ML17188A457
| ML17188A457 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/07/2017 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML17188A457 (55) | |
Text
ES-201 Examination Preparation Checklist Form ES-201-f Facility: .5 Date of Examination: _)O(LofY 0I Developed by: Written: Facility NRC II Operating Facility NRC
.
. Chief Target Task Description (Reference) Examiners Date Initials
-180 1 Examination administration date confirmed (C.1 a; C.2.a and b) qwc
-150 2. NRC examiners and facility contact assigned (C.1 .d; C.2.e) qwc
-150 3. Facility contact briefed on security and other requirements (C.2.c)
-150 4. Corporate notification letter sent (C.2.d) çwc 1-120] 5. Reference material due (C.1.e; C.3.c; Attachment 3)
{-90} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, WC ES-301-2, ES-301-5, ES-D-l, ES-401-1/2, ES-401N-112, ES-401-3, ES-401N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; C.3.d)
{-85} 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee ?WC (C.2.h; C.3.e)
{-60) 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, ES-401N-6, and any Form ES-201-2, ES-201-3, ES-301-1, or ES-301-2 updates), and reference materials due (C.1 .e, f, g and h; C.3.d)
-45 9. Written exam and operating test reviews completed. (C.3.f) qwe
-30 10. Preliminary license applications (NRC Form 398s) due (Cli; C.2.g; ES-202) WC
-21 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) qwc
-21 12. Examinations reviewed with facility licensee (Cl.]; C.2.f and h; C.3.g) qwc
-14 13. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202) lV
-14 14. Written examinations and operating tests approved by NRC supervisor (C.2.i; cwe C.3.h)
-7 15. Facility licensee management queried regarding the licensees views on the qwe examination. (C.2 j)
-7 16. Final applications reviewed; 1 or2 (if>l0) applications audited to confirm JWC qualifications I eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)
-7 17. Proctoring/written exam administration guidelines reviewed with facility licensee qw (C.3.k)
-7 18. Approved scenarios, job performance measures, and questions distributed to NRC lVC examiners (C.3.i)
- Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by case basis in coordination with the facility licensee.
[Applies only] {Does not apply} to examinations prepared by the NRC.
ES-201 Examination Outline Quality Checklist Form ES-201-2 Fad ity Srry PowCr Station Date of Exarnnatwc 9/t9/2016 tern Task Descrpton Si-0 I a Verify that the outline(s) fit(s) the appropoate mode), in accordance with ES-401 or ES-401N 1%, (l..9 R Assess whether tie OutIne was systematically and randorn:y prepared in accordance itfl 9
[Section D 1 of ES-401 or ES-401N sic wnether at KA categories are appropiately sarnplea c Assess whether the outline over-emphasizes any systems, evoiutiuns, or generic topics i 2 d Assess whether tie justifications for desetected or rejected KJA statements are appropriate (-
2 a Using Form ES-301-5 verify tiat the proposed scenario sets cover the rnquired number of normal evolutions instrument and comoonent failures technical specflctions. acd major S transients M b Assess whether there are enough scenario sets (and spares; to test the projected number and u mix of applicants in accordance with the expected crew composition ard rctaton schedule L without compromising exam integrity, and ensure that each applicant can be tested using at i çt3 A least one new or s.gnificantly modified scenano, that no scenarios are duplicated from the V T applicants audit test(s), and that scenarios will not ce repeated on subsecuent days c To the extent possible, assess whether the outline(s) conform(s) with the quaitative and quantitalve criteria specified on Form ES-301 -4 and describec in Appends 0 ., 4
- 3. a Verify that the systems watk-through outline meets the crtera specified on Form ES-301-2.
- 11) the outline(s) contain(s) the required number of control room and in-plant tasks dstributed W among the safety functions as specfied on the form A l2) task iaoetition trm tne last two NRC examinations is within the l,mds specified on the form L (3) no tasks are duplicated from the applicants audit test(s) S.
K (4 the number of new or modified tasks meets or exceeds the minimums specrfed on the form (5) the number of alternate atn. ow-power emergency. and RCA tasks meet the criteria on T the form H
R b Verify that tie administrative outline meets the criteria specified on Form ES-301-1.
(1) tie tasks are distc buted among the topics as specified on the form u (2) at least one task is new or significantly modified o (3) no more than one task is repeatec trom the last two NRC icensrng examnations 1$,
H
- c. Determine if there are enough different outlines to test the projected number and mis of applicants_and ensure that no items are_duplicated_on_subsequent_days - -.
4 a Assess whether plant-specific prorties (including PRA and IPE irsights) are covered in tne approprate exam sections o Assess woether the 10 CFR 55 41/43 and 55.45 sampling is appropriate. R
- c. Ensure that KJA importance ratings (except for plant-specific prorties) are at least 2 5 R ii. Check for duplication and overlap among exant sections Q C e Check the entire exam for balance of coverage I Assess whether the exam fits_the_appropriate_ob_eel_(RD_or_SRO)
Printed Na / nat re Dale a Author Michael R (clever) 7_yt_-
b Facilty Reviewer (j Rich Philpotl c NRCCniefExaminer.,4) ;.-. 5 y.i_.
o NRC Suoemisor GtCL LJ Iij%I.
Note 4 Independent NRC reviewer nitial items in Column c, chief examiner concurrence required Not applicable foi NRC-prepared examination outlines 0 Sample plan developed by Chief Examiner, Bruno Caballero.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: _Surry________________________ Date of Examination: _9/19/2016__
Examination Level: RO SRO Operating Test Number: SR 2016 301 Administrative Topic (see Note) Type Describe activity to be performed Code*
Conduct of Operations M, R Perform a Calorimetric Conduct of Operations N, R RCS Leakrate Equipment Control D, R Dose Rate Calculation Radiation Control N, R Complete EPIP-2.01 Initial Report Form Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items)
- 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: 9/19/2016____
Examination Level: RO SRO Operating Test Number: SR 2016 301 Administrative Topic (see Note) Type Describe activity to be performed Code*
Conduct of Operations M, R Shift Staffing Perform a Calorimetric Conduct of Operations M, R TRM Determination RCS Leakrate Equipment Control N, R Tech Spec Determination Radiation Control D, R Dose Rate Calculation Emergency Plan N, S Determine PAR NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- 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: _9/19/16______
Exam Level: RO SRO-I SRO-U Operating Test No.: SR 2016 301____
Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function
- b. Isolate a Leaking RSHX (059 AK3.01 3.5/3.9) D,L,S 9
- c. Perform E-0, Attachment 4 (WE14 EA1.3 3.3/3.8) N,L,EN,S 5
- d. Transfer the SI System to Cold Leg Recirc (006 A3.08 4.2/4.3) D,A,L,S 2
- e. Respond to a Loss of the Operating RHR Pump (005 A2.03 2.9/3.1) D,L,S 4P
- f. Bypass Containment Detection ON 0-FP-MON-IMS-1 D,S 8 (086 A4.02 3.5 3.5)
- g. Respond to a Secondary Transient (SYS 016 A2.01 3.0/3.1) A,D,S 4S
- h. Synchronize and Transfer Electrical Power Systems D,S 6 (062 A4.01 3.3/3.1)
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Locally Isolate Flooding #3 MER (062 AA2.03 2.6/2.9) D,A,L,E 4P
- k. Locally Swap U-2 AFW to Fire Water (061 K4.01 4.1/4.2) M,L,E,R 4S
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 A)lternate path 4 (4 - 6)
(C)ontrol room (D)irect from bank 8 ( 9)
(E)mergency or abnormal in-plant 3 ( 1)
(EN)gineered safety feature 1 ( 1) (control room system)
(L)ow-Power / Shutdown 7 ( 1)
(N)ew or (M)odified from bank including 1(A) 3 ( 2)
(P)revious 2 exams 0 ( 3) (randomly selected)
(R)CA 1 ( 1)
(S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _ Surry______________________ Date of Examination: _9/19/16____
Exam Level: RO SRO-I SRO-U Operating Test No.: SR 2016 301___
Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function
- b. Isolate a Leaking RSHX (059 AK3.01 3.5/3.9) D,L,S 9
- c. Perform E-0, Attachment 4 (WE14 EA1.3 3.3/3.8) N,L,EN 5
- d. Transfer the SI System to Cold Leg Recirc (006 A3.08 4.2/4.3) D,A,L,S 2
- e. Respond to a Loss of the Operating RHR Pump (005 A2.03 2.9/3.1) D,L,S 4P
- f. Bypass Containment Detection ON 0-FP-MON-IMS-1 D,S 8 (086 A4.02 3.5 3.5)
- g. Respond to a Secondary Transient (SYS 016 A2.01 3.0/3.1) A,D,S 4S h.
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Locally Isolate Flooding #3 MER (076 A2.01 3.5/3.7) D,A,L,E 4P
- k. Locally Swap U-2 AFW to Fire Water (061 K4.01 4.1/4.2) M,L,E,R 4S
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 SRO-I A)lternate path 4 (4 - 6)
(C)ontrol room (D)irect from bank 6 ( 8)
(E)mergency or abnormal in-plant 3 ( 1)
(EN)gineered safety feature 1 (1) (control room system)
(L)ow-Power / Shutdown 8 ( 1)
(N)ew or (M)odified from bank including 1(A) 4 ( 2)
(P)revious 2 exams 0 ( 3) (randomly selected)
(R)CA 1 ( 1)
(S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _ Surry ______________________ Date of Examination: _9/19/16_____
Exam Level: RO SRO-I SRO-U Operating Test No.: _ SR 2016 301___
Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function
- b. Isolate a Leaking RSHX (059 AK3.01 3.5/3.9) D,L,S 9
- c. Perform E-0, Attachment 4 (WE14 EA1.3 3.3/3.8) N,L,EN,S 5 d.
e.
f.
g.
h.
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Locally Isolate Flooding #3 MER (076 A2.01 3.5/3.7) D,A,L,E 4P
- k. Locally Swap U-2 AFW to Fire Water (061 K4.01 4.1/4.2) M,L,E,R 4S
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 SRO-U A)lternate path 2 (2-3)
(C)ontrol room (D)irect from bank 2 ( 4)
(E)mergency or abnormal in-plant 2 ( 1)
(EN)gineered safety feature 1 ( 1) (control room system)
(L)ow-Power / Shutdown 3 ( 1)
(N)ew or (M)odified from bank including 1(A) 3 ( 1)
(P)revious 2 exams 0 ( 2) (randomly selected)
(R)CA 1 ( 1)
(S)imulator
ES-301 Operating Test Quahty Checklist Form ES-301-3 Facility: Date of Examination: 911912016 Operating Test NumberSRaol-2016
.
- 1. General Crrtena
.
initials
a b*
- a. The operating test conforms with the previously approved outbne, changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution). !,1
- 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 D.1 a.)
- a. Overlap with the written examination and between different parts of the operating test is Within acceptable limits.
4
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level. h,
- 2. Walk-Through Criteria
- a. Each JPM includes the following, as applicable:
initial conditions
- initiating cues
- references and tools, including associated procedures
- reasonable and vatidated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee UP
- operationally important specific performance criteria that include:
detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the 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 ftom the last 2 NRC examinations) specied 1, ftp on those forms and Form ES-201 -2.
- 3. Simulator Criteria The associated simulator operating tests (scenario sets) have been reviewed in accwdance with Form ES-3Ol4anda copy is attached.
Printed Name / Signature Date
- a. Author Michael R Meyer! 1 -.
- b. Facility Reviewerf) Rich PhilpotI c NRC Chief Examiner f#) / ,
- d. NRC Supervisor (i L] .C\ 9 J 1- Zo l(.
NOTE:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column e; chief examiner concurrence required.
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Surry Date of Exam: (/19/16 Operating Test No.: SR 2016 301 A E Scenarios P V 1 2 3 4 T M P E O I L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION T N I T S A B S A B S A B S A B I C A R T O R T O R T O R T O M A T L U N Y O C P O C P O C P O C P M(*)
T P E R I U RO RX 5 6 6 1 1,1 1 1 0 1,1 NOR 1 1 1 SRO-I I/C 2,3 2,5 3,5 3,4 2,2 4 4 2 2,2 MAJ 6 7,8 7 6 1,2 2 2 1 SRO-U 1,1 TS 0 2 2 RO RX 1 1 0 NOR 2,5 1,6 1,6 1 2,2 1 1 1 2,1 SRO-I I/C 1,4 3,4 2,4 2,5 2,2 4 4 2 2,2 MAJ 6 7,8 7 6 1,2 2 2 1 SRO-U 1,1 TS 0 2 2 RO RX 5 6 6 1 1,1 1 1 0 1,1 NOR 1 1 0,1 1 1 1 SRO-I 1,0 I/C 1,2,3, 2,3,4 2,3,4 2,3,4 4,4 4 4 2 4 ,5 ,5 ,5 4,4 SRO-U MAJ 6 7,8 7 6 1,2 2 2 1 1,1 TS 1,2 2,3,5 3,4,5 2,4 2,3 0 2 2 3,2 RO RX 5 6 6 1 1,1 1 1 0 1,1 NOR 1 1 0,1 1 1 1 SRO-I 1,0 I/C 1,2,3, 2,3,4 2,3,4 2,3,4 4,4 4 4 2 4 ,5 ,5 ,5 4,4 SRO-U MAJ 6 7,8 7 6 1,2 2 2 1 1,1 TS 1,2 2,3,5 3,4,5 2,4 2,3 0 2 2 3,2
Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
- 4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.
ES-301 Competencies Checklist Form ES-301-6 Facility: Surry Date of Examination: 9/19/16 Operating Test No.: SR301-2016 APPLICANTS RO RO RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 1,2,3, 2,3, 2,3, 2,3, 1,2, 2,3, 2,3, 2,3, 1,2, 2,3, 2,3, 2,3,4, 4,6 4,5, 4,5, 4,5, 3,4, 4,5, 4,5, 4,5, 3,4, 4,5, 4,5, 5,6 Events and Conditions 7,8 7 6 6 7,8 7 6 6 7,8 7 Comply With and ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL Use Procedures (1)
Operate Control ALL ALL ALL ALL Boards (2)
Communicate ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate ALL ALL ALL ALL ALL ALL ALL ALL Supervisory Ability (3)
Comply With and 1,2 2,3, 3,4, 2,4 1,2 2,3, 3,4, 2,4 5 5 5 5 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. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)
ES-401, Pv. (ç PWR Examination Outline Form ES-401-2 Facility: L1IR Y DateofExam: T4&l3EI?. 25ib RD K/A Cateay Points SRO-Only_Points Tier Group K K K K K KAAAAIG* A2 G* Total 1 2 3 4 5 6 1 2 3 41 Total
- 1. 1 3 18 3 6 Emergency& 1 -, - - -,
Abnormal 2 I
! N/A 0<
N/A 9 4 Evolufions Tier Totals 4 4 5 4 27 6 5 10 i 3LZ 2
0 3333 - 28 3 5 Rant 2 TTI(T11011T 10 3 Systems Tier Totals 4 3 3 3 + 4 4 3 3 + 3 38 3 8
- 3. Generic Knowledge and Abilities 1 2 4 10 1 2 4 7 Categories 3 3 1 3 1 2. I I Note: 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 Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The
. $i.. final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RD exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do
, not apply at the facility should be deleted with justification; operationally important, site-specific I7I systems/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the 1& 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 (lR) of 2.5 or higher shall be 0- selected. Use the RD and SRO ratings for the RD and SRO-only portions, respectively.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
1t 6.
L7. The generic(G) K/As in Tiers 1 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 D.1 .b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance IVVL 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 a category 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 RD and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and I point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As ES-401, Page 38 of 50
ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
ReactorTrip Stabilization - Recovery 4.1 4.3 Ability to prioritize and interpret the significance of each
/1 annunciator or alarm.
008AK3.0l Pressurizer Vapor Space Accident / 3 3.7 4.4 Why PZR level may come back on scale if RCS is saturated.
011 EK2.02 Large Break LOCA / 3 2.6 2.7 Pumps 015AK2.l0 RCP Malfunctions/4 2.8 2.8 El El El El El El El El El RCP indicators and controls 022AG2.2.37 Loss of Ax Coolant Makeup / 2 3.6 4.6 Ability to determine operability and/or availability of safety related equipment 026AA1.03 LossofComponentCoolingWater/8 3.6 3.6 [] SWS as a backup to the CCWS
[]
029EK1.0l ATWS/1 2.8 3.1 El El El El El El El El Reactor nucleonics and thermo-hydraulics behavior O4OAA1.18 -
Steam Line Rupture Excessive Heat 4.2 4.2 Control rod position indicators Transfer / 4 El El El El El El El El El El 054AA2.03 Loss of Main Feedwater / 4 4.1 4.2 El El El El El El El Conditions and reasons for AFW pump startup El El El 055EA2.03 Station Blackout / 6 El El El El El El El i El El El Actions necessary to restore power 056AK1 .01 Loss of Off-site Power / 6 3.7 4.2 El El El El El El El El El El Principle of cooling by natural convection Page 1 of 2 10/28/2015 4:44PM
ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
IRO SRO 058AK3.01 Loss of DC Power! 6 3.4 3.7 Use of dc control power by D/Gs 062AA2.03 Loss of Nuclear Svc Water / 4 2.6 2.9 The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 065AK3.08 Loss of Instrument Air! 8 3.7 3.9 Actions contained in EOP for loss of instrument air 077AK1 .03 Generator Voltage and Electric Grid 3.3 3.4 Under-excitation Disturbances / 6 WEO4EA1 .3 LOCA Outside Containment / 3 3.8 4.0 Desired operating results during abnormal and emergency situations.
WEO5EK2.2 -
Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary Secondary Heat Sink / 4 El coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
well EG2.4.6 Loss of Emergency Coolant Recirc. / 4 3.7 4.7 El El El El El El El El El El Knowledge symptom based EOP mitigation strategies.
Page 2 of 2 10/28/2015 4:44PM
ES-401, REV 10 T1G2 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 001 AK3.02 Continuous Rod Withdrawal / 1 3.2 4.3 Tech-Spec limits on rod operability 036AA2.0l Fuel Handling Accident! 8 3.2 3.9 ARM system indications 037AG22.12 Steam Generator Tube Leak / 3 3.7 4.1 Knowledge of surveillance procedures.
O51AA1.04 Loss of Condenser Vacuum /4 2.5 2.5 Rod position 059AA1 .02 Accidental Liquid Rad Waste Rel. / 9 3.3 3.4 ARM system 069AK3.01 Loss of CTMT Integrity / 5 3.8 4.2 Guidance contained in EOP for loss of containment integrity 074EK2.09 mad. Core Cooling / 4 2.6 2.6 Controllers and positioners WEO3EK1 .1 LOCA Cooldown - Depress. / 4 3.4 4.0 Components, capacity, and function of emergency U U U systems.
WE15EA2.2 Containment Flooding / 5 2.9 3.3 U U U U U U U U U U Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
Page 1 of 1 10/28/2015 4:44PM
ES-401, REV 10 T2G1 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:
003A2.03 Reactor Coolant Pump 2.7 3.1 Li Li Li Problems associated with RCP motors, including faulty motors and current, winding and bearing temperature problems 004A2.27 Chemical and Volume Control 3.5 4.2 Improper RWST boron concentration 004K5.46 Chemical and Volume Control 2.5 2.9 Reason for going solid in PZR (collapsing steam bubble):
make sure no steam is in PRT when PORV is opened to drain RCS 005A1.03 Residual Heat Removal 2.5 2.6 Li Li Li Closed cooling water flow rate and temperature 006A2.13 Emergency Core Cooling 3.9 4.2 Li Li Li Li Li Li Li 1 Li Li Li Inadvertent SIS actuation 006G2.l .28 Emergency Core Cooling 4.1 4.1 Li Li Knowledge of the purpose and function of major system components and controls.
007A1 .02 Pressurizer Relief/Quench Tank 2.7 2.9 Maintaining quench tank pressure 008K2.02 Component Cooling Water 3.0 3.2 Li Li Li Li Li Li Li Li Li Li CCW pump, including emergency backup 01 0K1 .08 Pressurizer Pressure Control 3.2 3.5 Li Li Li Li Li Li Li Li Li Li PZR LCS 010K6.01 Pressurizer Pressure Control 2.7 3.1 Li Li Li Li Li Li Li Li Li Li Pressure detection systems 012K4.07 Reactor Protection 3.0 3.2 LiLiLiLiLiLiLiDLiLi First-out indication Page 1 of 3 10/28/2015 4:44PM
ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
no sno 01 3A4.0l Engineered Safety Features Actuation 4.5 4.8 ESFAS-initiated equipment which fails to actuate 013K6.0l Engineered Safety Features Actuation 2.7 3.1 Sensors and detectors 022A4.0l Containment Cooling 3.6 3.6 CCS fans 026A1 .03 Containment Spray 3.5 3.5 Containment sump level 026A4.0l Containment Spray 4.5 4.3 CSS controls 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS 039K5.08 Main and Reheat Steam 3.6 3.6 J Effect of steam removal on reactivity 059K4. 18 Main Feedwater 2.8 3.0 Automatic feedwater reduction on plant trip 061 K2.03 Auxiliary/Emergency Feedwater 4.0 3.8 AFW diesel driven pump 062A3.0l AC Electrical Distribution 3.0 3.1 Vital ac bus amperage
063G2.4.20 DC Electrical Distribution 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.
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ES-401, REV 10 T2G1 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:
PC SRO 063K3.02 DC Electrical Distribution Components using DC control power 064K6.08 Emergency Diesel Generator 3.2 3.3 DEED EDEED Fuel oil storage tanks 073K5.02 Process Radiation Monitoring 2.5 3.1 EEEJ LI EJEDEJE Radiation intensity changes with source distance 076K1.15 Service Water 2.5 2.6 DEED LI EDEED FPS 078K3.03 Instrument Air 3.0 3.4 EiEIE LI EDEEJE Cross-tied units 103K1.02 Containment 3.9 4.1 EJELIE E EDEEJE Containment isolation/containment integrity Page 3 of 3 10/28/2015 4:44PM
ES-401, REV 9 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:
RD SRO 015A1.02 Nuclear Instrumentation 3.5 3.6 LI SUR 016A3.02 Non-nuclear Instrumentation 2.9 2.9 LI LI LI LI L] LI LI LI Relationship between meter readings and actual parameter value 027K2.0l Containment Iodine Removal 3.1 3.4 Fans 028K5.04 Hydrogen Recombiner and Purge 2.6 3.2 The selective removal of hydrogen Control 034K6.02 Fuel Handling Equipment 2.6 3.3 Radiation monitoring systems 071 K3.04 Waste Gas Disposal 2.7 2.9 [] [ LI LI LI LI LI LI LI LI Ventilation system 072A4.0l Area Radiation Monitoring 3.0 3.3 LI LI LI LI LI LI LI LI LI LI Alarm and interlock setpoint checks and adjustments 075G2.l .30 Circulating Water 4.4 4.0 LI LI LI LI LI LI LI LI LI LI Ability to locate and operate components, including local controls.
079K4.0l Station Air 2.9 3.2 LI LI LI LI LI LI LI LI LI LI Cross-connect with lAS 086K1 .02 Fire Protection 2.7 3.2 LI LI LI LI LI LI LI LI LI LI Raw service water Page 1 of 1 10/28/2015 4:44PM
ES-401, REV 10 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 G2.1.15 Conduct of operations 2.7 3.4 Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
G2.1.3 Conduct of operations 3.7 3.9 Knowledge of shift or short term relief turnover practices.
G2.1 .43 Conduct of operations 4.1 4.3 Ability to use procedures to determine the effects on reactivity of plant changes G2.2.20 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.
G2.2.22 Equipment Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.
G2.2.7 Equipment Control 2.9 3.6 Knowledge of the process for conducting special or infrequent tests G2.3.1 3 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.4.1 1 Emergency Procedures/Plans 4.0 4.2 Knowledge of abnormal condition procedures.
G2.4.13 Emergency Procedures/Plans 4.0 4.6 Knowledge of crew roles and responsibilities during EOP usage.
G2.4.27 Emergency Procedures/Plans 3.4 3.9 Knowledge of fire in the plant procedures.
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ES-401, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 029EA2.09 ATWS I 1 4.4 4.5 Occurrence of a main turbine/reactor trip 038EG2.4.8 Steam Gen. Tube Rupture / 3 3.8 4.5 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
054AG2.l .23 Loss of Main Feedwater / 4 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
055EA2.03 Station Blackout / 6 3.9 4.7 Actions necessary to restore power 058AG2.4.20 Loss of DC Power / 6 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.
WE12EA2.2 -
Steam Line Rupture Excessive Heat 3.4 3.9 Adherence to appropriate procedures and operation Transfer / 4 within the limitations in the facilitys license and amendments.
Page 1 of 1 10/28/2015 4:44PM
ES-401, REV 10 SRO T1G2 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 061 AG2.4.30 ARM System Alarms /7 2.7 4.1 EEDDDDDDDD Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
068AA2.08 Control Room Evac. / 8 3.9 4.1 E DDE DED S/G pressure weO8EG2.1.19 RCS Overcooling - PTS/4 3.9 3.8 Ability to use plant computer to evaluate system or E DEE DEEDED component status.
WE13EA2.1 Steam Generator Over-pressure/4 2.9 3.4 E ÜD DEE DEE Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Page 1 of 1 10/28/2015 4:44PM
ES-401, REV 10 SRO T2G1 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 012A2.Ol Reactor Protection 3.1 3.6 Faulty bistable operation 039A2.03 Main and Reheat Steam 3.4 3.7 Indications and alarms for main steam and area radiation monitors (during SGTR) 062A2.04 AC Electrical Distribution 3.4 3.1 Effect on plant of de-energizing a bus 076G2.l .32 Service Water 3.8 4.0 LI LI LI LI Ability to explain and apply all system limits and precautions.
1 03G2.2.44 Containment 4.2 4.4 LILILILILILILILILILI 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 10/28/2015 4:44PM
ES-401, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 002A2.04 Reactor Coolant 4.3 4.6 Loss of heat sinks 014G2.2.22 Rod Position Indication 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.
068A2.02 Liquid Radwaste 2.7 2.8 Lack of tank recirculation prior to release Page 1 of 1 10/28/2015 4:44 PM
ES-401, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l .41 Conduct of operations 2.8 3.7 Knowledge of the refueling processes G2.l.7 Conductof operations 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
G2.2.13 Equipment Control 4.1 4.3 Knowledge of tagging and clearance procedures.
G2.2.40 Equipment Control 3.4 4.7 Ability to apply technical specifications for a system.
G2.3.12 Radiation Control 3.2 3.7 Ej Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.46 Emergency Procedures/Plans 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.
G2.4.9 Emergency Procedures/Plans 3.8 4.2 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
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ES-401 Written Examination Review Worksheet Form ES-401-9
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only K/A mismatch. K/A is for continuous rod withdrawal, question is for rod drop. Also, actual drop time is window dressing. Deleted actual rod drop time.
Changed P1 question to meet K/A.
1 F 2 N U I think it has a subset issue. If B is true, A is true.
Chang to ask for a maximum drop time.
Added maximum to P2 question to correct subset issue.
SAT If the RCP is tripped IAW step 16ff there is no procedure direction to close a spray valve. Change to ask the relationship between RCPs and spray valves. Moved AP-9.00 ref. from question to P1.
Changed Part 2 to question relationship between 2 F 2 N E RCPs and Spray valve.
Second part is clumsy. Change to ___ spray valve must be closed when 1-RC-P-1A is tripped.
Changed second part as noted.
SAT a minimum boron of should say a minimum boron 3 F 2 N E concentration of. Added concentration to P1.
SAT This question does not test the Effects of boron saturation on ion exchanger behavior i.e. What happens differently when saturated vs. not saturated.
Also has subsset issues. If A is true, so is B. Same with C and D. Changed Q to better meet K/A.
Question stem changed by asking effect of changing 4 H 2 X X N U temp for a demin bed that has been in service and is boron saturated. This tests knowledge of change in boron saturation. Changed P2 to eliminate subset by asking for maximum allowed difference in boron allowed.
SAT 5 H 2 N S Change to ask for the first SI signal actuated.
6 H 4 N E Changed P1 to ask for first SI signal.
SAT 7 H 2 N S
Initial PRT conditions and RCP status are window dressing. Removed PRT, and RCP conditions from 8 H 2 M E stem.
SAT Spurious is window dressing. Removed Spurious 9 H 2 N E from question stem.
SAT 10 H 2 N S 11 H 2 N S 12 H 2 N S 13 H 2 N S Do not diagnose in stem (LBLOCA). Removed 14 H 2 N E LBLOCA from stem.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only Borderline LOD 1.
The question gives that the initiating event is a loss of flow and asks the applicant to determine that the cause of the trip is loss of flow.
Change the initial condition to a power level closer to (but above) P-8.
Perhaps 2-part. First part, is cause of trip. RCS flow 15 F 2 N E or SG level. Second part, Is this indicated by color or flashing rate.
The reason for the RCP trip is window dressing.
Changed power level in stem of question to 40%.
Changed to 2-part question. P1 asks for annunciator that caused reactor trip. P2 asks for color of First out annunciator.
SAT Do not diagnose in stem (LBLOCA). Replaced LBLOCA with indications that would be present; Crew enters AP-16.00 (Initial); RCS pressure 150 psia and lowering (Current).
Subset. If A is true, B is true. Say minimum action required. Also, since the justification for the distractor 16 H 2 N E is that a different pump requires CLS to be reset, that seems like a more credible distractor (Reset CLS, place control switch in PTL.
Changed Part 2 to What is minimum action required Changed distractor A2 and C2 as noted above.
SAT 17 H 2 N S 18 H 2 B S to minimize the time required to repressurize the RCS is not a credible distractor. What is the link between continued RCP operation and time to 19 F 2 X B E subsequently repressurize? Changed C2 and D2 distractor to a more credible distractor that relates to Seal DP.
SAT One only needs to know the definition of the word median to get the second half correct. Suggest you ask about control response (or lack of control response). Changed P2 to ask about Control Rods.
20 H 2 X N E Change from asking what will happen to asking what should happen.
Changed P2 question to Should control rods move?
Do not diagnose in the stem (SBLOCA). Just give observable info the applicant needs to answer the 21 F 2 N E question. Deleted small break LOCA. Added bullet to indicate RCS pressure is 800 psig and lowering.
SAT It is intuitive that the least number of charging pumps best accomplishes overpressure mitigation. The applicant does not have to know anything about the LCO to get this one. Also this has nothing to do with loss of Rx coolant makeup. Changed question to better meet K/A. Question poses scenario where a 22 F 2 X X N U boration path is rendered inop. Candidates have to assess if they meet TS requirements for Boron injection.
The word claiming in the stem is unnecessary.
Removed claiming and replaced with ____, making this question a fill-in-the-blank question.
SAT KA mismatch. Do not have to know anything about containment sump level to correctly answer this question. Changed question from Containment Spray To Recirc Spray requirements which states that Recirc Spray pumps must be secured if Ctmt. Sump level is < 4.0 feet.
Subsets. If B is true, C is true. Ditto A and D. Need 23 F 2 X N U a limiter in the stem. Also restate stem as a requirement (must be secured). Added limiter to eliminate subset issue, and changed question to the minimum Containment sump level for operatin of the Recirc Spray pumps is ___. Kept distractor values the same.
SAT 24 F 2 N S Dont ask what shall be done. Ask what is required.
Changed question from what shall be to what 25 H 2 M E action is required to be taken SAT 26 F 2 N S
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only Give a range on the distractor temperature to match the structure of the correct answer. Do not diagnose in the stem (LBLOCA). Give the applicant the 27 F 2 N E observable indication necessary to answer the question. Gave range on distractors and changed indications to not diagnose in stem.
SAT Dont diagnose in stem (ATWS).
Give an initial power level.
The first two columns comprise four unique answers.
The second 2 columns add nothing.
Several minutes is too fuzzy. After some time, RCS pressure will either be controlled by safeties/PORVs, or else go offscale high. Either way, pressure will not E
28 H 2 M rise forever.
Does all feedwater . . .has been lost include AFW?
If not, specify. If so, I think this accident has not been analyzed. Re-wrote stem to give initial power as well as specify loss of MFW. Removed PZR Level and Steam Pressure columns. Changed several minutes to two (2) minutes.
SAT Dont ask what would happen. Ask about requirements. Changed stem to ask which of the listed RMs was required to be in service for fuel movement.
The version you sent me did not include this change.
29 F 2 N E Intended change was inadvertently not sent, desired change attached.
Stem should refer to required OPERABILITY of the rad monitor.
Added to be operable to stem.
SAT Is there a link between loading a spent fuel cask and an area rad alarm in the new fuel storage area?
Ensure this is operationally valid. The New fuel storage area and Spent fuel storage area are in same building and adjacent to each other. A fuel handling accident in the Fuel Building would affect both 30 H 2 X N E radiation monitors.
Also, it does not seem credible to me that a valid area rad alarm has no effect on fuel handling activities.
The distractor analysis refers to fuel assembly reconstitution, but the stem says that cask loading is in progress.
Revised question to ask the required MCR actions regarding ventilation lineup. Also revised distractor analysis to reflect cask load vice fuel reconstitution.
SAT Appears to be a K/A mismatch. What surveillance procedure is involved?
Changed question to require candidate to use 0-31 H 2 X N U OSP-RC-002 to calculate a primary-to-secondary leak rate. Now matches KA.
SAT Much window dressing. The question simply asks what devices reposition in response to a main steam isolation signal and what causes such a signal.
Everything above Which ONE seems to be 32 H 2 M E unnecessary.
Removed window dressing and changed wording as needed.
SAT How can the applicant determine that MTC is negative?
Added bullet stating that ramp plan calls for dilutions for duration of ramp, implying negative MTC.
Your comment does not describe what you actually did, but what you did is probably fine. If the value of MTC is normally available in the control room this 33 H 2 M S question is SAT. It MTC is not normally readily accessible, give a boron concentration indicative of late in core life.
MTC is not readily accessible in MCR, so changed bullet stating that RCS boron is 300 ppm. This should provide enough information to the candidates that MTC is negative.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only The distractor analysis says that if the turbine were in IMP IN, inward rod motion is credible. Wouldnt IMP IN aggravate the situation and make the cooldown worse? i.e. the turbine would respond to 34 H 2 X N E the drop in impulse pressure by taking more steam?
Removed reference to IMP IN and added explanation of Power Mismatch Circuit.
SAT 35 H 2 N S 36 H 2 M S Ensure that the name of the switch in the stem exactly matches plant labeling. i.e. if giveaway is not on the label, dont use it in the question.
37 H 2 N E Replaced giveaway with actual switch name (non-unit-specific).
SAT Lowering SG pressure by itself does not indicate Natural circulation is in progress. It would drop as a result of steaming and feeding even if loop isolation valves were closed. Perhaps consistent with is a more accurate phrase. Also, slowly lowering may be necessary (per procedure). If it rapidly lowers and Tcold doesnt follow it, this is an indication of a loss of NC.
38 H 2 B E Changed stem to replace indicates with is consistent with. Also changed stable or lowering to slowly lowering.
With this wording, I think B is also correct. Replace t with a distractor that is inconsistent with natural circulation.
Replaced distractor B with an indication that is NOT consistent with Natural Circulation; CETCs rising.
SAT 39 F 2 N S It is general employee knowledge to stop a radioactive leak if possible. This does not test licensed knowledge.
Also, is AUX BLDG SAMPLE Radiation Monitor 1-40 F 1 N U RM-156 an area monitor?
Perhaps require the applicant to identify a possible source for a given Area rad alarm?
Rewrote question to require applicant to identify likely source of a particular RM alarm.
SAT Send a reference that shows that median Tavg is used for feed isolation.
41 F 2 M S Added reference (0-AP-53.00, Attachment 4) showing Tave Control Circuit.
SAT 42 F 2 B S 43 H 2 M S 44 H 2 N S This does not test an EOP warning, caution, or note.
This question can be answered with system knowledge only.
Discussed with Chief - Surry doesnt have EOP 45 F 2 X N U actions for Loss of DC. Caution will come from 1-AP-10.06, Loss of DC Power. Chief agreed on phone call.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only Each possible answer contains a different component failure, 3 of which are wrong, so the why adds nothing. Simply ask which of these responses is a 46 F 2 B E direct result of the loss of the associated DC Power.
Removed the why component in the responses.
SAT K/A mismatch. This tests the effect of an EDG failure on fuel oil system, instead of the other way around.
Rewrote question to determine the effect on EDGs (Tech Spec) with the Aboveground Fuel Oil Storage Tank removed from service. Tested the candidates knowledge of the minimum on-site fuel oil required.
This version of the question makes most of the stem into window dressing. I believe that the minimum requirement is independent of the current status of tanks. I suggest you make this an evaluation of how 47 F 2 X B U the unavailability of the above ground tank affects EDG operability.
Removed the bullets pertaining to the Underground Fuel Oil Storage Tanks. Changed question to ask minimum fuel oil in UFOSTS per TS 3.16. Changed distractor D to 40,000 gal. to better match question.
Re-sequence answers from higher to lower or vice versa.
Re-sequenced answers from higher to lower.
SAT 48 H 2 N S Do not diagnose in stem (SBLOCA). K/A mismatch.
This is not guidance contained in EOP Rewrote question to use EOP guidance and removed SBLOCA from stem.
FR-Z.1 step 6 also directs closing MSTVs. Is the point to ask which one is first?
Changed stem bullet to indicate all other ESF equip 49 F 2 X N U responded as designed (other than MSTVs). This done to bolster question to support fact that FR-Z.1 is not required to be entered because both trains of CS operated. Changed P1 tostate which procedure will first close MSTVs Note: this may not be necessary if FR-Z.1 entry conditions are not met.
SAT Explain how this is a ventilation system.
Process Ventilation System takes suction of dilution 50 F 2 M E air in the Auxiliary Building near the Primary Sample Sink using Process Ventilation Blowers, discharging
through the lightning rods on top of containment.
Drawing attached.
SAT 51 F 2 M S 52 H 2 M S K/A mismatch. This question can be answered solely on system knowledge. Everything following Given the following is window dressing. The particular 53 H 2 N U condition of the plant is not relevant to the question.
Dont diagnose in stem (small LOCA).
Rewrote question to better match the KA.
SAT The question is confusing. It implies that the pump start location is dependent on screen speed. Is screen in fast an interlock or only a procedure 54 F 2 N E requirement?
Split question into 2 discrete parts to allay confusion.
SAT Dont diagnose in stem. Give indication the operator can see.
55 H 2 N E Revised stem to give operator indications rather than diagnosis.
SAT 56 F 2 N S 57 H 2 N S 58 H 2 N S
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only 59 H 2 N S 60 F 2 B S Dont diagnose in stem.
61 F 2 M E Revised stem.
SAT The 2 part does not discriminate. The applicant is nd told that a pressure change has a reactivity effect and then asks the applicant to determine that this is due to a pressure coefficient of reactivity. Also, I suspect 62 F 2 X N E that the pressure coefficient is due, at least in part, to voids from nucleate boiling.
Revised question to better differentiate what causes the reactivity change.
SAT 63 F 2 N S 64 F 2 M S 65 F 2 M S 66 F 2 N S 67 F 2 N S There is no apparent link to radiation control or radiological safety procedures.
68 F 2 N U Replaced question with a bank question from North Annas 2014 NRC exam.
SAT 69 F 2 N S 70 F 2 M S 71 F 2 N S Dont diagnose in stem.
72 H 2 N E Revised stem.
SAT Dont diagnose in stem.
73 H 2 N E Revised stem.
SAT 74 H 2 M S Dont diagnose in stem.
75 H 2 M E Revised Stem.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only 76 H 2 M S 77 H 2 N S 78 H 2 N S 79 H 2 N S 80 H 2 N S One tube rupture cause N-16 alarms on all SGs?
What is the reference for this?
In order to conclude from SG WR trends that the B SG is ruptured, it is necessary to know AFW flow rates and steaming rates.
Since our N-16 RMs are located very close to each 81 H 2 N E other (w/in ~ 5 feet), it is expected that a SGTR in one SG will cause all N-16 RMs to alarm due to shine. They are designed to detect very small leaks (0-200 gpd - equivalent to 0.14 gpm) that would otherwise not be seen. Revised stem to include feed/steam rates.
SAT 82 H 2 N S It does not seem operationally valid for PZR level and subcooling to be stable with an elevated containment pressure. What is the source of pressure in containment?
The distractor analysis for A says Plausible if candidate determines . . . based on PRZR level lowering. PRZR level is stable in the stem.
Clumsy wording in stem. The First procedure attempted to and Which procedure, will the team.
83 H 2 X N E Perhaps The first attempt to load EDG #1 is done in accordance with and remove the comma in the second part (after procedure).
Revised conditions and stem IAW NRC comments.
Provided more operationally-valid indications. CTMT pressure would be expected to be elevated due to loss of cooling.
Revised distractor analysis to refer to elevated CTMT pressure vice PZR level.
A complete loss of DC is possible at any time. Add to the first part in accordance with ECA 0.0. Giving the entire TRM to the applicant contains a risk of compromising another question. Ensure that no other question is affected by this reference.
Revised stem IAW NRC comments. Only one other question (#63) refers to the TRM, and then only to administrative requirements if a TRM item is determined to be inadequate. There is no compromise by giving the TRM as a reference.
Subset issues. If C is correct, A is correct (so I wouldnt pick C because I know there are not 2 84 H 2 N E correct answers). Ned a modifier in stem. Added modifier minimum to P1. Used a range of time which better matches ECA-0.0 Note.
This started as a TRM question, but in the present form, how is this SRO only? The form says it is procedure selection, but no procedure is selected. If this is unique to the SRO position in your training program. Attach the relevant learning objective.
Added Objective C for ND-88.1-LP-10, TRM Overview to Objective field and Part 55 content.
Added Figure1: Screening for SRO-only linked to 10CFR 55.43(b)(2), to Question Reference section.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only What does the note before the question mean?. It seems to me that adding the third bullet inappropriately tells the applicant that an emergency classification is necessary when that seemed to be the point of the question. Also, I thought the reference we were providing was the E-plan 85 H 2 N S classification document. The associated learning objective says utilizing the EAL charts.
Removed note and third bullet. The E-plan classification document is interchangeably referred to as the EAL Matrix or EAL Charts.
SAT The 5 minute delay does not seem operationally relevant. In the stated sequence, this 5 minutes would have elapsed. Also, explain how the loss of this bus is causing intake canal level to go down.
Revised to ask the reason for the 5-minute delay.
86 H 2 X N E The loss of 1G bus results in the loss of all Unit 1 CW pumps. With power restored, the crew would be expected to restart any previously running CW pumps.
SAT Dont diagnose in the stem. Why is RVLIS rising?
Revised stem to give indications that the operator 87 H 2 M E would have. Removed rising from RVLIS indication.
SAT Reference provided is contradicted by Reference provided to applicant: NO It seems that this would lead to E-plan activation, so 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is not a credible distractor.
The explanation says requires hospitalization but this information is not in the stem.
Changed No to Yes for reference provided.
Changed 4-hour report to 8-hour report as this is more plausible. VPAP-2802, section 6.3.5.b requires 88 H 2 S N E an 8-hour report to be made if an Alert/SAE/GE was declared. Actual report of the EAL is governed by EPIP-2.0.1/2.0.2, and not VPAP 2802. Changed the stem to include require hospitalization for their injuries.
SAT You must have changed you mind about someone needing hospitalization as part of the question.
Doesnt the low temperature in the pump house make 89 H 2 N E all ESW pumps inoperable which affects both units?
If so, that seems more operationally relevant than the battery inoperability.
Revised Part 1 to remove reference to ESW Pump batteries and just asked for ESW Pump status. Both units are affected, but TS allows two ESW pumps to be operable if one unit is in CSD with low SFP heat load. Unit 2 is on the way there, but not there yet.
SAT Why is circ/serv water temperature given in stem?
CW/SW temperature is a required variable to 90 H 2 M E determine Containment Allowable Air Partial Pressure IAW the TS figure.
SAT 91 F 2 N S 92 H 2 N S 93 H 2 N S Dont make it generic. Pick a particular example where this rule applies and use that as the premise of the question. It could be open reference for the LCO in question (but do not include the basis section that 94 H 2 X N E applies to specifically answer the question).
Made the question more specific, relating to a faulted electrical bus. Reference not required.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other
- 1. 2.
- 6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)
(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only The sentence that begins with Which ONE of the following is unnecessary and does not flow with the 95 H 2 N E following statements.
Removed the unnecessary statement.
SAT 96 H 2 N S 97 H 2 N S Inappropriate references to FR-H.1. (technical references, distractor analysis). Is the operator expected to determine that pressure/temperature conditions are to the right of limit A from memory?
On other questions that allow references, there was a note that said references provided. I did not see that here.
This is not SRO only because of procedure selection, 98 H 2 M E but because of the classification. Red path entry is RO knowledge.
Removed references to FR-H.1. Yes, the operator is expected to know the conditions that would place him/her to the right of Limit A. Removed reference since a picture of the screen is provided in the body of the question. Removed reference to procedure selection as basis for SRO-only.
SAT Dont ask what the SRO will do. Ask what is required.
99 H 2 M E Revised stem to incorporate NRC comments.
SAT Priority is fuzzy when use of yellow path procedures is optional. Ask about the terminus of the heat sink status tree.
Dont ask about expected team actions. Ask what the procedure referenced in the above terminus would direct.
You clearly changed the question but I think you 100 H 2 M E comments got lost here.
The 2nd part of the C distractor is not credible the way it is written. Perhaps you meant to use the PORV to steam the level down. Perhaps say to reduce inventory.
Added reduce inventory to C2.
ES-403 Written Examination Grading Form ES-403-1 Quality Checklist t/19 10/to) X Facility: 5URfi-1 Date of Exam: Exam Level: RO SRO Item Description Initials a b c
- 1. Clean answer sheets copied before grading
- 2. Answer key changes and question deletions justified and /
documented I
- 3. Applicants scores checked for addition errors (reviewers spot check > 25% of examinations) u
- 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 j I t\
- 6. Performance on missed questions checked for training /
deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Date Printed Name/Signature
- a. Grader Swctha Shah t0(O.&!20I
- b. Facility Reviewer(*) N/A 1 ;/I,
(*) (ary \\* (IllI1l)
- c. NRC Chief Examiner
- d. NRC Supervisor () tL o
fr
(*) The facility reviewers signature is not applicable for examinations graded by the NRC:
two independent NRC reviews are required.
ES-403, Page 6 of 6
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 6, 2016 Catherine Haney, Regional Administrator Serial No.16-143 United States Nuclear Regulatory Commission Region II SS&LITSC Marquis One Tower Docket Nos. 50-280 245 Peachtree Center Ave., NE, Suite 1200 50-281 Atlanta, Georgia 30303-1257 License Nos. DPR-32 DPR-37
Dear Ms. Haney,
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 SUBMITTAL OF OPERATING TEST OUTLINES AND SUPPORTING REFERENCE MATERIALS NRC letter dated March 24, 2016, Notification of License Operator Initial Examination Surry
-
Power Station, requested transmittal of the operating test outlines, and reference materials by May 3, 2016. The written examination will be due by May 16, 2016, and the operating test will be due by June 21, 2016. The timely submittal will support the initial reactor operator and senior reactor operator examinations scheduled for the weeks of September 19 and September 26, 2016.
This letter is to inform you that the initial license operating test outlines and Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-DI, ES-401-2, ES-401-3 and ES-401-4 were transmitted to Mr. Gary Callaway, NRC Chief Examiner, on May 2, 2016 and received on May 3, 2016. We request that the materials submitted to the NRC be withheld from public disclosure until after the operator examinations have been administered.
If you have any questions or require additional information, please contact Mr. Paul Orrison or Mike Meyer at (757) 365-2835.
Very truly yours, N. L. Lane Site Vice President Surry Power Station Commitments: None
Serial No.16-143 Docket Nos. 50-280/50-281 copy: Mr. Gerald J. McCoy Chief, Operations Branch United States Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555-0001 Senior Resident Inspector Surry Power Station
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINJA 23261 May 25, 2016 Catherine Haney, Regional Administrator Serial No. 16-143A United States Nuclear Regulatory Commission Region II SS&L!TSC Marquis One Tower Docket Nos. 50-280 245 Peachtree Center Ave., NE, Suite 1200 50-281 Atlanta, Georgia 30303-1257 License Nos, DPR-32 DPR-37
Dear Ms. Haney,
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 SUBMITTAL OF WRITTEN EXAMINATION NRC letter dated March 24, 2016, Surry Power Station Notification of Licensed Operator Initial
-
Examination, requested transmittal of the written examination to support the initial reactor operator and senior reactor operator tests scheduled for the weeks of September 19 and September 26, 2016. This letter is to inform you that the written examination was transmitted on May 16, 2016 and received by Mr. Gary Callaway, NRC Chief Examiner, on May 17, 2016.
We request that the materials submitted to the NRC be withheld from public disclosure until after the operator examinations have been administered.
If you have any questions or require additional information, please contact Mr. Paul Orrison or Mr. Mike Meyer at (757) 365-2835.
Sincerely, N. L. Lane Site Vice President Surry Power Station Commitments made by this letter: None
Serial No. 16-143A Submittal of Written Examination Docket Nos. 50-280/50-281 Page 2 of 2 cc: Mr. Gerald J. McCoy Chief, Operations Branch United States Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1 257 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555-0001 Senior Resident Inspector Surry Power Station