
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*          Safety Function
: a. Respond to Control Rod Withdrawal                                              M/S/A                    1
: b. Perform an Alternate Dilute                                                    N/S                      2
: c. Configure Containment Spray IAW ECA-1.1                                        D/S/EN/L                5
: d. Re-establish Normal Letdown Following SI                                        D/S/A/L                  3
: e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2                        D/S                    4S
: f. Remove SR NIs From Service During a Reactor Startup                            M/S/L                    7
: g. Respond to a Low Level Transient                                                D/S                      8 h.
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Locally Transfer Individual Components to the Aux Shutdown                      D/L/E                    8 Panel
: j. Isolate Service Water to MER #3                                                D/A/L/E                  3
: k. Locally Swap U-2 AFW to Fire Water                                              M/A/L/E/R              4S
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                  Criteria for RO / SRO-I / SRO-U SROI                  Actual        Criteria Met (A)lternate path                                                  4-6                    4                YES (D)irect from bank                                                8                    6                YES (E)mergency or abnormal in-plant                                  1                    3                YES (EN)gineered safety feature (L)ow-Power / Shutdown                                            1                    6                YES (N)ew or (M)odified from bank including 1(A)                      2                    4                YES (P)revious 2 exams (randomly selected)                            3                    0                YES (R)CA                                                            1                    1                YES (S)imulator / (C)ontrol room
ES-301                              Control Room/In-Plant Systems Outline                          Form ES-301-2 Facility: _Surry________________________                                Date of Examination: _7/21/14______
Exam Level: SRO-U                                                        Operating Test No.: _SR14301______
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function
: a. Respond to Control Rod Withdrawal                                              M/S/A                    1
: b. Perform an Alternate Dilute                                                    N/S                      2
: c. Configure Containment Spray IAW ECA-1.1                                        D/S/EN/L                  5 d.
e.
f.
g.
h.
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. Locally Transfer Individual Components to the Aux Shutdown                    D/L/E                    8 Panel j.
: k. Locally Swap U-2 AFW to Fire Water                                            M/A/L/E/R                4S
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                  Criteria for RO / SRO-I / SRO-U SROUI                Actual          Criteria Met (A)lternate path                                                  2-3                    2                YES (D)irect from bank                                                4                    2                YES (E)mergency or abnormal in-plant                                  1                    2                YES (EN)gineered safety feature                                      1                    1                YES (L)ow-Power / Shutdown                                            1                    2                YES (N)ew or (M)odified from bank including 1(A)                      1                    3                YES (P)revious 2 exams (randomly selected)                            2                    0                YES (R)CA                                                            1                    1                YES (S)imulator / (C)ontrol room
ES-301                                              Operating Test QuaUty Checklist                                      Form ES-301-3 Facility:      Surry                  Date of Examination: Week of 7/21 & 7/28/14            Operating Test Number: SR3Ot-2014 Initials
: 1. General Criteria a        b*    c#
: a.            The operating test conforms with the previously approved outline: changes are consistent with                .
sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution),
: b.            There is no day-to-day repetition between this and other operating tests to be administered during this examination.
: c.            The operating test shall not duplicate items from the applicants audit test(s). (see Section 0. 1.
a.)                PC      A.
: d.            Overlap with the written examination and between different parts of the operating test is within        -p.,
acceptable limits.
: e.            It appears that the operating test will differentiate between competent and less-than-com petent applicants at the designated license level.
: 2. Walk-Through Criteria                                                  --        --
: a.          Each JPM includes the following, as applicable:
* 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
* operationally important specific performance criteria that include:
detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important obseivations 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 sequence of steps, if applicable
: 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 distribution, bank use, repetition from the last 2 NRC examinations) specified                f on those forms and Form ES-201-2.
: 3. Simulator Criteria                                                -_        --
The associated simulator operating tests (scenario sets) have been reviewed in accordance with                            j Form ES-301-4 and a copy is attached.
Printed Name I Signature                                        Date
: a. Author                              Michael R. Meyer!                      1                                      ?
: b. Facility Reviewer()                Rich Philpot!                                                                        1,-I.
7/
: c. NRC Chief Examiner (#)              David Lan                                                                                V C1i-r
: d. NRC Supervisor
                                                                      /                                                7(n  (
NOTE:              The facility signature is not applicable for NRC-developed tests.
              #    Independent NRC reviewer initial items in Column c: chief examiner concurrence required.
ES-301                                    Simulator Scenario Quality Checklist                                    Form ES3O1-4 Facility: Surry        Date of Exam; Week of 8/21 & 8)28/14 Scenano Numbers: 1/ 2/ 3/4/5              Operating Test No.: SR3OI-2014 QUALITATIVE ATTRIBUTES                                                        Inibals a    b*      c#
: 1.        The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.
: 2.        The scenarios consist mostly of related events.                                                              ?)
: 3.          Each event description consists of
              . the point in the scenario when it is to be initiated a    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)                                                            V a    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.                                            7i-    (j,  -
: 8.      Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
: 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.
: 8.      The simulator modeling is not altered.                                                                      7\    (      .:;z
: 9.      The scenarios have been validated, 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.
L    i_.
: 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 of ES-301,                            2i            .t(
11,        All individual operator competencies can be evaluated, as verified using Form ES-301-6 12.
(submit the form along with the simulator scenarios).
Each applicant will be significantly involved in the minimum number of transients and events 22    L.      i specified on Form ES-301-5 (submit the form with the simulator scenarios).                                rN
: 13.      The level of difficulty is appropriate to support licensing decisions for each crew position.
jj Target Quantitative Attributes (Per Scenario; See Section DSd)                        Actual Attributes      --            --
: 1.      Total malfunctions (58)                                                                  6/ 6/ 5/ 5 Q
: 2.        Malfunctions after EOP entry (12)                                                        3/2/3) 2                ic
: 3.      Abnormal events (24)                                                                      4/51 5! 5
: 4.        Major transients (12)                                                                    1/ 1/ 1/ 1 22.. iL.
: 5.        EOPs entered/requiring substantive actions (12)                                          2/1! 1/ 2          71,  (      7, 6.
EOP contingenctes requiring substantive actions (02) 1/ 1/ 1/0          7    flt i-
: 7.      Critical tasks (23)                                                                      2/2/ 3/ 2                (
ES-301                        Transient and Event Checklist                        Form ES-301-5 Facility:                            Date of Exam:                  Operating Test No.:
A        E                                      Scenarios P        V        1                3                4                5          T      M P        E                                                                        O      I L        N      CREW          CREW              CREW              CREW          T      N I        T  POSITION        POSITION          POSITION          POSITION        A I
M C            S    A  B    S      A    B    S    A    B      S    A    B    L    U A        T  R    T  O    R      T    O    R    T    O    R    T    O          M(*)
N        Y  O    C  P    O      C    P    O    C    P    O    C    P R    I  U T        P E
RO        RX        5                5                6                1          1,1,  1  1  0 1,1 SRO-I    NOR                                                                        0    1  1  1 I/C        2,6              2,                2,4,              3,5        2,3,  4  4  2 SRO-U                                4,                6                ,6,        3,4 6                                  8 MAJ        7,8              8,                7,8              7          2,2,  2  2  1 9                                              2,1 TS                                                                        0    0  2  2 RX                                                                        0    1  1  0 RO        NOR            1,5              5                  6                1    2,1,  1  1  1 1,1 SRO-I    I/C            3,4,            3,7,9              3,5,9            2,4,  4,3,  4  4  2 6,9                                                  ,8    3,3 SRO-U    MAJ            7,8              8,9                7,8              7    2,2,  2  2  1 2,1 TS                                                                        0    0  2  2 RO        RX  5              5                  6                1                1,1,  1  1  0 1,1 SRO-I    NOR  1                                                                    1,0,  1  1  1 0,0 SRO-U    I/C  2,3,4          2,3,4,            2,3,4,            2,3,4,            5,6,  4  4  2
              ,6,9          6,7,9              5,6,9            5,6,8            6,6, MAJ  7,8                    8,        7,8              7                2,2,  2  2  1 9                                              2,2 TS  1,2,3          3,4,6              2,3,5,            2,5              3,3,  0  2  2 7                  6                                  4,4 RO        RX  5              5                  6                1                1,1,  1  1  0 1,1 SRO-I    NOR  1                                                                    1,0,  1  1  1 0,0 SRO-U    I/C  2,3,4          2,3,4,            2,3,4,            2,3,4,            5,6,  4  4  2
              ,6,9          6,7,9              5,6,9            5,6,8            6,6, MAJ  7,8                    8,        7,8              7                2,2,  2  2  1 9                                              2,0 TS  1,2,3          3,4,6,            2,3,5,            2,5              3,4,  0  2  2 7                  6                                  4,2
ES-301                                  Competencies Checklist                                Form ES-301-6 Facility: Surry Power Station    Date of Examination: 7/21/14          Operating Test No.: SR301-2014 APPLICANTS RO                      SRO-I                      SRO-U Competencies SCENARIO                  SCENARIO                    SCENARIO 1      3      4    5    1      3      4      5      1      3    4    5 Interpret/Diagnose            2,3,4  2,3,4  2,3,4 2,3,4 2,3,4  2,3,4  2,3,4, 2,3,4, 2,3,4  2,3,4 2,3,4 2,3,4,
                                ,5,6  ,5,6,  ,5,6,  ,5,6  ,5  ,5,6,  5,6,7,  5,6    ,5  ,5,6, ,5,6,  5,6 Events and Conditions                  8,9    7,8                8,9      8                    8    7,8 Comply With and                  All    All    All    All  All  All    All    All    All    All  All  All Use Procedures (1)
Operate Control                ALL    ALL    2,3,4 ALL  2,5,6  N/A    2,4,6, 1,3,5,  N/A    N/A  N/A  N/A
                                              ,5,6,        ,7,8          7,8  6,7,8 Boards (2)                                    7,8,9 Communicate                    ALL    ALL    All    All  All  All    All    All    All    All  All  All and Interact Demonstrate                    N/A    N/A    N/A  N/A    All  All    All    All    All    All  All  All Supervisory Ability (3)
Comply With and                N/A    N/A    N/A  N/A  1,2,3  3,4,6  2,3,5,  2,5  1,2,3  3,4,6 2,3,5  2,5
                                                                    ,7      6            ,4          ,6 Use Tech. Specs. (3)
Notes:
(1)      Includes Technical Specification compliance for an RO.
(2)      Optional for an SRO-U.
(3)      Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
ES-401                                    Written Examination Quality Checklist                                  Form ES-401-6 Facility Surry Power Station                                                Date of Exam:          Exam Level: RO    X  SRO  X Initial Item Description                                                a    b*      c
: 1.          Questions and answers are technically accurate and applicable to the facility.
: 2.          a.            NRC K/As are referenced for all questions.
: b.            Facility learning objectives are referenced as available.
: 3.          SRO questions are appropriate in accordance with Section D.2,d of ES401                                    (ZP
: 4.          The samphng process was random and systematic (If more than 4 RO or 2 SRO questions                Nose 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:
the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started: or X 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                    19/0        25/28    56172 question_distribution(s)_at_right.
: 7.          Between 50 and 60 percent of the questions on the RO                Memory            C/A exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly 45/16          55/84 selected K/As support the higher cognitive levels: enter the actual RO I SRO question distribution(s) at right.
: 8.          References/handouts provided do not give away answers or aid in the elimination of distractors.
: 9.          Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.                                                                                  i      L
: 10.          Question psychometric quality and format meet the guidelines in ES Appendix B.                      .-.
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.                                        f Printed Name / Signature                                Date
: a. Author                                            MichaelR Meyer /
: b. Facility Reviewer (*)                            Rich Philpot /        .      iLj
: c. NRC Chief Examiner (#)                            David Lanyi_/              O
: d. NRC Regional Supervisor                              .I-4  IAA&#xe7;\jy.
                                                                                  /      ..                                )
Note:          The facility reviewers initialslsignature are not applicable for NRC-developed examinations.
Independent NRC reviewer initial items in Column c; chief examiner concurrence required, Note 1: Sample Plan provided by Chief Examiner Ken Schaaf, and amended by Chief Examiner Amanda Toth.
ES-401                                                Written Examination Review Worksheet                                                      Form ES-401-9
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus                Dist.        Link          units ward K/A Only 1    H    2                          X                                              N  E  001AG2.1.20, Continuous Rod With-drawal / 1, Ability to execute procedure steps.
K/A is met.
D is not plausible. Without any idea that there might be a stuck rod, why would anyone EB.
6/04/14 Make look like D except normal boraton. For B add IAW GOP 6/18/14 SAT as revised.
2    H    3                          X                                              N  E  003G2.4.50, Reactor Coolant Pump / 4P, Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
K/A is met.
I think the way the answers are written, C and D are not plausible.
Rearrange the answers like the ARP would do it.
C. Trip the Reactor and initiate 1-E-0; Go to 1-AP-9.02, Loss of RCP Seal Cooling. STOP the affected RCP and after 5 minutes CLOSE Pressurizer Spray Valve from Loop A..
D. Go to 1-AP-9.00, RCP Abnormal Conditions. Initiate an orderly shutdown, then CLOSE Pressurizer Spray Valve from Loop A.
STOP the affected RCP.
6/4/14 Based upon the above indications, what AP should be entered? Should the reactor be tripped or not?
6/18/14 SAT as revised.
036AA1.04, Fuel Handling Accident / 8, Ability to operate and / or 3    F    2            X                                                            B  E monitor the following as they apply to the Fuel Handling Incidents:
Fuel handling equipment during an incident.
K/A is met.
Change the second bullet to state that the Fuel Handlers have stopped withdrawing the assembly from the core while doing a visual exam. Make it clear that it is still in the core.
Is this something you expect your ROs to know?
6/4/14 Add cavity level. Fuel fully withdrawn. AP-22.00 or AP-22.01? Then choice A and C but in vertical position.
6/18/14 SAT as revised.
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                  Explanation Focus                Dist.        Link          units ward K/A Only 4  H    3                                                                            S  004K5.06, Chemical and Volume Control / 1 & 2, Knowledge of the operational implications of the following, Concept of boron worth or inverse boron worth (reactivity, pcm/ppm).
K/A is met.
Do you expect your ROs to know the note about how to set the integrator without the procedure?
Although you have 4 different valuesfor the second answer, I see that it is really only 2 (-2 from calculation or -4 from calculation).
5  F    2                                                                        B  S  005K5.09, Residual Heat Removal / 4, Knowledge of the operational implications of the following concepts as they apply the RHRS:
Dilution and boration considerations.
K/A is met.
Reword B to state a calculation is performed to ensure RHR volume combined with RCS volume will not dilute below minimum required boron.
6  H    2                                                                        N  S  006K4.11, Emergency Core Cooling / 3, Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Reset of SIS.
K/A is met.
7  H    3                          X                                              B  E  007A1.02, Pressurizer Relief/Quench Tank / 5, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:,Maintaining quench tank pressure.
K/A is met Change the second question to read The lowest pressure Change fourth bullet to state  63% and slowly rising 6/4/14. SAT as revised.
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus                Dist.        Link          units ward K/A Only 8  H    3    X                                                                  N  U  007EK1.02, Reactor Trip - Stabilization - Recovery / 1, Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Shutdown margin.
K/A is met.
Change stem to read Which one of the following data sets describes the required boron concentration to maintain Shutdown Margin in the time period between 0 to 36 hours following the reactor trip? Assume no further operator actions other than maintaining RCS temperature?
As written A and C could both be correct. Both would provide adequate SDM. Without specific values to calculate SDM.
This might work if you specified the minimum required boron concentration.
6/4/14 Change question to ask if boration is required at 12 and 36 hours.
6/18/14 SAT as revised.
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
: 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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
: 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
: 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
: 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
ES-401                                                                      2                                                                Form ES-401-9
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 9  F    2                        X                                              B  E  027K2.01, Containment Iodine Removal / 5, Knowledge of bus power supplies to the following:, Fans K/A is met.
This is fine as long there is no ability to operate these fans locally. It looks like ND-88.4-LP-6 says that they can be operated at their individual breakers.
6/4/14 Sat as revised. First bullet states only leak has been identified.
008AA1.06, Pressurizer Vapor Space Accident/ 3, Ability to operate 10  H    3    X      X          X                                              M  U and / or monitor the following as they apply to the Pressurizer Vapor Space Accident: Control of PZR level.
K/A is met.
This is strange as written. The question asks what you should do and the aswers have things you shouldnt do.
How about you ask which pumps should be operating and your answers can be: None, B Charging, B LHSI, Both.
6/4/14. Remove 5 minutes. Comma after lowered.
6/18/14 SAT as revised.
11  F    2                        X                                              N  E  008K3.03, Component Cooling Water / 8, Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:,
RCP.
K/A is met.
Not very discerning. A better question would be WOOTF, if any, with answers of None, A, B&C, All.
6/4/14. Move if any to after RCPs.
6/18/14 SAT as revised.
009EK3.05, Small Break LOCA / 3, Knowledge of the reasons for the 12  F    3    X                                                                N  E following responses as the apply to the small break LOCA:, CCWS radiation alarm.
K/A is met.
Change question to read is the most likely cause.
6/4/14. Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 13  H    2                        X                                              B  U  010K1.06, Pressurizer Pressure Control / 3, Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems, CVCS.
K/A is met.
C is the only plausible answer. If there is only one valve in AUTO in the system, any operator is going to chose that to adjust something.
I dont have a copy of OP-RC-003. Is there a preocedural method to control the system in manual?
6/4/14. Add limits on discrimantors.
6/24/14 SAT as revised.
14  F    2                                                                      B  S  010K4.01, Pressurizer Pressure Control / 3, Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for the following, Spray valve warm-up.
K/A is met.
011EA2.10, Large Break LOCA / 3, Ability to determine or interpret 15  H    2    X                                                                N  E the following as they apply to a Large Break LOCA: Verification of adequate core cooling.
K/A is met.
Change the cue to read and cannot be manually started.
Delete the initial conditions. They are redundant..
6/4/14 Sat as revised.
16  H    3                                                              X        N  U  012K6.11, Reactor Protection / 7, Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Trip setpoint calculators.
K/A is NOT met.
This is close, but the K/A requires a loss or malfunction of the trip setpoint calculator. Change this to cause a failure in the pressure instrument input and it will meet the K/A.
Can the fourth bullet read failed high?
6/4/14 Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 17  H    3    X                  X                                              B  E  013K2.01, Engineered Safety Features Actuation / 2, Knowledge of bus power supplies to the following: ESFAS/safeguards equipment control.
K/A is met.
Change question to read WOOTF states a reason that a specific sequence is recommended by 1-AP-10.06, Loss of DC Power, when restoring power following a loss of a DC Bus?
Change answer C to To allow early restoration of letdown.
6/4/14 Sat as revised.
18  H    4    X                                                                N  E  013K6.01, Engineered Safety Features Actuation / 2, Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors.
K/A is met.
Add if any to the stem of the question.
Correct answer D Si to SI (typo).
6/4/14 Sat as revised.
19  F    3                                                                      M  S  015A4.02, Nuclear Instrumentation / 7, Ability to manually operate and/or monitor in the control room: NIS indicators.
K/A is met.
20  H    3                                                                      M  E  015AK3.01, RCP Malfunctions /I 4, Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) : Potential damage from high winding and/or bearing temperatures.
K/A is met.
Clean up the answers by breaking the answers in two. For example:
RCP Motor Upper Thrust bearing temperature is 195 oF and Rising; Annunciator RCP Frame Danger is lit.
6/4/14 Sat as revised.
21  H    3                                                                      B  S  016K1.08, Non nuclear Instrumentation / 7, Knowledge of the ph.ysical connections and/or cause effect relationships between the NNIS and the following systems: PZR PCS.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 22  F    2    X                                                                N  E  022A3.01, Containment Cooling / 5, Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation.
K/A is mostly met.
Question needs reworded. It is too complex as written.
Which ONE of the following describes:
: 1) The status of Containment Air Recirculation Fans. AND
: 2) Which Recirculation Spray Pumps are operated to maintain containment pressure less than 13 psia after containment pressure has been returned to less than atmospheric pressure.
6/4/14 SAT as revised.
23  H    3    X                                                                M  E  022AK1.03, Loss of Rx Coolant Makeup / 2, Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: Relationship between charging flow and PZR level.
K/A is met.
Change the stem to say  The following is observed:
Then put the alarms at the top of the bulleted list.
6/4/14 Sat as revised.
24  H    3    X                                                                N  E  025AA1.11, Loss of RHR System / 4, Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: Reactor building sump level indicators.
K/A is met.
An initial RCS pressure needs to be listed.
6/4/14 Initial pressure should be 300 psig. No trend required.
6/18/14 SAT as revised..
25  H    3                                                                      N  S  026A4.05, Containment Spray / 5, Ability to manually operate and/or monitor in the control room: Containment spray reset switches.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 26  H    3                                                                      B  U  026AA2.01, Loss of Component Cooling Water / 8, Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS.
K/A is met.
Too similar to RO question 12.
Are there any CC auto isolations at Surry? If so, use that tack.
Otherwise look for potential sump indications.
If you use this question instead of 12, give an RCS pressure and temperature in the initial conditions, but dont tell them that they are not on RHR yet.
6/4/14. Sat as revised.
27  F    2                                                                      B  S  026K4.09, Containment Spray / 5, Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover).
K/A is met.
28  H    3    X                                                                B  E  007K5.02, Pressurizer Relief/Quench Tank / 5, Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR.
K/A is met.
Do you normally use pressurizer heaters to support RCS heatup below 195 &deg;F? If so, please specify which heaters are energized in the IC. Otherwise have the IC state that the heaters are off.
6/4/14. Sat as revised.
29  F    2    X                                                                M  E  028K5.03, Hydrogen Recombiner and Purge Control / 5, Knowledge of the operational implications of the following concepts as they apply to the HRPS: Sources of hydrogen within containment.
K/A is met.
Remove Answer the following questions from the stem.
Is the term Zircaloy Hydriding use at Surry?
6/4/14 Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 30  F    2    X                                                                B  E  029EK2.06, ATWS / 1, Knowledge of the interrelations between the breakers, relays, and disconnects following an ATWS.
K/A is met.
Change B to Open Closed Open If you wnted to then you could eliminate RTB A from the answers.
Could the question be rewritten as An inadvertent actuation of RPS A occurred?
6/4/14. Sat as revised.
31  H    2    X      X          X                                              N  E/U 033K3.02, Spent Fuel Pool Cooling /, Knowledge of the effect that a loss or malfunction of the Spent Fuel Pool Cooling System will have on the following: Area and ventilation radiation monitoring systems.
K/A is met.
How far below the low level alarm will the pool drain? Typically Ive seen syphon holes in the drain lines of SFPs. Once there, no further drainage will occur and rad levels at the crane will stanilize.
Also, how high would you expect rad level to get?
Im OK with this questioon if the conditions really could exist. Just make the last bullet become a standalone statement.
Also is it relevent that both ubits are at 100%. If so correct the grammar in the first line to state Units 1 and 2 are. Otherwise Unit 1 is 6/4/14 Sat as revised.
034K6.02, Fuel Handling Equipment / 8, Knowledge of the effect of a 32  F    2                                                                      N  S loss or malfunction on the following will have on the Fuel Handling System : Radiation monitoring systems.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 33  H    3    X                                                                N  E  004A2.26, Chemical and Volume Control / 1 & 2, Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low VCT pressure.
K/A is met.
Is it relevant that both units are at 100%? I think that stating Unit 1 is at 100% would be adequate.
Make the pressure in the stem at 16 psig and slowly lowering. This way the second part is testing that the applicant knows that there is a rupture in the VCT that requires isolating.
6/4/14. Sat as revised.
037AK3.06, Steam Generator Tube Leak./3, Knowledge of the 34  H    3                                                              X        N  S reasons for the following responses as they apply to the Steam Generator Tube Leak: Normal operating precautions to preclude or minimize SGTR.
K/A is NOT met.
The question should deal with normal operating precautions to preclude or minimize SGTR. Possibly chemistry or differential pressure or temperatures.
Also remove the statement Based on the indications answer the following questions: That is self-evident.
6/4/14. After further review question was SAT as written.
35  H    3                                                                      B  S  039A3.02, Main and Reheat Steam / 4S, Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS.
K/A is met.
36  F    2                                                              X        N  S  040AG2.2.3, Steam Line Rupture - Excessive Heat Transfer / 4, (multi-unit license) Knowledge of the design, procedural, and operational differences between units.
K/A appears to be met.
Are these valves unique to Unit 2? For example, if I wanted to crosstie Unit 1 to Unit 2, would these same valves be accessed? If so this meets the K/A.
If the above is true, could we put a fire in the U2 turbine buiding, keep the evacuation, then have U2 loose its charging pumps?
6/4/14. After further review question was SAT as written.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 37  H    3                        X                                              M  E  051AA2.02, Loss of Condenser Vacuum/4, Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.
K/A is met.
Change question to read WOOOTF shall be done first IAW 1-AP-14.00? This wil make the hoggers more plausible.
6/4/14. Sat as revised.
38  H    3    X                                                                B  E  054AK3.01, Loss of Main Feedwater /4, Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Reactor and/or turbine trip manual and automatic.
K/A is met.
Make the first two bullets Initial Conditions.
The next section should be The following occurs:
Bulletize the rest, state that the alarms lock in or words to that effect.
Remove the first question and reword the second to ask What is the reason for the action(s) required by 1-AP-21.00? If you ask the first question, the answers make some of the distractors less plausible.
6/5/14 Going back to 2X2. Which describes actions IAW AP-21.
Second part A and B. by maintaining SG water levels.
6/18/14 SAT as revised.
056AA2.54, Loss of Off-site Power / 6, Ability to determine and 39                                  X                                                E interpret the following as they apply to the Loss of Offsite Power:
Breaker position (remote and local).
K/A is met.
Make the D answer all running. This is plausible because it matches the breaker indications.
6/5/14. Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 059AK1.01, Acciental Liquid Rad Waste Rel, / 9, Knowledge of the 40  F    2    X                                                        X        N  U operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: Types & radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant.
K/A is NOT met.
This K/A isnt looking to determine if a source is contaminated or not, but rather what type of radiation (alpha, beta, gamma) and their units of intensity.
6/5/14 neutron and alpha can/cannot be detected in this room.
Correct answer.
6/18/14 SAT as revised.
41  F    2                                                              X        M  U  059K3.03, Main Feedwater / 4S, Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/Gs.
K/A is NOT met.
This case is looking for some failure in the main feed system, not S/G level control. Look at something like a heater tube failures affect.
6/5/14 load is reduced to 85% IAW procedure. Is further load reduction required? Following the load reduction, SG press be ___
than the was at 100%.
6/19/14 Correct typo in Initial Conditions. Either capitalize feedwater or dont. Cant have it both wways. Otherwise SAT.
6/25/14 SAT as revised.
42  H    3                                                                      M  S  061K6.02, Auxiliary/Emergency Feedwater / 4S, Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps.
K/A is met.
43  F    3                                                                      B  S  062A1.01, AC Electrical Distribution / 6, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Significance of D/G load limits.
K/A is met.
This is fine if these values are expected to be memorized by the applicants.
6/5/14. SAT. Required knowledge.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 44  H    3                                                                      N  E  062AA1.01, Loss of Nuclear Svc Water / 4, Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): Nuclear service water temperature indications.
K/A is met.
Make first bullet current tense.
Make the third bullet the second bullet.
6/5/14 Remove DRP info. Is Cont Pressure vs Water Temp .. met?
6/19/14. SAT as revised.
45  H    3                                                                      N  S  063G2.1.31, DC Electrical Distribution / 6, Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
K/A is mostly met.
46  H    3                        X                                              N  E  063K1.03, DC Electrical Distribution / 6, Knowledge of the physical connections and/or cause effect relationships between the DC electrical system and the following systems: Battery charger and battery.
K/A is met.
Change distractors to as follows A. Unit 1 A and Unit 2 B.
B. Unit 1 B and Unit 2 B.
C. Unit 2 A and Unit 2 B D. Unit 2 B only.
With the 2J bus de-energized, the 2B battery discharge is just about given.
6/4/14 SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 47  F    2                        X                                              N  E  064K1.03, Emergency Diesel Generator / 6, Knowledge of the physical connections and/or cause effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system.
K/A is met.
D is not plausible. If the fuel racks close off all fuel, how can the EDG idle?
6/4/14. Put automatic between specific and actions in first question.
6/19/14. SAT as revised.
48  H    2                        X                                              M  E  065AG2.1.32, Loss of Instrument Air / 8, Ability to explain and apply all system limits and precautions.
K/A is met.
B is a subset of A, therefore this would cause applicants to stay away from both answers.
6/5/14. Make two by two. Is immediate entry required? Is reactor trip required 6/19/14. SAT as revised.
071A3.02, Waste Gas Disposal / 9, Ability to monitor automatic 49  H    3                                                                      N  S operation of the Waste Gas Disposal System including: Pressure-regulating system for waste gas vent header.
K.A is met.
50  F    2                                                                      N  S  072G2.1.28, Area Radiation Monitoring / 6, Knowledge of the purpose and function of major system components and controls.
K/A is met.
51  H    3                                                                      N  S  073A2.02, Process Radiation Monitoring / 7, Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 52  F    3                                                                      M  S  074EG2.4.21, Inad Core Cooling /4, Knowledge of the parameters and logic used to assess the status of safety functions.
K/A is met.
If you have feedback that the 2 column format is better, continue to use it. Otherwise just have bulleted sentences.
53  H    3                                                                      N  S  076K2.08, Service Water / 4S, Knowledge of bus power supplies to the ESF-actuated MOVs.
K/A is met.
54  H    3            X                                                          N  S  077AK2.01, Generator Voltage and Electric Grid Disturbances / 6, Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and motors.
K/A is met.
If system voltage is at its max and you are maximizing VARs in, arent you lowering a higher than normal voltage? If so, is the answer still correct?
6/5/14. This is how the system will respond. SAT.
55  H    3                                                                      N  S  078A4.01, Instrument Air / 8, Ability to manually operate and/or monitor in the control room:Pressure gauges.
K/A is met.
56  H    3    X                                                                N  E  079K4.01, Station Air / 8, Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with lAS.
K/A is met.
Make Bullet 5 as a stand alone (non-bulleted) sentence.
Label the last 3 bullets as current condition.
6/5/14. Two by two. Location of leak. Is U2 IAC running?. Put leak on SAC discharge.
6/19/14. SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 57  F    2                                            X                        B  S  086A1.01, Fire Protection / 8, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: Fire header pressure.
K/A is met.
Do you expect your operators to know that FP-37 is on the diesel fire pump and FP-36 is on the motor driven? If this is answered yes by the Facility Rep, then this question is SAT.
6/5/14 SAT. This is requijred knowledge.
58  F    3                                                                      M  S  103A2.04, Containment / 5, Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Containment evacuation (including recognition of the alarm).
K/A is met.
59  H    3                                                                      M  S  103A3.01, Containment / 5, Ability to monitor automatic operation of the containment system, including: Containment isolation.
K/A is met.
60  F    2                                                        .              N  S  G2.1.29, Conduct of operations, Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
K/A is met.
61  F    3                                                                      N  S  G2.1.40, Conduct of operations, Knowledge of refueling administrative requirements.
K/A is met.
62  F    3                                                                      M  S  G2.1.5, Conduct of operations, Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
K/A is met.
63  F    2                                                                      M  S  G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 64  F    2                                                                      N  S  G2.2.2, Equipment Control, Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
K/A is met.
65  F    1                                            X                        B  U  G2.3.5, Radiation Control, Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
K/A is met.
A is not plausible and D is barely plausible. This is a general rad worker question. LOD =1.
6/5/14 Use N-16 monitor.
6/19/14 As written, 10% is never wrong for the first part of the question. Need to rephrase to something like the minimum power level at whichthey can be relied upon.
6/25/14 SAT as revised.
66  F    1                                                                      N  U  G2.3.7, Radiation Control, Ability to comply with radiation work permit requirements during normal or abnormal conditions.
K/A is met.
Why would any person who has worked in nuclear power pick B
anything but D. Perhaps use a survey map with an RWP and see if they can figure out if they can do a task. LOD=1.
6/5/14. Bank question used.. SAT as revised.
67  F    3                                                                      N  E  G2.4.1, Emergency Procedures/Plans, Knowledge of EOP entry conditions and immediate action steps.
K/A is met.
Modify second question to read All of the methods provided in this procedure to secure steam flow to the Main Turbine from the Control Room?
6/5/14. Sat as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 68  F    3                                                                      N  E  G2.4.32, Emergency Procedures/Plans, Knowledge of operator response to loss of all annunciators.
K/A is met.
: 1) Change second question to read Upon power restoration what is the minimum acceptable method to perform a functional check in order to confirm that alarming conditions in the field will actuate the appropriate alarm?
6/5/14. SAT as revised.
69  H    3                                                                      N  S  G2.4.4, Emergency Procedures/Plans, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
K/A is met.
70  H    2                                                                      N  S  WE03EK2.1, LOCA Cooldown Depress /4, Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
K/A is met.
71  H    3                                                                      N  E  WE04EG2.4.3, LOCA Outside Containment / 3, Ability to identify post-accident instrumentation.
K/A is met.
In the question, replace the comma with an and and the and would with a to.
6/4/14. SAT as reivsed.
72  H    3                                                                      M  S  WE05EK2.2, Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4, Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facilitys heat removal 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.
K/A is met.
Make all of the bullets except the last one part of the initial conditions.
Make the last bullet a stand alone statement.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 73  H    3                                                                      N  S  WE11EK1.3, Loss of Emergency Coolant Recirc./ 4, Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Annunciators and conditions indicating signals and remedial actions associated with the (Loss of Emergency Coolant Recirc).
K/A is met.
WE14EK2.1, Knowledge of the interrelations between the (High 74  H    3                                                                      N  S Containment Pressure) and the following: / 5 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
K/A is met.
75  F    2                                                                      N  E  WE15EK1.2, Containment Flooding / 5, Normal, abnormal and emergency operating procedures associated with (Containment Flooding).
K/A is met.
Following a Design Basis LOCA, the MINIMUM containment sump level to enter FR-Z.2, Response to Containment Flooding is
_____1)_____ feet, and entry is a(n) _____2) _____ Path.
Change a __ to a(n)___.
6/4/14. First part remains the same. Second pressure would be a red path to FR-Z.1.
6/19/14. SAT as revised.
ES-401                                                Written Examination Review Worksheet                                                    Form ES-401-9
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus                Dist.        Link          units ward K/A Only 76  H    2            X                                                            M  S  004G2.2.22, Chemical and Volume Control / 1 & 2, Knowledge of limiting conditions for operations and safety limits.
K/A is met.
Why do you feel it is necessary to provide a drawing? This should be part of system knowledge.
6/4/14. SAT as is.
77  H    3                          X                                              M  S  009EA2.39, Small Break LOCA / 3, Ability to determine or interpret adequate core cooling as it applies to a small break LOCA.
K/A is met.
Is A credible? If you dont meet RCP trip criteria, it is almost always due to subcooling. If you dont have subcooling, why would you stop SI?
78  H    3                                                                        M  S  013A2.03, Engineered Safety Features Actuation / 2, Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Rapid depressurization K/A is mostly met.
79  H    3                                                                        N  S  017G2.4.47, in-core Temperature Monitor / 7, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
K/A is met.
022AA2. 01, Loss of Rx Coolant Makeup I 2, Ability to determine 80  H    3                                                                        M  S and interpret the following as they apply to the Loss of Reactor Coolant Makeup: (CFR 43.5/ 45.13) Whether charging line leak exists.
K/A is met.
: 1. 2.        3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues    T/F    Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus                Dist.        Link          units ward K/A Only 81  H    3                          X                                              N  E  024AG2.1.23, Emergency Boration/I 1, Ability to perform specific system and integrated plant procedures during all modes of plant operation.
K/A is met.
You have four different second part answers. If this answer is known, it makes the first part irrelevent and therefore would not meet the K/A. Why not choose the Delta flux answer associated with transients and the rod insertion associated with reactor trip and have a true 2 by 2 answer?
6/4/2014 Sat as revised.
82  H    2                          X                                              M  E  027AA2.10, Pressurizer Pressure Control System Malfunction / 3, Ability to determine and Interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR heater energized/de-energized condition.
K/A is met.
Is it necessary to tell them that the Master Controller output goes to 0%? This should be testable knowledge.
Change the second part answer to read will not be solid when critical.
6/4/14 Added comma after operation in question.
6/17/14 SAT as revised.
83  H    2                                                                      X  N  U  033AG2.2.44, Loss of Intermediate Range NI / 7, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
K/A is met.
Question is NOT at SRO level. The removal of fuses is RO knowledge. Knowing that you must verify permissive light within one hour is RO knowledge.
6/4/14 Control Power fuses would/ would not be removed and make the second part ask what AP-4.0 requires.
6/17/14 SAT as revised.
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
: 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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
: 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
: 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
: 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
ES-401                                                                      2                                                              Form ES-401-9
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 84  H    2                                                                      N  S  014A2.05, Rod Position Indication / 1, Ability to (a) predict the impacts of a reactor trip on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
K/A is met.
85  H    3                                                                      N  S  057AG2.1.28, Loss of Vital AC Inst. Bus/ 6, Knowledge of the purpose and function of major system components and controls.
K/A is met.
059A2.01, Main Feedwater / 4S, Ability to (a) predict the impacts of 86  H    3                        X                                              N  E feedwater actuation of AFW system on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
K/A is met.
Change 2nd distractor to 24 hours. This is more plausible as action 22 of the AFW TS.
Is this how you want to ask the question? An alternative could be What LCO is entered? With the answers as Table 3.7-2, Action 24.
48 hours to restore. And Table 3.7-2, Action 22. 24 hours to restore.
6/4/14 Change first part to ask if TS entry is required. Provide TS 3.e and Action 24.
6/17/14 SAT as revised.
87  H    3                                                                      N  S  061G2.4.47, Auxiliary/Emergency Feedwater, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
K/A is met.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 88  H    2            X                                                          N  E  075G2.2.44, Circulating Water / 8, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
K/A is met.
You need a value and trend for intake canal leve to ensure single answer.
6/4/14 Change 25 ft and lowering.
6/17/14 SAT as revised.
078A2.01, Instrument Air /, Ability to (a) predict the impacts of the 89  H    3                                                              X        N  U following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions.
K/A is NOT met.
Need to use procedures to control or mitigate. In this case I would suggest using 1-AOP-27.00. You can ask about the need to secure RHR pumps, or about alternate cooling methods , or isolating containment.
6/4/14. SAT as rewritten.
90  H    3                                                                      M  S  G2.1.25, Conduct of operations, Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
K/A is met.
91  H    3                        X                                              N  E  G2.1.32, Conduct of operations, Ability to explain and apply all system limits and precautions.
K/A is met.
There is a subset issue here. An applicant can claim that since 68%
is less than 75%, it is always correct. So he may answer correctly without knowing the information. More clearly phrase the question to ask what the TS states.
6/4/14. What is the max time to be less than 68%. 1 hour or 30 min.
6/17/14 SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                      8.
Q# LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                                Explanation Focus              Dist.        Link          units ward K/A Only 92  F    2                        X                                              M  E  G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.
K/A is met.
Remove because of a shortage of personnel from answer D.
6/14/04. Sat as rewritten.
93  H    3                                                                      N  S  G2.2.18, Equipment Control, Knowledge of the process for managing maintenance activities during shutdown operations.
K/A is met.
94  F    2                        X                                              N  E  G2.3.11, Radiation Control, Ability to control radiation releases.
K/A is met.
Change the second part to the following:
the dose to an individual standing _________________.
: 1) at the exclusion area boundary will not exceed 0.5 rem TEDE over a 2 hour period.
: 2) in an unrestricted area will not exceed 0.002 rem in any one hour.
This second part is a Part 20 requirement that does not apply in this case.
6/4/14 Sat as rewritten.
G2.3.12, Radiation Control, Knowledge of radiological safety 95  F    2                                                              X        N  E principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
K/A is not reall met.
Since there are four different answers fo the second part of the question, the first part is not relevent. Suggest that you delete the 24 hour and 4 hour answers from the second part. This would be an adequate question then.
6/4/14 Added maximum prior to the word time in question 2. No press release is planned to be issued.
6/17/14 SAT as revised.
: 1. 2.      3. Psychometric Flaws          4. Job Content Flaws  5. Other 6. 7.                                    8.
Q#  LOK  LOD (F/H) (1-5) Stem Cues T/F      Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S                              Explanation Focus              Dist.        Link          units ward K/A Only 96    H    2            X                                                          N  E  G2.4.28, Emergency Procedures/Plans, Knowledge of procedures relating to emergency response to sabotage.
K/A is met.
I believe that 0-AOP-36.00 requires both units be tripped upon breaching the fences. If so, let the applicants know that the applicable portions of the AOP are in progess with no issues.
6/4/14 Sat as rewritten.
97    F    3                                                                          S  WE11EG2.1.32, Loss of Emergency Coolant Recirc. /4, Ability to explain and apply all system limits and precautions.
K/A is met.
98    H    3                                                                          S  WE12EG2.4.4, Steam Line Rupture - Excessive Heat Transfer /4, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
K/A is met.
99    H    2                                                                      B  S  WE16EA2.2, High Containment Radiation / 9, Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
K/A is met.
100  H    3                                                                      N  S  WE01EA2.1, Rediagnosis / 3, Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
K/A is met.
ES-403                              Written Examination Grading                    Form ES-403-1 Quality Checklist Facility: Surry                        Date of Exam: 08/05/14      Exam Level: ROj SROE Initials Item Description                              a      b      c
: 1.      Clean answer sheets copied before grading                          -2    ,ii4
: 2.      Answer key changes and question deletions justified and documented                                                                  AX
: 3.      Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)
: 4.      Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail
: 5.      All other failing examinations checked to ensure that grades are justified
: 6.      Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature                        Date
: a. Grader                          Newton Lacy
: b. Facility Reviewer(*)            N/A
: c. NRC Chief Examiner (*)          David Lanyi /
                                                                              /        /7/fy
: d. NRC Supervisor (*)
(*)      The facility reviewers signature is not applicable for e nations graded by the NRC; two independent NRC reviews are required.
ES-403, Page 6 of 6
                                                    &#xa3;x4M                                    fA/v ES-201                                    Examination Outline Quality Checklist                                  Form ES-201-2 Facility:
5_jR                                      Date of Examination:
TuL1        c.//
Initials Item                                                    Task Description
: 1.      a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
R        b. Assess whether the outline was systematically and randomly prepared in accordance with I          Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.                          (17 T
T E
: c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.                    (/9
: d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.            M i4 N
: 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, S            and major transients.
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 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          from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
: c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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                  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 T            (3) no tasks are duplicated from the applicants audit test(s)
(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 (3) no more than one task is repeated from the last two NRC licensing examinations
: c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
: 4.      a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.                                                                  2)7  it E      b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.                                7
: c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.        7 R            Check for duplication and overlap among exam sections.                                                        41:4
: d.                                                                                                          1 L      e. Check the entire exam for balance of coverage.
: f. Assess whether the exam fits the appropriate job level (RO or SRO).
: a. Author
: b. Facility Reviewer (*)
If
: c. NRC Chief Examiner (#)              1I4              -  .4ArRt
: d. NRC Supervisor                      ,tAL4Ot4 i WlPLLMJ1/
Note:                    # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
                -  WR/77EA)              &4m}}

Latest revision as of 03:57, 5 February 2020

301Section 7
ML16089A388
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/22/2016
From:
Division of Nuclear Materials Safety I
To:
Virginia Electric & Power Co (VEPCO)
References
Download: ML16089A388 (59)
v • d • e


Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Surry Date of Examination: 7/2114 8/5/14 Examinations Developed by: cit / NRC (circle one)

Chief Target Task Description (Reference) Examiners Date*

Initials

-180 1. Examination administration date confirmed (C.1.a; C.2.a and b)

-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

-120 3. Facility contact briefed on security and other requirements (C.2.c)

-120 4. Corporate notification letter sent (C.2.d)

[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] (

-75 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-3d-S. ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)

-70 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)

-45 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)

-14 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)

-14 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g)

-7 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 14. Final applications reviewed; examination approval and waiver letters sent (C.2.i; Attachment 4; ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

  • Target dates are keyed to the examination date identified in the corporate 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 to examinations prepared by the NRC.

£x4M fA/v ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

5_jR Date of Examination:

TuL1 c.//

Initials Item Task Description

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

R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. (17 T

T E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. (/9
d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. M i4 N
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, S and major transients.

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 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 from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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 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 T (3) no tasks are duplicated from the applicants audit test(s)

(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 (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. 2)7 it E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 7
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 7 R Check for duplication and overlap among exam sections. 41:4
d. 1 L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)

If

c. NRC Chief Examiner (#) 1I4 - .4ArRt
d. NRC Supervisor ,tAL4Ot4 i WlPLLMJ1/

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

Not applicable for NRC-prepared examination outlines

- WR/77EA) &4m

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

Tier Group JI RO K/A Category Points SRO-Only Points FKKKKKAAAAG[ A2 G* JTotal

  • jTotal 11234561234 L___
1. J i 3 3f3 33 3 18 3 3 6 Emergency &

Abnormal Plant

[

[

2 II N/A 1

N/A 9 2 2 4 Evolutions LTie1Tota1s 5 1 4 4 5 27 5 5 10 1 32 2 3332 3322 28 3 2 5

  • 2 11111110111 10 2 3 piant Systems Tier Totals 4 3 3 4 4 4 3 3 4 3 3 38 if 4 8
3. GenericKnowledgeandAbilities Categories

] 1 2 3 4 10 1 2 3 4 7 3 2 2 3 2 2 2 1

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the PTier Totals@

in each K/A 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 4 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

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

6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.
7. *The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section 0.1 .b of ES-401 for the applicable KAs.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics=importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43..

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR 1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 007EK1 .02 Reactor Trip Stabilization Recovery 3.4 3.8 H H H H H H H H H H Shutdown margin

/1 008AA1 .06 Pressurizer Vapor Space Accident / 3 3.6 3.6 Control of PZR level 009EK3.05 Small Break LOCA / 3 3.4 3.8 CCWS radiation alarm 011 EA2.l 0 Large Break LOCA /3 4.5 4.7 Verification of adequate core cooling 015AK3.0l RCP Malfunctions /4 2.5 3.1 LI Potential damage from high winding and/or bearing temperatures 022AK1 03 Loss of Rx Coolant Makeup / 2 3 3.4 H H Relationship between charging flow and PZR level 025AA1 .11 Loss of RHR System / 4 2.9 3 H H H H H H H H H H Reactor building sump level indicators 026AA2.01 Loss of Component Cooling Water / 8 2.9 3.5 H H H H H H H H H H Location of a leak in the CCWS 029EK2.06 ATWS / 1 2.9 3.1 H H H H H H H H H H Breakers, relays, and disconnects.

040AG2.2.3 Steam Line Rupture - Excessive Heat 3.8 3.9 LI H H H H H H H H H (multi-unit license) Knowledge of the design, procedural Transfer / 4 and operational differences between units.

054AK3.01 Loss of Main Feedwater / 4 4.1 4.4 H H H H H H H H H H Reactor and/or turbine trip, manua( and automatic Page 1 of 2 10/04/2013 9:30AM

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 056AA2.54 Loss of Off-site Power/6 2.9 3 Breaker position (remote and local)

ElElEl 062AA1.01 Loss ofNuclearSvcWater/4 3.1 3.1 Nuclear service water temperature indications ElElElEl 065AG2.l.32 LossoflnstrumentAir/8 3.8 4.0 Ability to explain and apply all system limits and El El El El El El ElElEI precautions.

077AK2.01 Generator Voltage and Electric Grid 3.1 3.2 Motors Disturbances I 6

[] El El El El El ElElElEl weO4EG2.4.3 LOCA Outside Containment / Ability to identify post-accident instrumentation.

El El El El El El El EJElE WE05EK2.2 Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary Secondary Heat Sink / 4 El El El El El El ElElElEl coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 1 EK1 .3 Loss of Emergency Coolant Recirc. / 4 3.6 4.0 Annunciators and conditions indicating signals, and El remedial actions associated with the (Loss of Emergency Coolant Recir).

Page 2 of 2 10/04/2013 9:30AM

ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO1AG2.1 .20 Continuous Rod Withdrawal I 1 4.6 4.6 H H H H H H H H H Ability to execute procedure steps.

036AA1.04 Fuel Handling Accident/8 3.1 3.7 Fuel handling equipment during an incident 037AK3.06 Steam Generator Tube Leak) 3 3.6 4.1 H H H H H H H H H H Normal operating precautions to preclude or minimize SGTR 051AA2.02 Loss of Condenser Vacuuml4 3.9 4.1 Conditions requiring reactorand/orturbine trip 059AK1.0l Accidental Liquid RadWaste Rel. / 9 2.7 3.1 Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 074EG2.4.21 mad. Core Cooling /4 4.0 4.6 H H H H H H H H H H Knowledge of the parameters and logic used to assess the status of safety functions WEO3EK2.1 LOCA Cooldown Depress. /4 3.6 4.0 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE14EK2.l Loss of CTMT Integrity / 5 3.4 3.7 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEI 5EK1 .2 Containment Flooding /5 2.7 2.9 H H H H H H H H H H Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003G2.4.50 Reactor Coolant Pump 4.2 4.0 Ability to verify system alarm setpoints and operate controls Li J identified in the alarm response manual.

004A2.26 Chemical and Volume Control 2.8 3.0 Low VCT pressure LI 0041(5.06 Chemical and Volume Control 3.0 3.3 Concept of boron worth or inverse boron worth Li [] Li fl (reactivity, pcmlppm) 005K5.09 Residual Heat Removal 3.2 3.4 Dilution and boration considerations 006K4.ll EmergencyCoreCooling 3.9 4.2 ResetofSlS Li LI 007A1 .02 Pressurizer Relief/Quench Tank 2.7 2.9 j Maintaining quench tank pressure J

007K5.02 Pressurizer Relief/Quench Tank 3.1 34 Method of forming a steam bubble in the PZR Li Li Li Li IJ Li Li Li Li Li Li 008K3.03 Component Cooling Water 4.1 4.2 RCP Li Li Li Li Li Li Li Li Li [1 O1OK1.06 PressurizerPressureControl 2.9 3.1 CVCS Li Li Li Li Li Li Li Li Li 0101(4.01 PressurizerPressureControl 2.7 2.9 Sprayvalvewarm-up Li Li Li Li Li Li Li Li Li Li 012K6.ll Reactor Protection 2.9 2.9 Trip setpoint calculators Li Li Li LI Li []

Page 1 of 3 10/04/2013 9:30AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KP NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 01 3K2.0l Engineered Safety Features Actuation 3.6 3.8 LI ESFAS/safeguards equipment control LI LI LI LI LI LI C] C] LI 013K6.0l Engineered Safety Features Actuation 2.7 3.1 C] C] C] Sensors and detectors C] C] C]

022A3.01 Containment Cooling 4.1 4.3 Initiation of safeguards mode of operation C] LI LI LI LI LI LI LI LI LI 026A4.05 Containment Spray 3.5 3.5 Containment spray reset switches LI LI LI LI LI LI LI LI LI LI 026K4.09 Containment Spray 3.7 4.1 Prevention of path for escape of radioactivity from LI LI LI LI LI LI LI LI LI LI containment to the outside (interlock on RWST isolation after swapover) 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS LI LI LI C] LI LI LI LI LI LI 059K3.03 Main Feedwater 3.5 3.7. S/GS LI LI ] LI LI LI LI LI LI LI LI 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps LI C] LI LI LI LI LI LI LI LI 062A1 .01 AC Electrical Distribution 3.4 3.8 Significance of DIG load limits LI LI LI LI LI LI ] LI LI LI LI 063G2.1 .31 DC Electrical Distribution 4.6 4.3 Ability to locate control room switches, controls and LI C] LI LI LI LI LI LI LI LI indications and to determine that they are correctly reflecting the desired plant lineup.

063K1.03 DC Electrical Distribution 2.9 3.5 Battery charger and battery LI LI LI LI LI LI LI LI LI C]

Page 2 of 3 10/04/2013 9:30 AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064K1 .03 Emergency Diesel Generator 3.6 4.0 Diesel fuel oil supply system LI 073A2.02 Process Radiation Monitoring 2.7 3.2 Detector failure LI LI LI LI LI LI LI LI LI LI 076K2.08 Service Water 3.1 3.3 ESF-actuated MOVs LI LI LI LI LI LI LI LI LI LI 078A4.01 InstrumentAir 3.1 3.1 Pressure gauges LI LI LI LI LI LI LI LI LI ] LI 103A2.04 Containment 3.5 3.6 Containment evacuation (including recognition of the alarm)

LI LI LI LI LI LI LI LI LI LI 103A3.01 Containment 3.9 4.2 Containment isolation LI LI LI LI LI LI LI LI LI LI Page 3 of 3 10/04/2013 9:30 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 015A4.02 Nuclear Instrumentation 3.9 39 NIS indicators El 016K1.08 Non-nuclearlnstrumentation 3 PZRPCS El El El El El El El El El El 027K2.O1 Containment Iodine Removal 3.1 3.4 Fans 028K5.03 Hydrogen Recombiner and Purge 2.9 3.6 Sources of hydrogen within containment Control 033K3.02 Spent Fuel Pool Cooling 2.8 3.2 Area and ventilation radiation monitoring systems El 034K6.02 Fuel Handling Equipment 2.6 3.3 Radiation monitoring systems 071A3.Ol Waste Gas Disposal 2.6 2.7 HRPS El El El El El El El El El El 072G2.l.28 Area Radiation Monitoring 4.1 4.1 Knowledge of the purpose and function of major system El El El El El El El El El El components and controls.

079K4.O1 Station Air 2.9 3.2 Cross-connect with lAS El El El El El El El El El El 086A1 .01 Fire Protection 2.9 3.3 Fire header pressure El El El El El El El El El El Page 1 of 1 10/04/2013 9:30 AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.29 Conduct of operations 4.1 4.0 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.l.40 Conduct of operations 2.8 3.9 Knowledge of refueling administrative requirements G2.1 .5 Conduct of operations 2.9 3.9 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.2.13 Equipment Control 4.1 4.3 Knowledge of tagging and clearance procedures.

G2.2.2 Equipment Control 4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements J

during normal or abnormal conditions G2.4.1 Emergency Procedures/Plans 4.6 4.8 Knowledge of EOP entry conditions and immediate action steps.

G2.4.32 Emergency Procedures/Plans 3.6 4.0 Knowledge of operator response to loss of all annunciators.

G2.4.4 Emergency Procedures/Plans 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30 AM

ES-401, REV 9 SRO TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 009EA2.39 Small Break LOCA I 3 Adequate core cooling 022AA2.0l Loss of Rx Coolant Makeup /2 3.2 3.8 Whether charging line leak exists 027AA2.lO Pressurizer Pressure Control System 3.3 3.6 jrj PZR heater energized/de-energized condition Malfunction / 3 057AG2.1 .28 Loss of Vital AC Inst. Bus 16 4.1 4.1 Knowledge of the purpose and function of major system components and controls.

well EG2.l .32 Loss of Emergency Coolant Recirc. / 4 3.8 4.0 Ability to explain and apply all system limits and precautions.

wel2EG2.4.4 Steam Line Rupture Excessive Heat 4.5 4.7 Ability to recognize abnormal indications for system Transfer I 4 operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 1(3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 024AG2.l.23 Emergency Boration / 1 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

033AG2.2.44 Loss of Intermediate Range NI / 7 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions WEO1 EA2.l Rediagnosis / 3 3.2 4 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE16EA2.2 High Containment Radiation / 9 3.0 3.3 Adherence to appropriate procedures and operation LI LI LI LI LI LI LI LI LI LI within the limitations in the facilitys license and amendments.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 004G2.2.22 Chemical and Volume Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

013A2.03 Engineered Safety Features Actuation 4.4 4.7 Rapid depressurization 059A2.0l Main Feedwater 3.4 3.6 Feedwater actuation of AFW system 061G2.4.49 Auxiliary/Emergency Feedwater 4.6 4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

078A2.01 Instrument Air 2.4 2.9 Air dryer and filter malfunctions Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 017G2.4.47 In-core Temperature Monitor 4.2 4.2 Ability to diagnose and recognize trends in an accurate J

and timely manner utilizing the appropriate control room reference material.

056A2.04 Condensate 2.6 2.8 Loss of condensate pumps 075G2.2.44 Circulating Water 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.25 Conduct of operations 3.9 4.2 Ability to interpret reference materials such as graphs,

[

monographs and tables which contain performance data.

G2.l .32 Conduct of operations 3.8 4.0 Ability to explain and apply all system limits and precautions.

G2.2.13 Equipment Control 4.1 4.3 Knowledge of tagging and clearance procedures.

D L D L fl G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance D LI LI LI LI LI LI activities during shutdown operations.

G2.3.ll Radiation Control 3.8 4.3 Ability to control radiation releases G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.

Page 1 of 1 10/04/2013 9:30AM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Surry_________________________ Date of Examination: __7/21/14_____

Examination Level: RO Operating Test Number: _SR14-301_

Administrative Topic Type Describe activity to be performed (see Note) Code*

Quadrant Power Tilt Ratio Conduct of Operations R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Conduct of Operations Perform a review of OPT-FW-006 Equipment Control R/M K/A:G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Obtain Required Information IAW EPIP-2.01 Emergency Procedures/Plan R/N K/A: G2.4.39 Knowledge of RO responsibilities in emergency plan implementation. RO: 3.9 / SRO: 3.8.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry_______________________ Date of Examination: _7/21/14_____

Examination Level: SRO Operating Test Number: _SR14301__

Administrative Topic Type Describe activity to be performed (see Note) Code*

Quadrant Power Tilt Ratio Conduct of Operations R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations S/M K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8

/ SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control R/M K/A: G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO:

4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Classify and Determine PAR for General Emergency Emergency Procedures/Plan R/N K/A: G2.4.41 Knowledge of the emergency action level thresholds and classifications. RO: 2.9 / SRO: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Surry _____________________ Date of Examination: _7/21/14______

Exam Level: RO Operating Test No.: _SR14301______

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Perform an Alternate Dilute N/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove SR NIs From Service During a Reactor Startup M/S/L 7
g. Respond to a Low Level Transient D/S 8
h. Respond to a #3 EDG Start Failure N/A/S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/L/E 3
k. Locally Swap U-2 AFW to Fire Water M/A/L/E/R 4S

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U RO Actual Criteria Met (A)lternate path 4-6 5 YES (D)irect from bank 9 6 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow-Power / Shutdown 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 5 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Surry ______________________ Date of Examination: _7/21/14______

Exam Level: SRO-I Operating Test No.: _SR14301______

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Perform an Alternate Dilute N/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove SR NIs From Service During a Reactor Startup M/S/L 7
g. Respond to a Low Level Transient D/S 8 h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/L/E 3
k. Locally Swap U-2 AFW to Fire Water M/A/L/E/R 4S

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U SROI Actual Criteria Met (A)lternate path 4-6 4 YES (D)irect from bank 8 6 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow-Power / Shutdown 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 4 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Surry________________________ Date of Examination: _7/21/14______

Exam Level: SRO-U Operating Test No.: _SR14301______

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Perform an Alternate Dilute N/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/EN/L 5 d.

e.

f.

g.

h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel j.
k. Locally Swap U-2 AFW to Fire Water M/A/L/E/R 4S

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U SROUI Actual Criteria Met (A)lternate path 2-3 2 YES (D)irect from bank 4 2 YES (E)mergency or abnormal in-plant 1 2 YES (EN)gineered safety feature 1 1 YES (L)ow-Power / Shutdown 1 2 YES (N)ew or (M)odified from bank including 1(A) 1 3 YES (P)revious 2 exams (randomly selected) 2 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Operating Test QuaUty Checklist Form ES-301-3 Facility: Surry Date of Examination: Week of 7/21 & 7/28/14 Operating Test Number: SR3Ot-2014 Initials

1. General Criteria a b* c#
a. The operating test conforms with the previously approved outline: changes are consistent with .

sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution),

b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
c. The operating test shall not duplicate items from the applicants audit test(s). (see Section 0. 1.

a.) PC A.

d. Overlap with the written examination and between different parts of the operating test is within -p.,

acceptable limits.

e. It appears that the operating test will differentiate between competent and less-than-com petent applicants at the designated license level.
2. Walk-Through Criteria -- --
a. Each JPM includes the following, as applicable:
  • 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
  • operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important obseivations 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 sequence of steps, if applicable

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 distribution, bank use, repetition from the last 2 NRC examinations) specified f on those forms and Form ES-201-2.
3. Simulator Criteria -_ --

The associated simulator operating tests (scenario sets) have been reviewed in accordance with j Form ES-301-4 and a copy is attached.

Printed Name I Signature Date

a. Author Michael R. Meyer! 1  ?
b. Facility Reviewer() Rich Philpot! 1,-I.

7/

c. NRC Chief Examiner (#) David Lan V C1i-r
d. NRC Supervisor

/ 7(n (

NOTE: The facility signature is not applicable for NRC-developed tests.

  1. Independent NRC reviewer initial items in Column c: chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES3O1-4 Facility: Surry Date of Exam; Week of 8/21 & 8)28/14 Scenano Numbers: 1/ 2/ 3/4/5 Operating Test No.: SR3OI-2014 QUALITATIVE ATTRIBUTES Inibals a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.
2. The scenarios consist mostly of related events.  ?)
3. Each event description consists of

. the point in the scenario when it is to be initiated a 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) V a 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. 7i- (j, -
8. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
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.

8. The simulator modeling is not altered. 7\ ( .:;z
9. The scenarios have been validated, 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.

L i_.

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 of ES-301, 2i .t(

11, All individual operator competencies can be evaluated, as verified using Form ES-301-6 12.

(submit the form along with the simulator scenarios).

Each applicant will be significantly involved in the minimum number of transients and events 22 L. i specified on Form ES-301-5 (submit the form with the simulator scenarios). rN

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

jj Target Quantitative Attributes (Per Scenario; See Section DSd) Actual Attributes -- --

1. Total malfunctions (58) 6/ 6/ 5/ 5 Q
2. Malfunctions after EOP entry (12) 3/2/3) 2 ic
3. Abnormal events (24) 4/51 5! 5
4. Major transients (12) 1/ 1/ 1/ 1 22.. iL.
5. EOPs entered/requiring substantive actions (12) 2/1! 1/ 2 71, ( 7, 6.

EOP contingenctes requiring substantive actions (02) 1/ 1/ 1/0 7 flt i-

7. Critical tasks (23) 2/2/ 3/ 2 (

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Date of Exam: Operating Test No.:

A E Scenarios P V 1 3 4 5 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

M C S A B S A B S A B S A B L U A T R T O R T O R T O R T O M(*)

N Y O C P O C P O C P O C P R I U T P E

RO RX 5 5 6 1 1,1, 1 1 0 1,1 SRO-I NOR 0 1 1 1 I/C 2,6 2, 2,4, 3,5 2,3, 4 4 2 SRO-U 4, 6 ,6, 3,4 6 8 MAJ 7,8 8, 7,8 7 2,2, 2 2 1 9 2,1 TS 0 0 2 2 RX 0 1 1 0 RO NOR 1,5 5 6 1 2,1, 1 1 1 1,1 SRO-I I/C 3,4, 3,7,9 3,5,9 2,4, 4,3, 4 4 2 6,9 ,8 3,3 SRO-U MAJ 7,8 8,9 7,8 7 2,2, 2 2 1 2,1 TS 0 0 2 2 RO RX 5 5 6 1 1,1, 1 1 0 1,1 SRO-I NOR 1 1,0, 1 1 1 0,0 SRO-U I/C 2,3,4 2,3,4, 2,3,4, 2,3,4, 5,6, 4 4 2

,6,9 6,7,9 5,6,9 5,6,8 6,6, MAJ 7,8 8, 7,8 7 2,2, 2 2 1 9 2,2 TS 1,2,3 3,4,6 2,3,5, 2,5 3,3, 0 2 2 7 6 4,4 RO RX 5 5 6 1 1,1, 1 1 0 1,1 SRO-I NOR 1 1,0, 1 1 1 0,0 SRO-U I/C 2,3,4 2,3,4, 2,3,4, 2,3,4, 5,6, 4 4 2

,6,9 6,7,9 5,6,9 5,6,8 6,6, MAJ 7,8 8, 7,8 7 2,2, 2 2 1 9 2,0 TS 1,2,3 3,4,6, 2,3,5, 2,5 3,4, 0 2 2 7 6 4,2

ES-301 Competencies Checklist Form ES-301-6 Facility: Surry Power Station Date of Examination: 7/21/14 Operating Test No.: SR301-2014 APPLICANTS RO SRO-I SRO-U Competencies SCENARIO SCENARIO SCENARIO 1 3 4 5 1 3 4 5 1 3 4 5 Interpret/Diagnose 2,3,4 2,3,4 2,3,4 2,3,4 2,3,4 2,3,4 2,3,4, 2,3,4, 2,3,4 2,3,4 2,3,4 2,3,4,

,5,6 ,5,6, ,5,6, ,5,6 ,5 ,5,6, 5,6,7, 5,6 ,5 ,5,6, ,5,6, 5,6 Events and Conditions 8,9 7,8 8,9 8 8 7,8 Comply With and All All All All All All All All All All All All Use Procedures (1)

Operate Control ALL ALL 2,3,4 ALL 2,5,6 N/A 2,4,6, 1,3,5, N/A N/A N/A N/A

,5,6, ,7,8 7,8 6,7,8 Boards (2) 7,8,9 Communicate ALL ALL All All All All All All All All All All and Interact Demonstrate N/A N/A N/A N/A All All All All All All All All Supervisory Ability (3)

Comply With and N/A N/A N/A N/A 1,2,3 3,4,6 2,3,5, 2,5 1,2,3 3,4,6 2,3,5 2,5

,7 6 ,4 ,6 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility Surry Power Station Date of Exam: Exam Level: RO X SRO X Initial Item Description a b* c

1. Questions and answers are technically accurate and applicable to the facility.
2. a. NRC K/As are referenced for all questions.
b. Facility learning objectives are referenced as available.
3. SRO questions are appropriate in accordance with Section D.2,d of ES401 (ZP
4. The samphng process was random and systematic (If more than 4 RO or 2 SRO questions Nose 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:

the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started: or X 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 19/0 25/28 56172 question_distribution(s)_at_right.

7. Between 50 and 60 percent of the questions on the RO Memory C/A exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly 45/16 55/84 selected K/As support the higher cognitive levels: enter the actual RO I SRO question distribution(s) at right.
8. References/handouts provided do not give away answers or aid in the elimination of distractors.
9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified. i L
10. Question psychometric quality and format meet the guidelines in ES Appendix B. .-.

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. f Printed Name / Signature Date

a. Author MichaelR Meyer /
b. Facility Reviewer (*) Rich Philpot / . iLj
c. NRC Chief Examiner (#) David Lanyi_/ O
d. NRC Regional Supervisor .I-4 IAAç\jy.

/ .. )

Note: The facility reviewers initialslsignature are not applicable for NRC-developed examinations.

Independent NRC reviewer initial items in Column c; chief examiner concurrence required, Note 1: Sample Plan provided by Chief Examiner Ken Schaaf, and amended by Chief Examiner Amanda Toth.

ES-401 Written Examination Review Worksheet Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 1 H 2 X N E 001AG2.1.20, Continuous Rod With-drawal / 1, Ability to execute procedure steps.

K/A is met.

D is not plausible. Without any idea that there might be a stuck rod, why would anyone EB.

6/04/14 Make look like D except normal boraton. For B add IAW GOP 6/18/14 SAT as revised.

2 H 3 X N E 003G2.4.50, Reactor Coolant Pump / 4P, Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

K/A is met.

I think the way the answers are written, C and D are not plausible.

Rearrange the answers like the ARP would do it.

C. Trip the Reactor and initiate 1-E-0; Go to 1-AP-9.02, Loss of RCP Seal Cooling. STOP the affected RCP and after 5 minutes CLOSE Pressurizer Spray Valve from Loop A..

D. Go to 1-AP-9.00, RCP Abnormal Conditions. Initiate an orderly shutdown, then CLOSE Pressurizer Spray Valve from Loop A.

STOP the affected RCP.

6/4/14 Based upon the above indications, what AP should be entered? Should the reactor be tripped or not?

6/18/14 SAT as revised.

036AA1.04, Fuel Handling Accident / 8, Ability to operate and / or 3 F 2 X B E monitor the following as they apply to the Fuel Handling Incidents:

Fuel handling equipment during an incident.

K/A is met.

Change the second bullet to state that the Fuel Handlers have stopped withdrawing the assembly from the core while doing a visual exam. Make it clear that it is still in the core.

Is this something you expect your ROs to know?

6/4/14 Add cavity level. Fuel fully withdrawn. AP-22.00 or AP-22.01? Then choice A and C but in vertical position.

6/18/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 4 H 3 S 004K5.06, Chemical and Volume Control / 1 & 2, Knowledge of the operational implications of the following, Concept of boron worth or inverse boron worth (reactivity, pcm/ppm).

K/A is met.

Do you expect your ROs to know the note about how to set the integrator without the procedure?

Although you have 4 different valuesfor the second answer, I see that it is really only 2 (-2 from calculation or -4 from calculation).

5 F 2 B S 005K5.09, Residual Heat Removal / 4, Knowledge of the operational implications of the following concepts as they apply the RHRS:

Dilution and boration considerations.

K/A is met.

Reword B to state a calculation is performed to ensure RHR volume combined with RCS volume will not dilute below minimum required boron.

6 H 2 N S 006K4.11, Emergency Core Cooling / 3, Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Reset of SIS.

K/A is met.

7 H 3 X B E 007A1.02, Pressurizer Relief/Quench Tank / 5, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:,Maintaining quench tank pressure.

K/A is met Change the second question to read The lowest pressure Change fourth bullet to state 63% and slowly rising 6/4/14. SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 8 H 3 X N U 007EK1.02, Reactor Trip - Stabilization - Recovery / 1, Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Shutdown margin.

K/A is met.

Change stem to read Which one of the following data sets describes the required boron concentration to maintain Shutdown Margin in the time period between 0 to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following the reactor trip? Assume no further operator actions other than maintaining RCS temperature?

As written A and C could both be correct. Both would provide adequate SDM. Without specific values to calculate SDM.

This might work if you specified the minimum required boron concentration.

6/4/14 Change question to ask if boration is required at 12 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

6/18/14 SAT as revised.

Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 9 F 2 X B E 027K2.01, Containment Iodine Removal / 5, Knowledge of bus power supplies to the following:, Fans K/A is met.

This is fine as long there is no ability to operate these fans locally. It looks like ND-88.4-LP-6 says that they can be operated at their individual breakers.

6/4/14 Sat as revised. First bullet states only leak has been identified.

008AA1.06, Pressurizer Vapor Space Accident/ 3, Ability to operate 10 H 3 X X X M U and / or monitor the following as they apply to the Pressurizer Vapor Space Accident: Control of PZR level.

K/A is met.

This is strange as written. The question asks what you should do and the aswers have things you shouldnt do.

How about you ask which pumps should be operating and your answers can be: None, B Charging, B LHSI, Both.

6/4/14. Remove 5 minutes. Comma after lowered.

6/18/14 SAT as revised.

11 F 2 X N E 008K3.03, Component Cooling Water / 8, Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:,

RCP.

K/A is met.

Not very discerning. A better question would be WOOTF, if any, with answers of None, A, B&C, All.

6/4/14. Move if any to after RCPs.

6/18/14 SAT as revised.

009EK3.05, Small Break LOCA / 3, Knowledge of the reasons for the 12 F 3 X N E following responses as the apply to the small break LOCA:, CCWS radiation alarm.

K/A is met.

Change question to read is the most likely cause.

6/4/14. Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 13 H 2 X B U 010K1.06, Pressurizer Pressure Control / 3, Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems, CVCS.

K/A is met.

C is the only plausible answer. If there is only one valve in AUTO in the system, any operator is going to chose that to adjust something.

I dont have a copy of OP-RC-003. Is there a preocedural method to control the system in manual?

6/4/14. Add limits on discrimantors.

6/24/14 SAT as revised.

14 F 2 B S 010K4.01, Pressurizer Pressure Control / 3, Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for the following, Spray valve warm-up.

K/A is met.

011EA2.10, Large Break LOCA / 3, Ability to determine or interpret 15 H 2 X N E the following as they apply to a Large Break LOCA: Verification of adequate core cooling.

K/A is met.

Change the cue to read and cannot be manually started.

Delete the initial conditions. They are redundant..

6/4/14 Sat as revised.

16 H 3 X N U 012K6.11, Reactor Protection / 7, Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Trip setpoint calculators.

K/A is NOT met.

This is close, but the K/A requires a loss or malfunction of the trip setpoint calculator. Change this to cause a failure in the pressure instrument input and it will meet the K/A.

Can the fourth bullet read failed high?

6/4/14 Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 17 H 3 X X B E 013K2.01, Engineered Safety Features Actuation / 2, Knowledge of bus power supplies to the following: ESFAS/safeguards equipment control.

K/A is met.

Change question to read WOOTF states a reason that a specific sequence is recommended by 1-AP-10.06, Loss of DC Power, when restoring power following a loss of a DC Bus?

Change answer C to To allow early restoration of letdown.

6/4/14 Sat as revised.

18 H 4 X N E 013K6.01, Engineered Safety Features Actuation / 2, Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors.

K/A is met.

Add if any to the stem of the question.

Correct answer D Si to SI (typo).

6/4/14 Sat as revised.

19 F 3 M S 015A4.02, Nuclear Instrumentation / 7, Ability to manually operate and/or monitor in the control room: NIS indicators.

K/A is met.

20 H 3 M E 015AK3.01, RCP Malfunctions /I 4, Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) : Potential damage from high winding and/or bearing temperatures.

K/A is met.

Clean up the answers by breaking the answers in two. For example:

RCP Motor Upper Thrust bearing temperature is 195 oF and Rising; Annunciator RCP Frame Danger is lit.

6/4/14 Sat as revised.

21 H 3 B S 016K1.08, Non nuclear Instrumentation / 7, Knowledge of the ph.ysical connections and/or cause effect relationships between the NNIS and the following systems: PZR PCS.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 22 F 2 X N E 022A3.01, Containment Cooling / 5, Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation.

K/A is mostly met.

Question needs reworded. It is too complex as written.

Which ONE of the following describes:

1) The status of Containment Air Recirculation Fans. AND
2) Which Recirculation Spray Pumps are operated to maintain containment pressure less than 13 psia after containment pressure has been returned to less than atmospheric pressure.

6/4/14 SAT as revised.

23 H 3 X M E 022AK1.03, Loss of Rx Coolant Makeup / 2, Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: Relationship between charging flow and PZR level.

K/A is met.

Change the stem to say The following is observed:

Then put the alarms at the top of the bulleted list.

6/4/14 Sat as revised.

24 H 3 X N E 025AA1.11, Loss of RHR System / 4, Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: Reactor building sump level indicators.

K/A is met.

An initial RCS pressure needs to be listed.

6/4/14 Initial pressure should be 300 psig. No trend required.

6/18/14 SAT as revised..

25 H 3 N S 026A4.05, Containment Spray / 5, Ability to manually operate and/or monitor in the control room: Containment spray reset switches.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 26 H 3 B U 026AA2.01, Loss of Component Cooling Water / 8, Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS.

K/A is met.

Too similar to RO question 12.

Are there any CC auto isolations at Surry? If so, use that tack.

Otherwise look for potential sump indications.

If you use this question instead of 12, give an RCS pressure and temperature in the initial conditions, but dont tell them that they are not on RHR yet.

6/4/14. Sat as revised.

27 F 2 B S 026K4.09, Containment Spray / 5, Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:

Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover).

K/A is met.

28 H 3 X B E 007K5.02, Pressurizer Relief/Quench Tank / 5, Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR.

K/A is met.

Do you normally use pressurizer heaters to support RCS heatup below 195 °F? If so, please specify which heaters are energized in the IC. Otherwise have the IC state that the heaters are off.

6/4/14. Sat as revised.

29 F 2 X M E 028K5.03, Hydrogen Recombiner and Purge Control / 5, Knowledge of the operational implications of the following concepts as they apply to the HRPS: Sources of hydrogen within containment.

K/A is met.

Remove Answer the following questions from the stem.

Is the term Zircaloy Hydriding use at Surry?

6/4/14 Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 30 F 2 X B E 029EK2.06, ATWS / 1, Knowledge of the interrelations between the breakers, relays, and disconnects following an ATWS.

K/A is met.

Change B to Open Closed Open If you wnted to then you could eliminate RTB A from the answers.

Could the question be rewritten as An inadvertent actuation of RPS A occurred?

6/4/14. Sat as revised.

31 H 2 X X X N E/U 033K3.02, Spent Fuel Pool Cooling /, Knowledge of the effect that a loss or malfunction of the Spent Fuel Pool Cooling System will have on the following: Area and ventilation radiation monitoring systems.

K/A is met.

How far below the low level alarm will the pool drain? Typically Ive seen syphon holes in the drain lines of SFPs. Once there, no further drainage will occur and rad levels at the crane will stanilize.

Also, how high would you expect rad level to get?

Im OK with this questioon if the conditions really could exist. Just make the last bullet become a standalone statement.

Also is it relevent that both ubits are at 100%. If so correct the grammar in the first line to state Units 1 and 2 are. Otherwise Unit 1 is 6/4/14 Sat as revised.

034K6.02, Fuel Handling Equipment / 8, Knowledge of the effect of a 32 F 2 N S loss or malfunction on the following will have on the Fuel Handling System : Radiation monitoring systems.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 33 H 3 X N E 004A2.26, Chemical and Volume Control / 1 & 2, Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low VCT pressure.

K/A is met.

Is it relevant that both units are at 100%? I think that stating Unit 1 is at 100% would be adequate.

Make the pressure in the stem at 16 psig and slowly lowering. This way the second part is testing that the applicant knows that there is a rupture in the VCT that requires isolating.

6/4/14. Sat as revised.

037AK3.06, Steam Generator Tube Leak./3, Knowledge of the 34 H 3 X N S reasons for the following responses as they apply to the Steam Generator Tube Leak: Normal operating precautions to preclude or minimize SGTR.

K/A is NOT met.

The question should deal with normal operating precautions to preclude or minimize SGTR. Possibly chemistry or differential pressure or temperatures.

Also remove the statement Based on the indications answer the following questions: That is self-evident.

6/4/14. After further review question was SAT as written.

35 H 3 B S 039A3.02, Main and Reheat Steam / 4S, Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS.

K/A is met.

36 F 2 X N S 040AG2.2.3, Steam Line Rupture - Excessive Heat Transfer / 4, (multi-unit license) Knowledge of the design, procedural, and operational differences between units.

K/A appears to be met.

Are these valves unique to Unit 2? For example, if I wanted to crosstie Unit 1 to Unit 2, would these same valves be accessed? If so this meets the K/A.

If the above is true, could we put a fire in the U2 turbine buiding, keep the evacuation, then have U2 loose its charging pumps?

6/4/14. After further review question was SAT as written.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 37 H 3 X M E 051AA2.02, Loss of Condenser Vacuum/4, Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.

K/A is met.

Change question to read WOOOTF shall be done first IAW 1-AP-14.00? This wil make the hoggers more plausible.

6/4/14. Sat as revised.

38 H 3 X B E 054AK3.01, Loss of Main Feedwater /4, Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Reactor and/or turbine trip manual and automatic.

K/A is met.

Make the first two bullets Initial Conditions.

The next section should be The following occurs:

Bulletize the rest, state that the alarms lock in or words to that effect.

Remove the first question and reword the second to ask What is the reason for the action(s) required by 1-AP-21.00? If you ask the first question, the answers make some of the distractors less plausible.

6/5/14 Going back to 2X2. Which describes actions IAW AP-21.

Second part A and B. by maintaining SG water levels.

6/18/14 SAT as revised.

056AA2.54, Loss of Off-site Power / 6, Ability to determine and 39 X E interpret the following as they apply to the Loss of Offsite Power:

Breaker position (remote and local).

K/A is met.

Make the D answer all running. This is plausible because it matches the breaker indications.

6/5/14. Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 059AK1.01, Acciental Liquid Rad Waste Rel, / 9, Knowledge of the 40 F 2 X X N U operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: Types & radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant.

K/A is NOT met.

This K/A isnt looking to determine if a source is contaminated or not, but rather what type of radiation (alpha, beta, gamma) and their units of intensity.

6/5/14 neutron and alpha can/cannot be detected in this room.

Correct answer.

6/18/14 SAT as revised.

41 F 2 X M U 059K3.03, Main Feedwater / 4S, Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/Gs.

K/A is NOT met.

This case is looking for some failure in the main feed system, not S/G level control. Look at something like a heater tube failures affect.

6/5/14 load is reduced to 85% IAW procedure. Is further load reduction required? Following the load reduction, SG press be ___

than the was at 100%.

6/19/14 Correct typo in Initial Conditions. Either capitalize feedwater or dont. Cant have it both wways. Otherwise SAT.

6/25/14 SAT as revised.

42 H 3 M S 061K6.02, Auxiliary/Emergency Feedwater / 4S, Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps.

K/A is met.

43 F 3 B S 062A1.01, AC Electrical Distribution / 6, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Significance of D/G load limits.

K/A is met.

This is fine if these values are expected to be memorized by the applicants.

6/5/14. SAT. Required knowledge.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 44 H 3 N E 062AA1.01, Loss of Nuclear Svc Water / 4, Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): Nuclear service water temperature indications.

K/A is met.

Make first bullet current tense.

Make the third bullet the second bullet.

6/5/14 Remove DRP info. Is Cont Pressure vs Water Temp .. met?

6/19/14. SAT as revised.

45 H 3 N S 063G2.1.31, DC Electrical Distribution / 6, Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

K/A is mostly met.

46 H 3 X N E 063K1.03, DC Electrical Distribution / 6, Knowledge of the physical connections and/or cause effect relationships between the DC electrical system and the following systems: Battery charger and battery.

K/A is met.

Change distractors to as follows A. Unit 1 A and Unit 2 B.

B. Unit 1 B and Unit 2 B.

C. Unit 2 A and Unit 2 B D. Unit 2 B only.

With the 2J bus de-energized, the 2B battery discharge is just about given.

6/4/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 47 F 2 X N E 064K1.03, Emergency Diesel Generator / 6, Knowledge of the physical connections and/or cause effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system.

K/A is met.

D is not plausible. If the fuel racks close off all fuel, how can the EDG idle?

6/4/14. Put automatic between specific and actions in first question.

6/19/14. SAT as revised.

48 H 2 X M E 065AG2.1.32, Loss of Instrument Air / 8, Ability to explain and apply all system limits and precautions.

K/A is met.

B is a subset of A, therefore this would cause applicants to stay away from both answers.

6/5/14. Make two by two. Is immediate entry required? Is reactor trip required 6/19/14. SAT as revised.

071A3.02, Waste Gas Disposal / 9, Ability to monitor automatic 49 H 3 N S operation of the Waste Gas Disposal System including: Pressure-regulating system for waste gas vent header.

K.A is met.

50 F 2 N S 072G2.1.28, Area Radiation Monitoring / 6, Knowledge of the purpose and function of major system components and controls.

K/A is met.

51 H 3 N S 073A2.02, Process Radiation Monitoring / 7, Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 52 F 3 M S 074EG2.4.21, Inad Core Cooling /4, Knowledge of the parameters and logic used to assess the status of safety functions.

K/A is met.

If you have feedback that the 2 column format is better, continue to use it. Otherwise just have bulleted sentences.

53 H 3 N S 076K2.08, Service Water / 4S, Knowledge of bus power supplies to the ESF-actuated MOVs.

K/A is met.

54 H 3 X N S 077AK2.01, Generator Voltage and Electric Grid Disturbances / 6, Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and motors.

K/A is met.

If system voltage is at its max and you are maximizing VARs in, arent you lowering a higher than normal voltage? If so, is the answer still correct?

6/5/14. This is how the system will respond. SAT.

55 H 3 N S 078A4.01, Instrument Air / 8, Ability to manually operate and/or monitor in the control room:Pressure gauges.

K/A is met.

56 H 3 X N E 079K4.01, Station Air / 8, Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with lAS.

K/A is met.

Make Bullet 5 as a stand alone (non-bulleted) sentence.

Label the last 3 bullets as current condition.

6/5/14. Two by two. Location of leak. Is U2 IAC running?. Put leak on SAC discharge.

6/19/14. SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 57 F 2 X B S 086A1.01, Fire Protection / 8, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: Fire header pressure.

K/A is met.

Do you expect your operators to know that FP-37 is on the diesel fire pump and FP-36 is on the motor driven? If this is answered yes by the Facility Rep, then this question is SAT.

6/5/14 SAT. This is requijred knowledge.

58 F 3 M S 103A2.04, Containment / 5, Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Containment evacuation (including recognition of the alarm).

K/A is met.

59 H 3 M S 103A3.01, Containment / 5, Ability to monitor automatic operation of the containment system, including: Containment isolation.

K/A is met.

60 F 2 . N S G2.1.29, Conduct of operations, Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

K/A is met.

61 F 3 N S G2.1.40, Conduct of operations, Knowledge of refueling administrative requirements.

K/A is met.

62 F 3 M S G2.1.5, Conduct of operations, Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

K/A is met.

63 F 2 M S G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 64 F 2 N S G2.2.2, Equipment Control, Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

K/A is met.

65 F 1 X B U G2.3.5, Radiation Control, Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

K/A is met.

A is not plausible and D is barely plausible. This is a general rad worker question. LOD =1.

6/5/14 Use N-16 monitor.

6/19/14 As written, 10% is never wrong for the first part of the question. Need to rephrase to something like the minimum power level at whichthey can be relied upon.

6/25/14 SAT as revised.

66 F 1 N U G2.3.7, Radiation Control, Ability to comply with radiation work permit requirements during normal or abnormal conditions.

K/A is met.

Why would any person who has worked in nuclear power pick B

anything but D. Perhaps use a survey map with an RWP and see if they can figure out if they can do a task. LOD=1.

6/5/14. Bank question used.. SAT as revised.

67 F 3 N E G2.4.1, Emergency Procedures/Plans, Knowledge of EOP entry conditions and immediate action steps.

K/A is met.

Modify second question to read All of the methods provided in this procedure to secure steam flow to the Main Turbine from the Control Room?

6/5/14. Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 68 F 3 N E G2.4.32, Emergency Procedures/Plans, Knowledge of operator response to loss of all annunciators.

K/A is met.

1) Change second question to read Upon power restoration what is the minimum acceptable method to perform a functional check in order to confirm that alarming conditions in the field will actuate the appropriate alarm?

6/5/14. SAT as revised.

69 H 3 N S G2.4.4, Emergency Procedures/Plans, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

K/A is met.

70 H 2 N S WE03EK2.1, LOCA Cooldown Depress /4, Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

K/A is met.

71 H 3 N E WE04EG2.4.3, LOCA Outside Containment / 3, Ability to identify post-accident instrumentation.

K/A is met.

In the question, replace the comma with an and and the and would with a to.

6/4/14. SAT as reivsed.

72 H 3 M S WE05EK2.2, Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4, Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facilitys heat removal 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.

K/A is met.

Make all of the bullets except the last one part of the initial conditions.

Make the last bullet a stand alone statement.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 73 H 3 N S WE11EK1.3, Loss of Emergency Coolant Recirc./ 4, Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Annunciators and conditions indicating signals and remedial actions associated with the (Loss of Emergency Coolant Recirc).

K/A is met.

WE14EK2.1, Knowledge of the interrelations between the (High 74 H 3 N S Containment Pressure) and the following: / 5 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

K/A is met.

75 F 2 N E WE15EK1.2, Containment Flooding / 5, Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

K/A is met.

Following a Design Basis LOCA, the MINIMUM containment sump level to enter FR-Z.2, Response to Containment Flooding is

_____1)_____ feet, and entry is a(n) _____2) _____ Path.

Change a __ to a(n)___.

6/4/14. First part remains the same. Second pressure would be a red path to FR-Z.1.

6/19/14. SAT as revised.

ES-401 Written Examination Review Worksheet Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 76 H 2 X M S 004G2.2.22, Chemical and Volume Control / 1 & 2, Knowledge of limiting conditions for operations and safety limits.

K/A is met.

Why do you feel it is necessary to provide a drawing? This should be part of system knowledge.

6/4/14. SAT as is.

77 H 3 X M S 009EA2.39, Small Break LOCA / 3, Ability to determine or interpret adequate core cooling as it applies to a small break LOCA.

K/A is met.

Is A credible? If you dont meet RCP trip criteria, it is almost always due to subcooling. If you dont have subcooling, why would you stop SI?

78 H 3 M S 013A2.03, Engineered Safety Features Actuation / 2, Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Rapid depressurization K/A is mostly met.

79 H 3 N S 017G2.4.47, in-core Temperature Monitor / 7, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

K/A is met.

022AA2. 01, Loss of Rx Coolant Makeup I 2, Ability to determine 80 H 3 M S and interpret the following as they apply to the Loss of Reactor Coolant Makeup: (CFR 43.5/ 45.13) Whether charging line leak exists.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 81 H 3 X N E 024AG2.1.23, Emergency Boration/I 1, Ability to perform specific system and integrated plant procedures during all modes of plant operation.

K/A is met.

You have four different second part answers. If this answer is known, it makes the first part irrelevent and therefore would not meet the K/A. Why not choose the Delta flux answer associated with transients and the rod insertion associated with reactor trip and have a true 2 by 2 answer?

6/4/2014 Sat as revised.

82 H 2 X M E 027AA2.10, Pressurizer Pressure Control System Malfunction / 3, Ability to determine and Interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR heater energized/de-energized condition.

K/A is met.

Is it necessary to tell them that the Master Controller output goes to 0%? This should be testable knowledge.

Change the second part answer to read will not be solid when critical.

6/4/14 Added comma after operation in question.

6/17/14 SAT as revised.

83 H 2 X N U 033AG2.2.44, Loss of Intermediate Range NI / 7, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

K/A is met.

Question is NOT at SRO level. The removal of fuses is RO knowledge. Knowing that you must verify permissive light within one hour is RO knowledge.

6/4/14 Control Power fuses would/ would not be removed and make the second part ask what AP-4.0 requires.

6/17/14 SAT as revised.

Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 84 H 2 N S 014A2.05, Rod Position Indication / 1, Ability to (a) predict the impacts of a reactor trip on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

K/A is met.

85 H 3 N S 057AG2.1.28, Loss of Vital AC Inst. Bus/ 6, Knowledge of the purpose and function of major system components and controls.

K/A is met.

059A2.01, Main Feedwater / 4S, Ability to (a) predict the impacts of 86 H 3 X N E feedwater actuation of AFW system on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

K/A is met.

Change 2nd distractor to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This is more plausible as action 22 of the AFW TS.

Is this how you want to ask the question? An alternative could be What LCO is entered? With the answers as Table 3.7-2, Action 24.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to restore. And Table 3.7-2, Action 22. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore.

6/4/14 Change first part to ask if TS entry is required. Provide TS 3.e and Action 24.

6/17/14 SAT as revised.

87 H 3 N S 061G2.4.47, Auxiliary/Emergency Feedwater, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 88 H 2 X N E 075G2.2.44, Circulating Water / 8, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

K/A is met.

You need a value and trend for intake canal leve to ensure single answer.

6/4/14 Change 25 ft and lowering.

6/17/14 SAT as revised.

078A2.01, Instrument Air /, Ability to (a) predict the impacts of the 89 H 3 X N U following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions.

K/A is NOT met.

Need to use procedures to control or mitigate. In this case I would suggest using 1-AOP-27.00. You can ask about the need to secure RHR pumps, or about alternate cooling methods , or isolating containment.

6/4/14. SAT as rewritten.

90 H 3 M S G2.1.25, Conduct of operations, Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

K/A is met.

91 H 3 X N E G2.1.32, Conduct of operations, Ability to explain and apply all system limits and precautions.

K/A is met.

There is a subset issue here. An applicant can claim that since 68%

is less than 75%, it is always correct. So he may answer correctly without knowing the information. More clearly phrase the question to ask what the TS states.

6/4/14. What is the max time to be less than 68%. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 30 min.

6/17/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 92 F 2 X M E G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.

K/A is met.

Remove because of a shortage of personnel from answer D.

6/14/04. Sat as rewritten.

93 H 3 N S G2.2.18, Equipment Control, Knowledge of the process for managing maintenance activities during shutdown operations.

K/A is met.

94 F 2 X N E G2.3.11, Radiation Control, Ability to control radiation releases.

K/A is met.

Change the second part to the following:

the dose to an individual standing _________________.

1) at the exclusion area boundary will not exceed 0.5 rem TEDE over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period.
2) in an unrestricted area will not exceed 0.002 rem in any one hour.

This second part is a Part 20 requirement that does not apply in this case.

6/4/14 Sat as rewritten.

G2.3.12, Radiation Control, Knowledge of radiological safety 95 F 2 X N E principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

K/A is not reall met.

Since there are four different answers fo the second part of the question, the first part is not relevent. Suggest that you delete the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> answers from the second part. This would be an adequate question then.

6/4/14 Added maximum prior to the word time in question 2. No press release is planned to be issued.

6/17/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 96 H 2 X N E G2.4.28, Emergency Procedures/Plans, Knowledge of procedures relating to emergency response to sabotage.

K/A is met.

I believe that 0-AOP-36.00 requires both units be tripped upon breaching the fences. If so, let the applicants know that the applicable portions of the AOP are in progess with no issues.

6/4/14 Sat as rewritten.

97 F 3 S WE11EG2.1.32, Loss of Emergency Coolant Recirc. /4, Ability to explain and apply all system limits and precautions.

K/A is met.

98 H 3 S WE12EG2.4.4, Steam Line Rupture - Excessive Heat Transfer /4, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

K/A is met.

99 H 2 B S WE16EA2.2, High Containment Radiation / 9, Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

K/A is met.

100 H 3 N S WE01EA2.1, Rediagnosis / 3, Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

K/A is met.

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Surry Date of Exam: 08/05/14 Exam Level: ROj SROE Initials Item Description a b c

1. Clean answer sheets copied before grading -2 ,ii4
2. Answer key changes and question deletions justified and documented AX
3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail
5. All other failing examinations checked to ensure that grades are justified
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature Date
a. Grader Newton Lacy
b. Facility Reviewer(*) N/A
c. NRC Chief Examiner (*) David Lanyi /

/ /7/fy

d. NRC Supervisor (*)

(*) The facility reviewers signature is not applicable for e nations graded by the NRC; two independent NRC reviews are required.

ES-403, Page 6 of 6

£x4M fA/v ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

5_jR Date of Examination:

TuL1 c.//

Initials Item Task Description

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

R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. (17 T

T E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. (/9
d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. M i4 N
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, S and major transients.

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 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 from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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 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 T (3) no tasks are duplicated from the applicants audit test(s)

(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 (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. 2)7 it E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 7
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 7 R Check for duplication and overlap among exam sections. 41:4
d. 1 L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)

If

c. NRC Chief Examiner (#) 1I4 - .4ArRt
d. NRC Supervisor ,tAL4Ot4 i WlPLLMJ1/

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

Not applicable for NRC-prepared examination outlines

- WR/77EA) &4m

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Surry Date of Examination: 7/2114 8/5/14 Examinations Developed by: cit / NRC (circle one)

Chief Target Task Description (Reference) Examiners Date*

Initials

-180 1. Examination administration date confirmed (C.1.a; C.2.a and b)

-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

-120 3. Facility contact briefed on security and other requirements (C.2.c)

-120 4. Corporate notification letter sent (C.2.d)

[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] (

-75 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-3d-S. ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)

-70 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)

-45 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)

-14 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)

-14 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g)

-7 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 14. Final applications reviewed; examination approval and waiver letters sent (C.2.i; Attachment 4; ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

  • Target dates are keyed to the examination date identified in the corporate 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 to examinations prepared by the NRC.

£x4M fA/v ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

5_jR Date of Examination:

TuL1 c.//

Initials Item Task Description

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

R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. (17 T

T E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. (/9
d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. M i4 N
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, S and major transients.

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 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 from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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 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 T (3) no tasks are duplicated from the applicants audit test(s)

(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 (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. 2)7 it E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 7
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 7 R Check for duplication and overlap among exam sections. 41:4
d. 1 L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)

If

c. NRC Chief Examiner (#) 1I4 - .4ArRt
d. NRC Supervisor ,tAL4Ot4 i WlPLLMJ1/

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

Not applicable for NRC-prepared examination outlines

- WR/77EA) &4m

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

Tier Group JI RO K/A Category Points SRO-Only Points FKKKKKAAAAG[ A2 G* JTotal

  • jTotal 11234561234 L___
1. J i 3 3f3 33 3 18 3 3 6 Emergency &

Abnormal Plant

[

[

2 II N/A 1

N/A 9 2 2 4 Evolutions LTie1Tota1s 5 1 4 4 5 27 5 5 10 1 32 2 3332 3322 28 3 2 5

  • 2 11111110111 10 2 3 piant Systems Tier Totals 4 3 3 4 4 4 3 3 4 3 3 38 if 4 8
3. GenericKnowledgeandAbilities Categories

] 1 2 3 4 10 1 2 3 4 7 3 2 2 3 2 2 2 1

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the PTier Totals@

in each K/A 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 4 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

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

6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.
7. *The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section 0.1 .b of ES-401 for the applicable KAs.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics=importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43..

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR 1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 007EK1 .02 Reactor Trip Stabilization Recovery 3.4 3.8 H H H H H H H H H H Shutdown margin

/1 008AA1 .06 Pressurizer Vapor Space Accident / 3 3.6 3.6 Control of PZR level 009EK3.05 Small Break LOCA / 3 3.4 3.8 CCWS radiation alarm 011 EA2.l 0 Large Break LOCA /3 4.5 4.7 Verification of adequate core cooling 015AK3.0l RCP Malfunctions /4 2.5 3.1 LI Potential damage from high winding and/or bearing temperatures 022AK1 03 Loss of Rx Coolant Makeup / 2 3 3.4 H H Relationship between charging flow and PZR level 025AA1 .11 Loss of RHR System / 4 2.9 3 H H H H H H H H H H Reactor building sump level indicators 026AA2.01 Loss of Component Cooling Water / 8 2.9 3.5 H H H H H H H H H H Location of a leak in the CCWS 029EK2.06 ATWS / 1 2.9 3.1 H H H H H H H H H H Breakers, relays, and disconnects.

040AG2.2.3 Steam Line Rupture - Excessive Heat 3.8 3.9 LI H H H H H H H H H (multi-unit license) Knowledge of the design, procedural Transfer / 4 and operational differences between units.

054AK3.01 Loss of Main Feedwater / 4 4.1 4.4 H H H H H H H H H H Reactor and/or turbine trip, manua( and automatic Page 1 of 2 10/04/2013 9:30AM

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 056AA2.54 Loss of Off-site Power/6 2.9 3 Breaker position (remote and local)

ElElEl 062AA1.01 Loss ofNuclearSvcWater/4 3.1 3.1 Nuclear service water temperature indications ElElElEl 065AG2.l.32 LossoflnstrumentAir/8 3.8 4.0 Ability to explain and apply all system limits and El El El El El El ElElEI precautions.

077AK2.01 Generator Voltage and Electric Grid 3.1 3.2 Motors Disturbances I 6

[] El El El El El ElElElEl weO4EG2.4.3 LOCA Outside Containment / Ability to identify post-accident instrumentation.

El El El El El El El EJElE WE05EK2.2 Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary Secondary Heat Sink / 4 El El El El El El ElElElEl coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 1 EK1 .3 Loss of Emergency Coolant Recirc. / 4 3.6 4.0 Annunciators and conditions indicating signals, and El remedial actions associated with the (Loss of Emergency Coolant Recir).

Page 2 of 2 10/04/2013 9:30AM

ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO1AG2.1 .20 Continuous Rod Withdrawal I 1 4.6 4.6 H H H H H H H H H Ability to execute procedure steps.

036AA1.04 Fuel Handling Accident/8 3.1 3.7 Fuel handling equipment during an incident 037AK3.06 Steam Generator Tube Leak) 3 3.6 4.1 H H H H H H H H H H Normal operating precautions to preclude or minimize SGTR 051AA2.02 Loss of Condenser Vacuuml4 3.9 4.1 Conditions requiring reactorand/orturbine trip 059AK1.0l Accidental Liquid RadWaste Rel. / 9 2.7 3.1 Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 074EG2.4.21 mad. Core Cooling /4 4.0 4.6 H H H H H H H H H H Knowledge of the parameters and logic used to assess the status of safety functions WEO3EK2.1 LOCA Cooldown Depress. /4 3.6 4.0 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE14EK2.l Loss of CTMT Integrity / 5 3.4 3.7 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEI 5EK1 .2 Containment Flooding /5 2.7 2.9 H H H H H H H H H H Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003G2.4.50 Reactor Coolant Pump 4.2 4.0 Ability to verify system alarm setpoints and operate controls Li J identified in the alarm response manual.

004A2.26 Chemical and Volume Control 2.8 3.0 Low VCT pressure LI 0041(5.06 Chemical and Volume Control 3.0 3.3 Concept of boron worth or inverse boron worth Li [] Li fl (reactivity, pcmlppm) 005K5.09 Residual Heat Removal 3.2 3.4 Dilution and boration considerations 006K4.ll EmergencyCoreCooling 3.9 4.2 ResetofSlS Li LI 007A1 .02 Pressurizer Relief/Quench Tank 2.7 2.9 j Maintaining quench tank pressure J

007K5.02 Pressurizer Relief/Quench Tank 3.1 34 Method of forming a steam bubble in the PZR Li Li Li Li IJ Li Li Li Li Li Li 008K3.03 Component Cooling Water 4.1 4.2 RCP Li Li Li Li Li Li Li Li Li [1 O1OK1.06 PressurizerPressureControl 2.9 3.1 CVCS Li Li Li Li Li Li Li Li Li 0101(4.01 PressurizerPressureControl 2.7 2.9 Sprayvalvewarm-up Li Li Li Li Li Li Li Li Li Li 012K6.ll Reactor Protection 2.9 2.9 Trip setpoint calculators Li Li Li LI Li []

Page 1 of 3 10/04/2013 9:30AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KP NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 01 3K2.0l Engineered Safety Features Actuation 3.6 3.8 LI ESFAS/safeguards equipment control LI LI LI LI LI LI C] C] LI 013K6.0l Engineered Safety Features Actuation 2.7 3.1 C] C] C] Sensors and detectors C] C] C]

022A3.01 Containment Cooling 4.1 4.3 Initiation of safeguards mode of operation C] LI LI LI LI LI LI LI LI LI 026A4.05 Containment Spray 3.5 3.5 Containment spray reset switches LI LI LI LI LI LI LI LI LI LI 026K4.09 Containment Spray 3.7 4.1 Prevention of path for escape of radioactivity from LI LI LI LI LI LI LI LI LI LI containment to the outside (interlock on RWST isolation after swapover) 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS LI LI LI C] LI LI LI LI LI LI 059K3.03 Main Feedwater 3.5 3.7. S/GS LI LI ] LI LI LI LI LI LI LI LI 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps LI C] LI LI LI LI LI LI LI LI 062A1 .01 AC Electrical Distribution 3.4 3.8 Significance of DIG load limits LI LI LI LI LI LI ] LI LI LI LI 063G2.1 .31 DC Electrical Distribution 4.6 4.3 Ability to locate control room switches, controls and LI C] LI LI LI LI LI LI LI LI indications and to determine that they are correctly reflecting the desired plant lineup.

063K1.03 DC Electrical Distribution 2.9 3.5 Battery charger and battery LI LI LI LI LI LI LI LI LI C]

Page 2 of 3 10/04/2013 9:30 AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064K1 .03 Emergency Diesel Generator 3.6 4.0 Diesel fuel oil supply system LI 073A2.02 Process Radiation Monitoring 2.7 3.2 Detector failure LI LI LI LI LI LI LI LI LI LI 076K2.08 Service Water 3.1 3.3 ESF-actuated MOVs LI LI LI LI LI LI LI LI LI LI 078A4.01 InstrumentAir 3.1 3.1 Pressure gauges LI LI LI LI LI LI LI LI LI ] LI 103A2.04 Containment 3.5 3.6 Containment evacuation (including recognition of the alarm)

LI LI LI LI LI LI LI LI LI LI 103A3.01 Containment 3.9 4.2 Containment isolation LI LI LI LI LI LI LI LI LI LI Page 3 of 3 10/04/2013 9:30 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 015A4.02 Nuclear Instrumentation 3.9 39 NIS indicators El 016K1.08 Non-nuclearlnstrumentation 3 PZRPCS El El El El El El El El El El 027K2.O1 Containment Iodine Removal 3.1 3.4 Fans 028K5.03 Hydrogen Recombiner and Purge 2.9 3.6 Sources of hydrogen within containment Control 033K3.02 Spent Fuel Pool Cooling 2.8 3.2 Area and ventilation radiation monitoring systems El 034K6.02 Fuel Handling Equipment 2.6 3.3 Radiation monitoring systems 071A3.Ol Waste Gas Disposal 2.6 2.7 HRPS El El El El El El El El El El 072G2.l.28 Area Radiation Monitoring 4.1 4.1 Knowledge of the purpose and function of major system El El El El El El El El El El components and controls.

079K4.O1 Station Air 2.9 3.2 Cross-connect with lAS El El El El El El El El El El 086A1 .01 Fire Protection 2.9 3.3 Fire header pressure El El El El El El El El El El Page 1 of 1 10/04/2013 9:30 AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.29 Conduct of operations 4.1 4.0 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.l.40 Conduct of operations 2.8 3.9 Knowledge of refueling administrative requirements G2.1 .5 Conduct of operations 2.9 3.9 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.2.13 Equipment Control 4.1 4.3 Knowledge of tagging and clearance procedures.

G2.2.2 Equipment Control 4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements J

during normal or abnormal conditions G2.4.1 Emergency Procedures/Plans 4.6 4.8 Knowledge of EOP entry conditions and immediate action steps.

G2.4.32 Emergency Procedures/Plans 3.6 4.0 Knowledge of operator response to loss of all annunciators.

G2.4.4 Emergency Procedures/Plans 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30 AM

ES-401, REV 9 SRO TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 009EA2.39 Small Break LOCA I 3 Adequate core cooling 022AA2.0l Loss of Rx Coolant Makeup /2 3.2 3.8 Whether charging line leak exists 027AA2.lO Pressurizer Pressure Control System 3.3 3.6 jrj PZR heater energized/de-energized condition Malfunction / 3 057AG2.1 .28 Loss of Vital AC Inst. Bus 16 4.1 4.1 Knowledge of the purpose and function of major system components and controls.

well EG2.l .32 Loss of Emergency Coolant Recirc. / 4 3.8 4.0 Ability to explain and apply all system limits and precautions.

wel2EG2.4.4 Steam Line Rupture Excessive Heat 4.5 4.7 Ability to recognize abnormal indications for system Transfer I 4 operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 1(3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 024AG2.l.23 Emergency Boration / 1 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

033AG2.2.44 Loss of Intermediate Range NI / 7 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions WEO1 EA2.l Rediagnosis / 3 3.2 4 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE16EA2.2 High Containment Radiation / 9 3.0 3.3 Adherence to appropriate procedures and operation LI LI LI LI LI LI LI LI LI LI within the limitations in the facilitys license and amendments.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 004G2.2.22 Chemical and Volume Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

013A2.03 Engineered Safety Features Actuation 4.4 4.7 Rapid depressurization 059A2.0l Main Feedwater 3.4 3.6 Feedwater actuation of AFW system 061G2.4.49 Auxiliary/Emergency Feedwater 4.6 4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

078A2.01 Instrument Air 2.4 2.9 Air dryer and filter malfunctions Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 017G2.4.47 In-core Temperature Monitor 4.2 4.2 Ability to diagnose and recognize trends in an accurate J

and timely manner utilizing the appropriate control room reference material.

056A2.04 Condensate 2.6 2.8 Loss of condensate pumps 075G2.2.44 Circulating Water 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.25 Conduct of operations 3.9 4.2 Ability to interpret reference materials such as graphs,

[

monographs and tables which contain performance data.

G2.l .32 Conduct of operations 3.8 4.0 Ability to explain and apply all system limits and precautions.

G2.2.13 Equipment Control 4.1 4.3 Knowledge of tagging and clearance procedures.

D L D L fl G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance D LI LI LI LI LI LI activities during shutdown operations.

G2.3.ll Radiation Control 3.8 4.3 Ability to control radiation releases G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.

Page 1 of 1 10/04/2013 9:30AM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Surry_________________________ Date of Examination: __7/21/14_____

Examination Level: RO Operating Test Number: _SR14-301_

Administrative Topic Type Describe activity to be performed (see Note) Code*

Quadrant Power Tilt Ratio Conduct of Operations R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Conduct of Operations Perform a review of OPT-FW-006 Equipment Control R/M K/A:G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Obtain Required Information IAW EPIP-2.01 Emergency Procedures/Plan R/N K/A: G2.4.39 Knowledge of RO responsibilities in emergency plan implementation. RO: 3.9 / SRO: 3.8.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry_______________________ Date of Examination: _7/21/14_____

Examination Level: SRO Operating Test Number: _SR14301__

Administrative Topic Type Describe activity to be performed (see Note) Code*

Quadrant Power Tilt Ratio Conduct of Operations R/M K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations S/M K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8

/ SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control R/M K/A: G2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO:

4.1 Calculate Radiation Exposure when Placing Unit 1 Residual Heat Removal System in Service Radiation Control R/M K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Classify and Determine PAR for General Emergency Emergency Procedures/Plan R/N K/A: G2.4.41 Knowledge of the emergency action level thresholds and classifications. RO: 2.9 / SRO: 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Surry _____________________ Date of Examination: _7/21/14______

Exam Level: RO Operating Test No.: _SR14301______

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Perform an Alternate Dilute N/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove SR NIs From Service During a Reactor Startup M/S/L 7
g. Respond to a Low Level Transient D/S 8
h. Respond to a #3 EDG Start Failure N/A/S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/L/E 3
k. Locally Swap U-2 AFW to Fire Water M/A/L/E/R 4S

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U RO Actual Criteria Met (A)lternate path 4-6 5 YES (D)irect from bank 9 6 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow-Power / Shutdown 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 5 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Surry ______________________ Date of Examination: _7/21/14______

Exam Level: SRO-I Operating Test No.: _SR14301______

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Perform an Alternate Dilute N/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove SR NIs From Service During a Reactor Startup M/S/L 7
g. Respond to a Low Level Transient D/S 8 h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/L/E 3
k. Locally Swap U-2 AFW to Fire Water M/A/L/E/R 4S

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U SROI Actual Criteria Met (A)lternate path 4-6 4 YES (D)irect from bank 8 6 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow-Power / Shutdown 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 4 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Surry________________________ Date of Examination: _7/21/14______

Exam Level: SRO-U Operating Test No.: _SR14301______

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Perform an Alternate Dilute N/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/EN/L 5 d.

e.

f.

g.

h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel j.
k. Locally Swap U-2 AFW to Fire Water M/A/L/E/R 4S

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U SROUI Actual Criteria Met (A)lternate path 2-3 2 YES (D)irect from bank 4 2 YES (E)mergency or abnormal in-plant 1 2 YES (EN)gineered safety feature 1 1 YES (L)ow-Power / Shutdown 1 2 YES (N)ew or (M)odified from bank including 1(A) 1 3 YES (P)revious 2 exams (randomly selected) 2 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Operating Test QuaUty Checklist Form ES-301-3 Facility: Surry Date of Examination: Week of 7/21 & 7/28/14 Operating Test Number: SR3Ot-2014 Initials

1. General Criteria a b* c#
a. The operating test conforms with the previously approved outline: changes are consistent with .

sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution),

b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
c. The operating test shall not duplicate items from the applicants audit test(s). (see Section 0. 1.

a.) PC A.

d. Overlap with the written examination and between different parts of the operating test is within -p.,

acceptable limits.

e. It appears that the operating test will differentiate between competent and less-than-com petent applicants at the designated license level.
2. Walk-Through Criteria -- --
a. Each JPM includes the following, as applicable:
  • 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
  • operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important obseivations 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 sequence of steps, if applicable

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 distribution, bank use, repetition from the last 2 NRC examinations) specified f on those forms and Form ES-201-2.
3. Simulator Criteria -_ --

The associated simulator operating tests (scenario sets) have been reviewed in accordance with j Form ES-301-4 and a copy is attached.

Printed Name I Signature Date

a. Author Michael R. Meyer! 1  ?
b. Facility Reviewer() Rich Philpot! 1,-I.

7/

c. NRC Chief Examiner (#) David Lan V C1i-r
d. NRC Supervisor

/ 7(n (

NOTE: The facility signature is not applicable for NRC-developed tests.

  1. Independent NRC reviewer initial items in Column c: chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES3O1-4 Facility: Surry Date of Exam; Week of 8/21 & 8)28/14 Scenano Numbers: 1/ 2/ 3/4/5 Operating Test No.: SR3OI-2014 QUALITATIVE ATTRIBUTES Inibals a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.
2. The scenarios consist mostly of related events.  ?)
3. Each event description consists of

. the point in the scenario when it is to be initiated a 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) V a 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. 7i- (j, -
8. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
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.

8. The simulator modeling is not altered. 7\ ( .:;z
9. The scenarios have been validated, 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.

L i_.

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 of ES-301, 2i .t(

11, All individual operator competencies can be evaluated, as verified using Form ES-301-6 12.

(submit the form along with the simulator scenarios).

Each applicant will be significantly involved in the minimum number of transients and events 22 L. i specified on Form ES-301-5 (submit the form with the simulator scenarios). rN

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

jj Target Quantitative Attributes (Per Scenario; See Section DSd) Actual Attributes -- --

1. Total malfunctions (58) 6/ 6/ 5/ 5 Q
2. Malfunctions after EOP entry (12) 3/2/3) 2 ic
3. Abnormal events (24) 4/51 5! 5
4. Major transients (12) 1/ 1/ 1/ 1 22.. iL.
5. EOPs entered/requiring substantive actions (12) 2/1! 1/ 2 71, ( 7, 6.

EOP contingenctes requiring substantive actions (02) 1/ 1/ 1/0 7 flt i-

7. Critical tasks (23) 2/2/ 3/ 2 (

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Date of Exam: Operating Test No.:

A E Scenarios P V 1 3 4 5 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

M C S A B S A B S A B S A B L U A T R T O R T O R T O R T O M(*)

N Y O C P O C P O C P O C P R I U T P E

RO RX 5 5 6 1 1,1, 1 1 0 1,1 SRO-I NOR 0 1 1 1 I/C 2,6 2, 2,4, 3,5 2,3, 4 4 2 SRO-U 4, 6 ,6, 3,4 6 8 MAJ 7,8 8, 7,8 7 2,2, 2 2 1 9 2,1 TS 0 0 2 2 RX 0 1 1 0 RO NOR 1,5 5 6 1 2,1, 1 1 1 1,1 SRO-I I/C 3,4, 3,7,9 3,5,9 2,4, 4,3, 4 4 2 6,9 ,8 3,3 SRO-U MAJ 7,8 8,9 7,8 7 2,2, 2 2 1 2,1 TS 0 0 2 2 RO RX 5 5 6 1 1,1, 1 1 0 1,1 SRO-I NOR 1 1,0, 1 1 1 0,0 SRO-U I/C 2,3,4 2,3,4, 2,3,4, 2,3,4, 5,6, 4 4 2

,6,9 6,7,9 5,6,9 5,6,8 6,6, MAJ 7,8 8, 7,8 7 2,2, 2 2 1 9 2,2 TS 1,2,3 3,4,6 2,3,5, 2,5 3,3, 0 2 2 7 6 4,4 RO RX 5 5 6 1 1,1, 1 1 0 1,1 SRO-I NOR 1 1,0, 1 1 1 0,0 SRO-U I/C 2,3,4 2,3,4, 2,3,4, 2,3,4, 5,6, 4 4 2

,6,9 6,7,9 5,6,9 5,6,8 6,6, MAJ 7,8 8, 7,8 7 2,2, 2 2 1 9 2,0 TS 1,2,3 3,4,6, 2,3,5, 2,5 3,4, 0 2 2 7 6 4,2

ES-301 Competencies Checklist Form ES-301-6 Facility: Surry Power Station Date of Examination: 7/21/14 Operating Test No.: SR301-2014 APPLICANTS RO SRO-I SRO-U Competencies SCENARIO SCENARIO SCENARIO 1 3 4 5 1 3 4 5 1 3 4 5 Interpret/Diagnose 2,3,4 2,3,4 2,3,4 2,3,4 2,3,4 2,3,4 2,3,4, 2,3,4, 2,3,4 2,3,4 2,3,4 2,3,4,

,5,6 ,5,6, ,5,6, ,5,6 ,5 ,5,6, 5,6,7, 5,6 ,5 ,5,6, ,5,6, 5,6 Events and Conditions 8,9 7,8 8,9 8 8 7,8 Comply With and All All All All All All All All All All All All Use Procedures (1)

Operate Control ALL ALL 2,3,4 ALL 2,5,6 N/A 2,4,6, 1,3,5, N/A N/A N/A N/A

,5,6, ,7,8 7,8 6,7,8 Boards (2) 7,8,9 Communicate ALL ALL All All All All All All All All All All and Interact Demonstrate N/A N/A N/A N/A All All All All All All All All Supervisory Ability (3)

Comply With and N/A N/A N/A N/A 1,2,3 3,4,6 2,3,5, 2,5 1,2,3 3,4,6 2,3,5 2,5

,7 6 ,4 ,6 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility Surry Power Station Date of Exam: Exam Level: RO X SRO X Initial Item Description a b* c

1. Questions and answers are technically accurate and applicable to the facility.
2. a. NRC K/As are referenced for all questions.
b. Facility learning objectives are referenced as available.
3. SRO questions are appropriate in accordance with Section D.2,d of ES401 (ZP
4. The samphng process was random and systematic (If more than 4 RO or 2 SRO questions Nose 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:

the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started: or X 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 19/0 25/28 56172 question_distribution(s)_at_right.

7. Between 50 and 60 percent of the questions on the RO Memory C/A exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly 45/16 55/84 selected K/As support the higher cognitive levels: enter the actual RO I SRO question distribution(s) at right.
8. References/handouts provided do not give away answers or aid in the elimination of distractors.
9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified. i L
10. Question psychometric quality and format meet the guidelines in ES Appendix B. .-.

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. f Printed Name / Signature Date

a. Author MichaelR Meyer /
b. Facility Reviewer (*) Rich Philpot / . iLj
c. NRC Chief Examiner (#) David Lanyi_/ O
d. NRC Regional Supervisor .I-4 IAAç\jy.

/ .. )

Note: The facility reviewers initialslsignature are not applicable for NRC-developed examinations.

Independent NRC reviewer initial items in Column c; chief examiner concurrence required, Note 1: Sample Plan provided by Chief Examiner Ken Schaaf, and amended by Chief Examiner Amanda Toth.

ES-401 Written Examination Review Worksheet Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 1 H 2 X N E 001AG2.1.20, Continuous Rod With-drawal / 1, Ability to execute procedure steps.

K/A is met.

D is not plausible. Without any idea that there might be a stuck rod, why would anyone EB.

6/04/14 Make look like D except normal boraton. For B add IAW GOP 6/18/14 SAT as revised.

2 H 3 X N E 003G2.4.50, Reactor Coolant Pump / 4P, Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

K/A is met.

I think the way the answers are written, C and D are not plausible.

Rearrange the answers like the ARP would do it.

C. Trip the Reactor and initiate 1-E-0; Go to 1-AP-9.02, Loss of RCP Seal Cooling. STOP the affected RCP and after 5 minutes CLOSE Pressurizer Spray Valve from Loop A..

D. Go to 1-AP-9.00, RCP Abnormal Conditions. Initiate an orderly shutdown, then CLOSE Pressurizer Spray Valve from Loop A.

STOP the affected RCP.

6/4/14 Based upon the above indications, what AP should be entered? Should the reactor be tripped or not?

6/18/14 SAT as revised.

036AA1.04, Fuel Handling Accident / 8, Ability to operate and / or 3 F 2 X B E monitor the following as they apply to the Fuel Handling Incidents:

Fuel handling equipment during an incident.

K/A is met.

Change the second bullet to state that the Fuel Handlers have stopped withdrawing the assembly from the core while doing a visual exam. Make it clear that it is still in the core.

Is this something you expect your ROs to know?

6/4/14 Add cavity level. Fuel fully withdrawn. AP-22.00 or AP-22.01? Then choice A and C but in vertical position.

6/18/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 4 H 3 S 004K5.06, Chemical and Volume Control / 1 & 2, Knowledge of the operational implications of the following, Concept of boron worth or inverse boron worth (reactivity, pcm/ppm).

K/A is met.

Do you expect your ROs to know the note about how to set the integrator without the procedure?

Although you have 4 different valuesfor the second answer, I see that it is really only 2 (-2 from calculation or -4 from calculation).

5 F 2 B S 005K5.09, Residual Heat Removal / 4, Knowledge of the operational implications of the following concepts as they apply the RHRS:

Dilution and boration considerations.

K/A is met.

Reword B to state a calculation is performed to ensure RHR volume combined with RCS volume will not dilute below minimum required boron.

6 H 2 N S 006K4.11, Emergency Core Cooling / 3, Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Reset of SIS.

K/A is met.

7 H 3 X B E 007A1.02, Pressurizer Relief/Quench Tank / 5, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:,Maintaining quench tank pressure.

K/A is met Change the second question to read The lowest pressure Change fourth bullet to state 63% and slowly rising 6/4/14. SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 8 H 3 X N U 007EK1.02, Reactor Trip - Stabilization - Recovery / 1, Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Shutdown margin.

K/A is met.

Change stem to read Which one of the following data sets describes the required boron concentration to maintain Shutdown Margin in the time period between 0 to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following the reactor trip? Assume no further operator actions other than maintaining RCS temperature?

As written A and C could both be correct. Both would provide adequate SDM. Without specific values to calculate SDM.

This might work if you specified the minimum required boron concentration.

6/4/14 Change question to ask if boration is required at 12 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

6/18/14 SAT as revised.

Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 9 F 2 X B E 027K2.01, Containment Iodine Removal / 5, Knowledge of bus power supplies to the following:, Fans K/A is met.

This is fine as long there is no ability to operate these fans locally. It looks like ND-88.4-LP-6 says that they can be operated at their individual breakers.

6/4/14 Sat as revised. First bullet states only leak has been identified.

008AA1.06, Pressurizer Vapor Space Accident/ 3, Ability to operate 10 H 3 X X X M U and / or monitor the following as they apply to the Pressurizer Vapor Space Accident: Control of PZR level.

K/A is met.

This is strange as written. The question asks what you should do and the aswers have things you shouldnt do.

How about you ask which pumps should be operating and your answers can be: None, B Charging, B LHSI, Both.

6/4/14. Remove 5 minutes. Comma after lowered.

6/18/14 SAT as revised.

11 F 2 X N E 008K3.03, Component Cooling Water / 8, Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:,

RCP.

K/A is met.

Not very discerning. A better question would be WOOTF, if any, with answers of None, A, B&C, All.

6/4/14. Move if any to after RCPs.

6/18/14 SAT as revised.

009EK3.05, Small Break LOCA / 3, Knowledge of the reasons for the 12 F 3 X N E following responses as the apply to the small break LOCA:, CCWS radiation alarm.

K/A is met.

Change question to read is the most likely cause.

6/4/14. Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 13 H 2 X B U 010K1.06, Pressurizer Pressure Control / 3, Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems, CVCS.

K/A is met.

C is the only plausible answer. If there is only one valve in AUTO in the system, any operator is going to chose that to adjust something.

I dont have a copy of OP-RC-003. Is there a preocedural method to control the system in manual?

6/4/14. Add limits on discrimantors.

6/24/14 SAT as revised.

14 F 2 B S 010K4.01, Pressurizer Pressure Control / 3, Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for the following, Spray valve warm-up.

K/A is met.

011EA2.10, Large Break LOCA / 3, Ability to determine or interpret 15 H 2 X N E the following as they apply to a Large Break LOCA: Verification of adequate core cooling.

K/A is met.

Change the cue to read and cannot be manually started.

Delete the initial conditions. They are redundant..

6/4/14 Sat as revised.

16 H 3 X N U 012K6.11, Reactor Protection / 7, Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Trip setpoint calculators.

K/A is NOT met.

This is close, but the K/A requires a loss or malfunction of the trip setpoint calculator. Change this to cause a failure in the pressure instrument input and it will meet the K/A.

Can the fourth bullet read failed high?

6/4/14 Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 17 H 3 X X B E 013K2.01, Engineered Safety Features Actuation / 2, Knowledge of bus power supplies to the following: ESFAS/safeguards equipment control.

K/A is met.

Change question to read WOOTF states a reason that a specific sequence is recommended by 1-AP-10.06, Loss of DC Power, when restoring power following a loss of a DC Bus?

Change answer C to To allow early restoration of letdown.

6/4/14 Sat as revised.

18 H 4 X N E 013K6.01, Engineered Safety Features Actuation / 2, Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors.

K/A is met.

Add if any to the stem of the question.

Correct answer D Si to SI (typo).

6/4/14 Sat as revised.

19 F 3 M S 015A4.02, Nuclear Instrumentation / 7, Ability to manually operate and/or monitor in the control room: NIS indicators.

K/A is met.

20 H 3 M E 015AK3.01, RCP Malfunctions /I 4, Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) : Potential damage from high winding and/or bearing temperatures.

K/A is met.

Clean up the answers by breaking the answers in two. For example:

RCP Motor Upper Thrust bearing temperature is 195 oF and Rising; Annunciator RCP Frame Danger is lit.

6/4/14 Sat as revised.

21 H 3 B S 016K1.08, Non nuclear Instrumentation / 7, Knowledge of the ph.ysical connections and/or cause effect relationships between the NNIS and the following systems: PZR PCS.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 22 F 2 X N E 022A3.01, Containment Cooling / 5, Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation.

K/A is mostly met.

Question needs reworded. It is too complex as written.

Which ONE of the following describes:

1) The status of Containment Air Recirculation Fans. AND
2) Which Recirculation Spray Pumps are operated to maintain containment pressure less than 13 psia after containment pressure has been returned to less than atmospheric pressure.

6/4/14 SAT as revised.

23 H 3 X M E 022AK1.03, Loss of Rx Coolant Makeup / 2, Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: Relationship between charging flow and PZR level.

K/A is met.

Change the stem to say The following is observed:

Then put the alarms at the top of the bulleted list.

6/4/14 Sat as revised.

24 H 3 X N E 025AA1.11, Loss of RHR System / 4, Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: Reactor building sump level indicators.

K/A is met.

An initial RCS pressure needs to be listed.

6/4/14 Initial pressure should be 300 psig. No trend required.

6/18/14 SAT as revised..

25 H 3 N S 026A4.05, Containment Spray / 5, Ability to manually operate and/or monitor in the control room: Containment spray reset switches.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 26 H 3 B U 026AA2.01, Loss of Component Cooling Water / 8, Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS.

K/A is met.

Too similar to RO question 12.

Are there any CC auto isolations at Surry? If so, use that tack.

Otherwise look for potential sump indications.

If you use this question instead of 12, give an RCS pressure and temperature in the initial conditions, but dont tell them that they are not on RHR yet.

6/4/14. Sat as revised.

27 F 2 B S 026K4.09, Containment Spray / 5, Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:

Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover).

K/A is met.

28 H 3 X B E 007K5.02, Pressurizer Relief/Quench Tank / 5, Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR.

K/A is met.

Do you normally use pressurizer heaters to support RCS heatup below 195 °F? If so, please specify which heaters are energized in the IC. Otherwise have the IC state that the heaters are off.

6/4/14. Sat as revised.

29 F 2 X M E 028K5.03, Hydrogen Recombiner and Purge Control / 5, Knowledge of the operational implications of the following concepts as they apply to the HRPS: Sources of hydrogen within containment.

K/A is met.

Remove Answer the following questions from the stem.

Is the term Zircaloy Hydriding use at Surry?

6/4/14 Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 30 F 2 X B E 029EK2.06, ATWS / 1, Knowledge of the interrelations between the breakers, relays, and disconnects following an ATWS.

K/A is met.

Change B to Open Closed Open If you wnted to then you could eliminate RTB A from the answers.

Could the question be rewritten as An inadvertent actuation of RPS A occurred?

6/4/14. Sat as revised.

31 H 2 X X X N E/U 033K3.02, Spent Fuel Pool Cooling /, Knowledge of the effect that a loss or malfunction of the Spent Fuel Pool Cooling System will have on the following: Area and ventilation radiation monitoring systems.

K/A is met.

How far below the low level alarm will the pool drain? Typically Ive seen syphon holes in the drain lines of SFPs. Once there, no further drainage will occur and rad levels at the crane will stanilize.

Also, how high would you expect rad level to get?

Im OK with this questioon if the conditions really could exist. Just make the last bullet become a standalone statement.

Also is it relevent that both ubits are at 100%. If so correct the grammar in the first line to state Units 1 and 2 are. Otherwise Unit 1 is 6/4/14 Sat as revised.

034K6.02, Fuel Handling Equipment / 8, Knowledge of the effect of a 32 F 2 N S loss or malfunction on the following will have on the Fuel Handling System : Radiation monitoring systems.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 33 H 3 X N E 004A2.26, Chemical and Volume Control / 1 & 2, Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low VCT pressure.

K/A is met.

Is it relevant that both units are at 100%? I think that stating Unit 1 is at 100% would be adequate.

Make the pressure in the stem at 16 psig and slowly lowering. This way the second part is testing that the applicant knows that there is a rupture in the VCT that requires isolating.

6/4/14. Sat as revised.

037AK3.06, Steam Generator Tube Leak./3, Knowledge of the 34 H 3 X N S reasons for the following responses as they apply to the Steam Generator Tube Leak: Normal operating precautions to preclude or minimize SGTR.

K/A is NOT met.

The question should deal with normal operating precautions to preclude or minimize SGTR. Possibly chemistry or differential pressure or temperatures.

Also remove the statement Based on the indications answer the following questions: That is self-evident.

6/4/14. After further review question was SAT as written.

35 H 3 B S 039A3.02, Main and Reheat Steam / 4S, Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS.

K/A is met.

36 F 2 X N S 040AG2.2.3, Steam Line Rupture - Excessive Heat Transfer / 4, (multi-unit license) Knowledge of the design, procedural, and operational differences between units.

K/A appears to be met.

Are these valves unique to Unit 2? For example, if I wanted to crosstie Unit 1 to Unit 2, would these same valves be accessed? If so this meets the K/A.

If the above is true, could we put a fire in the U2 turbine buiding, keep the evacuation, then have U2 loose its charging pumps?

6/4/14. After further review question was SAT as written.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 37 H 3 X M E 051AA2.02, Loss of Condenser Vacuum/4, Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.

K/A is met.

Change question to read WOOOTF shall be done first IAW 1-AP-14.00? This wil make the hoggers more plausible.

6/4/14. Sat as revised.

38 H 3 X B E 054AK3.01, Loss of Main Feedwater /4, Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Reactor and/or turbine trip manual and automatic.

K/A is met.

Make the first two bullets Initial Conditions.

The next section should be The following occurs:

Bulletize the rest, state that the alarms lock in or words to that effect.

Remove the first question and reword the second to ask What is the reason for the action(s) required by 1-AP-21.00? If you ask the first question, the answers make some of the distractors less plausible.

6/5/14 Going back to 2X2. Which describes actions IAW AP-21.

Second part A and B. by maintaining SG water levels.

6/18/14 SAT as revised.

056AA2.54, Loss of Off-site Power / 6, Ability to determine and 39 X E interpret the following as they apply to the Loss of Offsite Power:

Breaker position (remote and local).

K/A is met.

Make the D answer all running. This is plausible because it matches the breaker indications.

6/5/14. Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 059AK1.01, Acciental Liquid Rad Waste Rel, / 9, Knowledge of the 40 F 2 X X N U operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: Types & radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant.

K/A is NOT met.

This K/A isnt looking to determine if a source is contaminated or not, but rather what type of radiation (alpha, beta, gamma) and their units of intensity.

6/5/14 neutron and alpha can/cannot be detected in this room.

Correct answer.

6/18/14 SAT as revised.

41 F 2 X M U 059K3.03, Main Feedwater / 4S, Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/Gs.

K/A is NOT met.

This case is looking for some failure in the main feed system, not S/G level control. Look at something like a heater tube failures affect.

6/5/14 load is reduced to 85% IAW procedure. Is further load reduction required? Following the load reduction, SG press be ___

than the was at 100%.

6/19/14 Correct typo in Initial Conditions. Either capitalize feedwater or dont. Cant have it both wways. Otherwise SAT.

6/25/14 SAT as revised.

42 H 3 M S 061K6.02, Auxiliary/Emergency Feedwater / 4S, Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps.

K/A is met.

43 F 3 B S 062A1.01, AC Electrical Distribution / 6, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Significance of D/G load limits.

K/A is met.

This is fine if these values are expected to be memorized by the applicants.

6/5/14. SAT. Required knowledge.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 44 H 3 N E 062AA1.01, Loss of Nuclear Svc Water / 4, Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): Nuclear service water temperature indications.

K/A is met.

Make first bullet current tense.

Make the third bullet the second bullet.

6/5/14 Remove DRP info. Is Cont Pressure vs Water Temp .. met?

6/19/14. SAT as revised.

45 H 3 N S 063G2.1.31, DC Electrical Distribution / 6, Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

K/A is mostly met.

46 H 3 X N E 063K1.03, DC Electrical Distribution / 6, Knowledge of the physical connections and/or cause effect relationships between the DC electrical system and the following systems: Battery charger and battery.

K/A is met.

Change distractors to as follows A. Unit 1 A and Unit 2 B.

B. Unit 1 B and Unit 2 B.

C. Unit 2 A and Unit 2 B D. Unit 2 B only.

With the 2J bus de-energized, the 2B battery discharge is just about given.

6/4/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 47 F 2 X N E 064K1.03, Emergency Diesel Generator / 6, Knowledge of the physical connections and/or cause effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system.

K/A is met.

D is not plausible. If the fuel racks close off all fuel, how can the EDG idle?

6/4/14. Put automatic between specific and actions in first question.

6/19/14. SAT as revised.

48 H 2 X M E 065AG2.1.32, Loss of Instrument Air / 8, Ability to explain and apply all system limits and precautions.

K/A is met.

B is a subset of A, therefore this would cause applicants to stay away from both answers.

6/5/14. Make two by two. Is immediate entry required? Is reactor trip required 6/19/14. SAT as revised.

071A3.02, Waste Gas Disposal / 9, Ability to monitor automatic 49 H 3 N S operation of the Waste Gas Disposal System including: Pressure-regulating system for waste gas vent header.

K.A is met.

50 F 2 N S 072G2.1.28, Area Radiation Monitoring / 6, Knowledge of the purpose and function of major system components and controls.

K/A is met.

51 H 3 N S 073A2.02, Process Radiation Monitoring / 7, Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 52 F 3 M S 074EG2.4.21, Inad Core Cooling /4, Knowledge of the parameters and logic used to assess the status of safety functions.

K/A is met.

If you have feedback that the 2 column format is better, continue to use it. Otherwise just have bulleted sentences.

53 H 3 N S 076K2.08, Service Water / 4S, Knowledge of bus power supplies to the ESF-actuated MOVs.

K/A is met.

54 H 3 X N S 077AK2.01, Generator Voltage and Electric Grid Disturbances / 6, Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and motors.

K/A is met.

If system voltage is at its max and you are maximizing VARs in, arent you lowering a higher than normal voltage? If so, is the answer still correct?

6/5/14. This is how the system will respond. SAT.

55 H 3 N S 078A4.01, Instrument Air / 8, Ability to manually operate and/or monitor in the control room:Pressure gauges.

K/A is met.

56 H 3 X N E 079K4.01, Station Air / 8, Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with lAS.

K/A is met.

Make Bullet 5 as a stand alone (non-bulleted) sentence.

Label the last 3 bullets as current condition.

6/5/14. Two by two. Location of leak. Is U2 IAC running?. Put leak on SAC discharge.

6/19/14. SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 57 F 2 X B S 086A1.01, Fire Protection / 8, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: Fire header pressure.

K/A is met.

Do you expect your operators to know that FP-37 is on the diesel fire pump and FP-36 is on the motor driven? If this is answered yes by the Facility Rep, then this question is SAT.

6/5/14 SAT. This is requijred knowledge.

58 F 3 M S 103A2.04, Containment / 5, Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Containment evacuation (including recognition of the alarm).

K/A is met.

59 H 3 M S 103A3.01, Containment / 5, Ability to monitor automatic operation of the containment system, including: Containment isolation.

K/A is met.

60 F 2 . N S G2.1.29, Conduct of operations, Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

K/A is met.

61 F 3 N S G2.1.40, Conduct of operations, Knowledge of refueling administrative requirements.

K/A is met.

62 F 3 M S G2.1.5, Conduct of operations, Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

K/A is met.

63 F 2 M S G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 64 F 2 N S G2.2.2, Equipment Control, Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

K/A is met.

65 F 1 X B U G2.3.5, Radiation Control, Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

K/A is met.

A is not plausible and D is barely plausible. This is a general rad worker question. LOD =1.

6/5/14 Use N-16 monitor.

6/19/14 As written, 10% is never wrong for the first part of the question. Need to rephrase to something like the minimum power level at whichthey can be relied upon.

6/25/14 SAT as revised.

66 F 1 N U G2.3.7, Radiation Control, Ability to comply with radiation work permit requirements during normal or abnormal conditions.

K/A is met.

Why would any person who has worked in nuclear power pick B

anything but D. Perhaps use a survey map with an RWP and see if they can figure out if they can do a task. LOD=1.

6/5/14. Bank question used.. SAT as revised.

67 F 3 N E G2.4.1, Emergency Procedures/Plans, Knowledge of EOP entry conditions and immediate action steps.

K/A is met.

Modify second question to read All of the methods provided in this procedure to secure steam flow to the Main Turbine from the Control Room?

6/5/14. Sat as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 68 F 3 N E G2.4.32, Emergency Procedures/Plans, Knowledge of operator response to loss of all annunciators.

K/A is met.

1) Change second question to read Upon power restoration what is the minimum acceptable method to perform a functional check in order to confirm that alarming conditions in the field will actuate the appropriate alarm?

6/5/14. SAT as revised.

69 H 3 N S G2.4.4, Emergency Procedures/Plans, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

K/A is met.

70 H 2 N S WE03EK2.1, LOCA Cooldown Depress /4, Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

K/A is met.

71 H 3 N E WE04EG2.4.3, LOCA Outside Containment / 3, Ability to identify post-accident instrumentation.

K/A is met.

In the question, replace the comma with an and and the and would with a to.

6/4/14. SAT as reivsed.

72 H 3 M S WE05EK2.2, Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4, Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facilitys heat removal 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.

K/A is met.

Make all of the bullets except the last one part of the initial conditions.

Make the last bullet a stand alone statement.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 73 H 3 N S WE11EK1.3, Loss of Emergency Coolant Recirc./ 4, Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Annunciators and conditions indicating signals and remedial actions associated with the (Loss of Emergency Coolant Recirc).

K/A is met.

WE14EK2.1, Knowledge of the interrelations between the (High 74 H 3 N S Containment Pressure) and the following: / 5 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

K/A is met.

75 F 2 N E WE15EK1.2, Containment Flooding / 5, Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

K/A is met.

Following a Design Basis LOCA, the MINIMUM containment sump level to enter FR-Z.2, Response to Containment Flooding is

_____1)_____ feet, and entry is a(n) _____2) _____ Path.

Change a __ to a(n)___.

6/4/14. First part remains the same. Second pressure would be a red path to FR-Z.1.

6/19/14. SAT as revised.

ES-401 Written Examination Review Worksheet Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 76 H 2 X M S 004G2.2.22, Chemical and Volume Control / 1 & 2, Knowledge of limiting conditions for operations and safety limits.

K/A is met.

Why do you feel it is necessary to provide a drawing? This should be part of system knowledge.

6/4/14. SAT as is.

77 H 3 X M S 009EA2.39, Small Break LOCA / 3, Ability to determine or interpret adequate core cooling as it applies to a small break LOCA.

K/A is met.

Is A credible? If you dont meet RCP trip criteria, it is almost always due to subcooling. If you dont have subcooling, why would you stop SI?

78 H 3 M S 013A2.03, Engineered Safety Features Actuation / 2, Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Rapid depressurization K/A is mostly met.

79 H 3 N S 017G2.4.47, in-core Temperature Monitor / 7, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

K/A is met.

022AA2. 01, Loss of Rx Coolant Makeup I 2, Ability to determine 80 H 3 M S and interpret the following as they apply to the Loss of Reactor Coolant Makeup: (CFR 43.5/ 45.13) Whether charging line leak exists.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 81 H 3 X N E 024AG2.1.23, Emergency Boration/I 1, Ability to perform specific system and integrated plant procedures during all modes of plant operation.

K/A is met.

You have four different second part answers. If this answer is known, it makes the first part irrelevent and therefore would not meet the K/A. Why not choose the Delta flux answer associated with transients and the rod insertion associated with reactor trip and have a true 2 by 2 answer?

6/4/2014 Sat as revised.

82 H 2 X M E 027AA2.10, Pressurizer Pressure Control System Malfunction / 3, Ability to determine and Interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR heater energized/de-energized condition.

K/A is met.

Is it necessary to tell them that the Master Controller output goes to 0%? This should be testable knowledge.

Change the second part answer to read will not be solid when critical.

6/4/14 Added comma after operation in question.

6/17/14 SAT as revised.

83 H 2 X N U 033AG2.2.44, Loss of Intermediate Range NI / 7, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

K/A is met.

Question is NOT at SRO level. The removal of fuses is RO knowledge. Knowing that you must verify permissive light within one hour is RO knowledge.

6/4/14 Control Power fuses would/ would not be removed and make the second part ask what AP-4.0 requires.

6/17/14 SAT as revised.

Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

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 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 (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 (i.e., the question has a valid 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 (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 K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 84 H 2 N S 014A2.05, Rod Position Indication / 1, Ability to (a) predict the impacts of a reactor trip on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

K/A is met.

85 H 3 N S 057AG2.1.28, Loss of Vital AC Inst. Bus/ 6, Knowledge of the purpose and function of major system components and controls.

K/A is met.

059A2.01, Main Feedwater / 4S, Ability to (a) predict the impacts of 86 H 3 X N E feedwater actuation of AFW system on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

K/A is met.

Change 2nd distractor to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This is more plausible as action 22 of the AFW TS.

Is this how you want to ask the question? An alternative could be What LCO is entered? With the answers as Table 3.7-2, Action 24.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to restore. And Table 3.7-2, Action 22. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore.

6/4/14 Change first part to ask if TS entry is required. Provide TS 3.e and Action 24.

6/17/14 SAT as revised.

87 H 3 N S 061G2.4.47, Auxiliary/Emergency Feedwater, Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

K/A is met.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 88 H 2 X N E 075G2.2.44, Circulating Water / 8, Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

K/A is met.

You need a value and trend for intake canal leve to ensure single answer.

6/4/14 Change 25 ft and lowering.

6/17/14 SAT as revised.

078A2.01, Instrument Air /, Ability to (a) predict the impacts of the 89 H 3 X N U following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions.

K/A is NOT met.

Need to use procedures to control or mitigate. In this case I would suggest using 1-AOP-27.00. You can ask about the need to secure RHR pumps, or about alternate cooling methods , or isolating containment.

6/4/14. SAT as rewritten.

90 H 3 M S G2.1.25, Conduct of operations, Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

K/A is met.

91 H 3 X N E G2.1.32, Conduct of operations, Ability to explain and apply all system limits and precautions.

K/A is met.

There is a subset issue here. An applicant can claim that since 68%

is less than 75%, it is always correct. So he may answer correctly without knowing the information. More clearly phrase the question to ask what the TS states.

6/4/14. What is the max time to be less than 68%. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 30 min.

6/17/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 92 F 2 X M E G2.2.13, Equipment Control, Knowledge of tagging and clearance procedures.

K/A is met.

Remove because of a shortage of personnel from answer D.

6/14/04. Sat as rewritten.

93 H 3 N S G2.2.18, Equipment Control, Knowledge of the process for managing maintenance activities during shutdown operations.

K/A is met.

94 F 2 X N E G2.3.11, Radiation Control, Ability to control radiation releases.

K/A is met.

Change the second part to the following:

the dose to an individual standing _________________.

1) at the exclusion area boundary will not exceed 0.5 rem TEDE over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period.
2) in an unrestricted area will not exceed 0.002 rem in any one hour.

This second part is a Part 20 requirement that does not apply in this case.

6/4/14 Sat as rewritten.

G2.3.12, Radiation Control, Knowledge of radiological safety 95 F 2 X N E principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

K/A is not reall met.

Since there are four different answers fo the second part of the question, the first part is not relevent. Suggest that you delete the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> answers from the second part. This would be an adequate question then.

6/4/14 Added maximum prior to the word time in question 2. No press release is planned to be issued.

6/17/14 SAT as revised.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 96 H 2 X N E G2.4.28, Emergency Procedures/Plans, Knowledge of procedures relating to emergency response to sabotage.

K/A is met.

I believe that 0-AOP-36.00 requires both units be tripped upon breaching the fences. If so, let the applicants know that the applicable portions of the AOP are in progess with no issues.

6/4/14 Sat as rewritten.

97 F 3 S WE11EG2.1.32, Loss of Emergency Coolant Recirc. /4, Ability to explain and apply all system limits and precautions.

K/A is met.

98 H 3 S WE12EG2.4.4, Steam Line Rupture - Excessive Heat Transfer /4, Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

K/A is met.

99 H 2 B S WE16EA2.2, High Containment Radiation / 9, Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

K/A is met.

100 H 3 N S WE01EA2.1, Rediagnosis / 3, Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

K/A is met.

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Surry Date of Exam: 08/05/14 Exam Level: ROj SROE Initials Item Description a b c

1. Clean answer sheets copied before grading -2 ,ii4
2. Answer key changes and question deletions justified and documented AX
3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail
5. All other failing examinations checked to ensure that grades are justified
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature Date
a. Grader Newton Lacy
b. Facility Reviewer(*) N/A
c. NRC Chief Examiner (*) David Lanyi /

/ /7/fy

d. NRC Supervisor (*)

(*) The facility reviewers signature is not applicable for e nations graded by the NRC; two independent NRC reviews are required.

ES-403, Page 6 of 6

£x4M fA/v ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

5_jR Date of Examination:

TuL1 c.//

Initials Item Task Description

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

R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. (17 T

T E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. (/9
d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. M i4 N
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, S and major transients.

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 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 from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative 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 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 T (3) no tasks are duplicated from the applicants audit test(s)

(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 (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. 2)7 it E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 7
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 7 R Check for duplication and overlap among exam sections. 41:4
d. 1 L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)

If

c. NRC Chief Examiner (#) 1I4 - .4ArRt
d. NRC Supervisor ,tAL4Ot4 i WlPLLMJ1/

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

Not applicable for NRC-prepared examination outlines

- WR/77EA) &4m

Retrieved from "https://kanterella.com/w/index.php?title=ML16089A388&oldid=2444696"