ML092940740
| ML092940740 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/20/2009 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| 50-413/08-301, 50-414/08-301 | |
| Download: ML092940740 (83) | |
Text
{{#Wiki_filter:ES-201 Examination Preparation Checklist Form ES-201-1 Facility: C~Jffi,* Date of Examination: 121117D(~ Developed by: Written - Facility lXl NRcD II Facili~)tl Operating - Facility)in NRcD Target Chief Date* Task Description (Reference) Examiner's 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) 8/}
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-120 3. Facility contact briefed on security and other requirements (C.2.c) Blh elk
-120 4. Corporate notification letter sent (C.2.d) q'/"7, q'l'7,
[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 3)] 79/Z j.o. 179/Z j-"- F- {-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d) r/17 {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)} C;!22- {-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 any Form 10/17 ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d)
-30 9. Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.g; ES-202) /0/3/
-14 10. Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; ES-202) If/I 7
-14 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) 11//7
-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) II/;7
-7 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h) I#/Z1
-7 14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)
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-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k) /1/ zi
-7 16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i) (f/~f
- 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, Page 25 of 28
ES-201, Rev. 9 Examination Security Agreement Form ES-201-3 1.Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of l:Jec ..laof as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised. 2.Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of"b-e<:. *=08:. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. PRINTED NAMEJOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE
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- ES-201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes) of !I...O/.O¥' as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes) of . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
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ES-201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of bE.C. Z~ of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-Examination To the best of my knowledge, I ~d not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Pe(:.Ze4::) . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE i.Ar:-"'~/
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ES-201, Page 26 of 27
ES-201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of (2., (lb<t as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 0 .. /-0 '" . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
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Dameron, Hubert C From: Lyall, Kevin S Sent: Wednesday, February 04, 2009 11:48 AM To: Dameron, Hubert C; Wilkins, Teresa A
Subject:
Re: HLP exam security I attest that I did not divulge any exam material to anyone and that the statements below are true. I turned my badge back into Sam Brooks when I left. Kevin Kevin From: Dameron, Hubert C To: Lyall, Kevin S; Wilkins, Teresa A Sent: Wed Feb 04 10:53:14 2009
Subject:
HLP exam security Both of you signed the exam security agreement for the 08 HLP exam. I need both of you to sign back out. While it's best for you to physically sign out of the document I can deal with via e-mail. When you sign out you attest to the follOWing: To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Dec. 2008. From the date that I entered into this security agreement until the completion ofthe examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC. A reply to this email stating that you attest that the statement is correct is sufficient. Please mail the badge to me at CN01A. 1
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
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Date of Examination: l'Llod t:)~ Initials Item Task Description a b* cft-1. w
- a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. ~~ I~
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- b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KIA categories are appropriately sampled. ~ ~~ J
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{Yf)..; T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. cPt ~ar{)#"' ~ E
~S 'J~k N d. Assess whether the justifications for deselected or rejected KIA statements are appropriate. be'"
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- 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, j6 ~{
S and major transients. I M b. Assess whether there are enough scenario sets (and spares) to test the projected number U L A and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated cb ~( J T from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. dt? \J~ ;f 4f 0
- c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R
and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
- 3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1 ) the outline(s) contain(s) the required number of control room and in-plant tasks W 1 T 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 (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 JJr
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on the form. I
- 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 <¥1 ~, " " (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. dV1 ~( 1# ; II 1--
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- 4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered y G
in the appropriate exam sections. ~ ~ E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. ~ I~ bW ~ It¥' -*;A-A ()n N E
- c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. M I¥? W ,..VI R
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- d. Check for duplication and overlap among exam sections. d0 I{\",
1d0 (\'" ~ :..- L e. Check the entire exam for balance of coverage. dV1 I~ 1dJ-lt ~ J r;1\ tv
- f. Assess whether the exam fits the appropriate job level (RO or SRO). cPt W I~ ~~
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- c. NRC Chief Examiner (#) GE:epr~C) LLl, lAsOl hL11le-1' GE:(Z.pf<f..) hL:t1\.e)! W:-=-
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- d. NRC Supervisor MAuow.....
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n Note: # Independent NRC reviewer initial items in Column "c ; chief examiner concurrence required.
- Not applicable for NRC-prepared examination outlines
ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ~RO DSRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R N USing Data Book Figure 9 (Pennissible Successive Attempts to Start Motors) detennine the allowed starting time for NCP. Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjA/6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Calculate Unit Vent flow manually per PTjljAj4450j017 (Unit Vent Flow Manual Calculation). Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Umits Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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, Rev. 9 . Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO ~SRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations RM Determine if a work hours extension is required and if so, which limits are exceeded. Conduct of Operations RM Perform a manual shutdown margin calculation (Unit at Power) per OPjOj Aj6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control SM Determine SLC requirements and complete a Unit Vent Flow Manual Calculation per PTjljAj4450j017 Radiation Protection RM Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Umits Emergency Plan RD Upgrade an Emergency Classification and Complete an Emergency Notification Form NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ~RO o SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function
- a. Perform a Manual Makeup to the vcr (SNAP 191) D S 1
- b. Respond to NC System Leakage (SNAP 192) ADS 2
- c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D L S 3 a SGTR (SNAP 193)
- d. Cooldown the PRT Using NCDT Heat Exchanger (SNAP 194) D S 5
- e. Restore Offsite Power to 6.9 kV Busses per AP/07 (Loss of Normal Power) A L N S 6 Enclosure 21 (Black Restart Procedure) (SNAP 195)
- f. Perform the Immediate Actions of AP/1/N5500/16, (Malfunction of Nuclear D S 7 Instrumentation System), Case 4, (P/R Malfunction) (SNAP 196)
- g. Shirt Operating RC Pumps (SNAP 197) A N S 8
- h. Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198)
In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Locally Break Vacuum on a Loss of Feedwater D E 4S
- j. Align Seal Injection to the Unit 2 NC Pumps D E 2
- k. Alternate Cooling to 1A NV Pump D E R 8
@ Ali RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; ali 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room
- Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (O)irect from bank .:5.9/.:5.8/.:5.4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - 1 - 1 ~ 1 (control room system)
(L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams .:5. 3 1 .:5. 3 I .:5. 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator
ES-301, Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO ~ SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System j JPM Title Type Code* Safety Function a.
- b. Respond to NC System Leakage (SNAP 192) ADS 2
- c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D L S 3 a SGTR (SNAP 193)
- d. Cooldown the PRT Using NCDT Heat Exchanger (SNAP 194) D S 5
- e. Restore Offsite Power to 6.9 kV Busses per APj07 (Loss of Normal Power) A L N S 6 Enclosure 21 (Black Restart Procedure) (SNAP 195)
- f. Perform the Immediate Actions of APj1jAj5500j16, (Malfunction of Nuclear D S 7 Instrumentation System), case 4, (PjR Malfunction) (SNAP 196)
- g. Shirt Operating RC Pumps (SNAP 197) A N S 8
- h. Perform the Immediate Actions of APj1jAj5500j004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198)
In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Locally Break Vacuum on a Loss of Feedwater D E 4S
- j. Align Seal Injection to the Unit 2 NC Pumps D E 2
- k. Altemate Cooling to 1A NV Pump D E R 8
@ All RO and SRO-I control room (and in-plant) systems must be different and selVe different safety functions; all 5 SRO-U systems must selVe 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 (A)ltemate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank ~9/~8/~4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - / - / ~ 1 (control room system)
(L)ow-Power / Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams ~ 3 / ~ 3 / ~ 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator
ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level: ORO o SRO-I ~ SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function a. b. c. d.
- e. Restore Offsite Power to 6.9 kV Busses per AP/07 (Loss of Normal Power) A L N S 6 Enclosure 21 (Black Restart Procedure) (SNAP 195) f.
- g. Shirt Operating RC Pumps (SNAP 197) A N S 8
- h. Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) (SNAP 198)
In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i.
- j. Align Seal Injection to the Unit 2 NC Pumps D E 2
- k. Alternate Cooling to 1A NV Pump D E R 8
@ 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 I SRO-II SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank .::.9/.::.8/.::.4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - 1 - 1 ~ 1 (control room system)
(L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/~2/~1 (P)revious 2 exams .::. 3 1 .::. 3 1 .::. 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator
ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: CA-""fAl.c) C,pc-"'tAl.cJi5A i5A odo IZ,( 0,[0 f Date of Examination: IZ,{ Operating Test Number: Operatinq 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). ()..Lj ~¥' A I
~
- b. There is no day-to-day repetition between this and other operating tests to be administered during this examination. ~ bl r ,.
- c. The operating test shall not duplicate items from the applicants' audit test(s). (see Section D.1.a.) ~ ~~
~i ,f
- d. Overlap with the written examination and between different parts of the operating test is within ~
acceptable limits. ~
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated desiqnated license level. ~ tJ>i J~'I~
- 2. Walk-Through Criteria - -- --
- a. Each JPM includes the following, as applicable:
(JJ initial conditions initiating cues
- references and tools, including associated procedures Jj
- 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 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
~
J l~
~~
¥ 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 I on those forms and Form ES-201-2.
- 3. Simulator Criteria -- -
The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached. tJJJ .\J~ ~ Printed Nam.i~ignature Printed Nai<s~nature Date
- a. Author ddOl +rv rL S o,frv Suu 1I1l:;\)r / ~ .j..A.A.- -
-- It !J,;
f,tf/of LoY
- b. Facility Reviewer(*) I0LII{t0 /'-'l//leW:!/ (J-/4?*~-'
/0Lllft0 D. ~/I;e(j/fJ-f~/--/ Lf (f II?
II ~ii)t" jut"
- c. NRC Chief Examiner (#) ~t;fM.'1J) hi,
£t;M-'lJ) It-\S\~VLY~.fi
(,J, It-Y>'vkH vVLJ4! /,,'.£.'
~l'( /;IF!!
IIZF1/
, t~'if8 C?1-¥t8
- d. NRC Supervisor 1JAW.ow -r: W~ /1Cliut:rffw:r--- r/~/v~
f llY Y NOTE:
- The facility signature is not applicable for NRC-developed tests.
# Independent NRC reviewer initial items in Column "cn; chief examiner concurrence required.
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: ~AVJ("3A Date of Exam:l2lDII~~enario Numbers: 'ZI 11'l Operating Test No.: QUALITATIVE ATTRIBUTES Initials a b* c#
- 1. The initial conditions are realistic, in that some equipment andlor instrumentation may be out of service, but it does not cue the operators into expected events. (jt/l ~~ g
- 2. The scenarios consist mostly of related events. .{JJf IJI{ I~
'{':Jif" 1:\
~
- 3. Each event description consists of
- the point in the scenario when it is to be initiated dt-7
~f t
- the malfunction(s) that are entered to initiate the event I~f
- the symptomslcues that will be visible to the crew
- the expected operator actions (by shift position)
- 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. ~ tJ(' (J
- 5. The events are valid with regard to physics and thermodynamics. d0 1\1~
\1~ , \
- 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives. lfJJ. ~~
tJ~ 'f
'f v
- 7. If time compression techniques are used, the scenario summary clearly so indicates.
J1~ ~~ J10 Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. R f
- 8. The simulator modeling is not altered. M ~ ~ Y
- 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.
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- 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. (, dJ1 ~ T(
- 11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios). \jif
- 12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios). ~ ~~( 0
)
- 13. The level of difficulty is appropriate to support licensing decisions for each crew position. (JJ W M t¥ (f Target Quantitative Attributes (Per Scenario; See Section D.5.d) 'i~~~~u~l* , -- -- TJ
- 1. Total malfunctions (5-8) 715/7 PI bP-' Ie IbP-' (
-1
- 2. Malfunctions after EOP entry (1-2) 5 12-/~ tJij tJti lb~
b~ trn lin
- 3. Abnormal events (2-4) G, I ..., I & {JA..
'IP.. I~~
t-..~ cf: CF--
- 4. Major transients (1-2) Z I (/2 ~ I~~
cf1.-v ~~ rr rI-'
- 5. EOPs enteredlrequiring substantive actions (1-2) 2. I Z I If ~ ~ J
- 6. EOP contingencies requiring substantive actions (0-2) 2- lOla M \:)~ ~
- 7. Critical tasks (2-3) '2.- 12. I Z- ~ ~~ 1~
ES-301 Transient and Event Checklist Form ES-301-5 Facility: CATAWBA NUCLEAR STATION Date of Exam: 12/01/2008 Operating Test No.: A E Scenarios P V 1 2 3 4 T M P E 0 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 0 R T 0 R T 0 R T 0 M(*) N Y 0 C P 0 C P 0 C P 0 C P R I U T P E RO RX 1 4 1 1/2 1 1 0 ~ NOR 2 0/1 1 1 1 SRO-I I/C 46 235 16 235 35 46 126 345 4/5 4 4 2 0 SRO-U MAJ 7 7 7 7 7 7 7 7 2 2 2 1 0 TS 0 2 2 RX 1 4 1 1/2 1 1 0 RO 0 NOR 2 0/1 1 1 1 SRO-I I/C 23456 12356 3456 12345 4/5 4 4 2 0 6 SRO-U MAJ 7 7 7 7 2 2 2 1 ~ TS 356 123 46 34 4-6 0 2 2 RO RX 1 1 4 4 1 1 1/2 1 1 0 0 NOR 2 0/1 1 1 1 SRO-I I/C 23456 46 12356 16 3456 35 12345 126 4/5 4 4 2 ~ 6 SRO-U 0 MAJ 7 7 7 7 7 7 7 7 2 2 2 1 TS 356 123 46 34 2/3 0 2 2 RO RX 1 1 0 0 NOR 1 1 1 SRO-I IIC 4 4 2 0 SRO-U MAJ 2 2 1 0 TS 0 2 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 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 Instant SRO additionally serves in the BOP position, one IIC 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 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
ES-301, Rev. 9 Competencies Checklist Form ES-301-6 Facility: Catawba Nuclear Station Date of Examination: 12/01/2008 Operating Test No.: APPLICANTS RO BOP SRO-U/I N/A Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 467 146 357 126 235 235 467 345 2-7 1-7 3-7 1-7 and Conditions 7 7 7 7 7 Comply With and 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 Use Procedures (1) 7 7 7 7 7 7 7 7 Operate Control 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 Boards (2) 7 7 7 7 7 7 7 7 Communicate 146 146 135 126 235 235 246 345 1-7 1-7 1-7 1-7 and Interact 7 7 7 7 7 7 7 7 Demonstrate Supervisory n/a n/a n/a n/a n/a n/a n/a n/a 1-7 1-7 1-7 1-7 Ability (3) Comply With and n/a n/a n/a n/a n/a n/a n/a n/a 356 123 46 34 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 IbCA\~M Date of Exam: ,z.I \o, Exam:'z.lOtOt \ 0' RO Exam Level: RO[2( [2( <:Rn SRoD n Initial G~ Item Description a b*
- 1. Questions and answers are technically accurate and applicable to the facility. ~ b~ Jt V
- 2. a.
b. NRC KlAs are referenced for all questions. Facility learning objectives are referenced as available. l-' ~~ ~l
- 3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 ~?-' ~\tg v
- 4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office). I J
- 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 r--- l _ the audit exam was completed before the license exam was started; or
~e
_ tJJe examinations were developed independently; or
-0hehe licensee certifies that there is no duplication; or
_ other (explain) ~~ btf ~\
- 6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest
~
new or modified); enter the actual RO / SRO-only question distribution(s) distribution(s} at right.
'6/- 9/- 9 / - yg/-
7. 8. Between 50 and 60 percent of the questions on the RO exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected KlAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s} distribution(s) at right. References/handouts provided do not give away answers or aid in the elimination of distractors. 35' Memory 35""'// - - CIA
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~~
I-" b~ ~-,
~
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~
- 9. Question content conforms with specific KIA statements in the previously approved t""'"
examination outline and is appropriate for the tier to which they are assigned; deviations are justified. Wrt'
- 10. Question psychometric quality and format meet the guidelines in ES Appendix B. r ~~ Mk
~ tJ~ /~
- 11. The exam contains the required number of one-point, multiple choice items; ; 1\-
the total is correct and agrees with the value on the cover sheet.
'-.J Si~ature Printed Name / 7cature Date
- a. Author Jo~ IL.SulraA IL.~rQA ~(}}.hAf-
/o,AhAJ- {tt/or an{diar
/L. l/;J. J!;;. ') .J.J
=.~
- b. Facility Reviewer (*) B{(!.IA-v 1l. A '{fer ---2l './h--
- c. NRC Chief Examiner (#) .~ c((A '1.,1) \,.) U\5 f4{ A-A1P/'V'--f({..'~.d"'f-;
- d. NRC Regional Supervisor J/~IIN~l JIIJII'N-lL'/. \JJlhLlA-AIA.I / 7l\
(. 'W/bIliANAU /7\ I "'"' (~ht1//tg
~~
Note:
- The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
n
# Independent NRC reviewer initial items in Column "c chief examiner concurrence required.
f)}JAL-2008 RO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description EPE007 EK2.03 Reactor Trip T/G 1 /1 RO 3.5 SRO 3.6 1 507 Knowledge of the interrelations between a reactor trip Reactor trip status panel and the following: (CFR 41.7/45.7) EPE009 EA2.10 Small Break LOCA T/G 1 / 1 RO 3.1 SRO 3.7 2 508 Ability to determine or interpret the following as they apply Airborne activity ............................................... .. to a small break LOCA: (CFR 43.5/45.13) EPE011 2.4.30 Large Break LOCA T/G 1 / 1 RO 2.7 SRO 4.1 3 509 EPE011 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 143.5 145.11 ) APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1 / 1 RO 2.7 SRO 3.1 4 510 Knowledge of the operational implications of the following Relationship of charging flow to pressure differential between charging and concepts as they apply to Loss of Reactor Coolant RCS ................................ . Makeup: (CFR 41.8/41.10 145.3) APE025 2.4.30 Loss of Residual Heat Removal System (RHRS) T/G 1 / 1 RO 2.7 SRO 4.1 5 511 APE025 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE026 AA2.03 Loss of Component Cooling Water (CCW) T/G 1 / 1 RO 2.6 SRO 2.9 6 512 Ability to determine and interpret the following as they The valve lineups necessary to restart the CCWS while bypassing the portion apply to the Loss of Component Cooling Water: (CFR: of the system causing the abnormal condition ................ .. 43.5/45.13) APE027 AA1.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 /1 RO 3.9* SRO 3.6* 7 513 Ability to operate and 1 or monitor the following as they Pressure recovery, using emergency-only heaters .................... . apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 145.5/45.6) Page 1 of 12
2008 RO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description EPE029 2.4.34 Anticipated Transient Without Scram (ATWS) T/G 1 / 1 RO 4.2 SRO 4.1 8 514 EPE029 GENERIC Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13) EPE038 EK1.02 Steam Generator Tube Rupture (SGTR) T/G 1 / 1 RO 3.2 SRO 3.5 9 515 Knowledge of the operational implications of the following Leak rate vs. pressure drop ....................................... . concepts as they apply to the SGTR: (CFR 41.8 / 41.10 / 45.3) APE057 AA2.13 Loss of Vital AC Electrical Instrument Bus T/G 1 / 1 RO 3.0 SRO 3.4 10 516 Ability to determine and interpret the following as they VCT level and pressure indicators and recorders ..................... . apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5/ 45.13) APE058 AA1.02 Loss of DC Power T/G 1/1 RO 3.1* SRO 3.1 11 517 Ability to operate and / or monitor the following as they Static inverter dc input breaker, frequency meter, ac output breaker, and apply to the Loss of DC Power: (CFR 41.7/45.5/45.6) ground fault detector ............................ . APE062 AK3.03 Loss of Nuclear Service Water T/G 1 / 1 RO 4.0 SRO 4.2 12 518 Knowledge of the reasons for the following responses as Guidance actions contained in EOP for Loss of nuclear service water .... they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 /45.7) APE065 AK3.03 Loss of Instrument Air T/G 1 / 1 RO 2.9 SRO 3.4 13 519 Knowledge of the reasons for the following responses as Knowing effects on plant operation of isolating certain equipment from they apply to the Loss of Instrument Air: (CFR 41.5,41.10 instrument air .................................... .
/45.6/45.13)
Page 2 of 12
2008 RO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KiA Number KiA System Tier/Group Importance RO/SRO KiA Description APE077 AA1.01 Generator Voltage and Electric Grid Disturbances T/G 110 RO 3.6 SRO 3.7 14 520 Ability to operate and/or monitor the following as they Grid frequency and voltage ........................................................ . apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10 145.5,45.7, and 45.8 ) WE04 EK2.2 LOCA Outside Containment T/G 1 1 1 RO 3.8 SRO 4.0 15 521 Knowledge of the interrelations between the (LOCA Facility*s heat removal systems, including primary coolant, emergency coolant, Outside the decay heat removal systems, and relations between the proper operation Containment) and the following: of these systems to the operation of the facility. (CFR: 41.7/45.7) WE05 EK3.1 Loss of Secondary Heat Sink T/G 1 1 1 RO 3.4 SRO 3.8 16 522 Knowledge of the reasons for the following responses as Facility operating characteristics during transient conditions, includingDcoolant they apply to the (Loss of Secondary Heat Sink) chemistry and the effects of temperature, pressure, and reactivity changes and (CFR: 41.5/41.10, 45.6,45.13) operating limitations and reasons for these operating characteristics. WE11 EK2.1 Loss of Emergency Coolant Recirculation T/G 1 1 1 RO 3.6 SRO 3.9 17 523 Knowledge of the interrelations between the (Loss of Components, and functions of control and safety systems, including Emergency instrumentation, signals, interlocks, failure modes, and automatic and manual Coolant Recirculation) and the following: features. (CFR: 41.7/45.7) WE12 EK1.3 Uncontrolled Depressurization of all Steam Generators T/G 1 1 1 RO 3.4 SRO 3.7 18 524 Knowledge of the operational implications of the following Annunciators and conditions indicating signals, and remedial actions concepts as they apply to the (Uncontrolled associated with the (Uncontrolled Depressurization of all Steam Generators). Depressurization of all Steam Generators) (CFR: 41.8/41.10/45.3) APE001 AA1.06 Continuous Rod Withdrawal T/G 1 12 RO 3.0* SRO 2.9* 19 525 Ability to operate and 1 or monitor the following as they Rod transfer switches ............................................ . apply to the Continuous Rod Withdrawal: (CFR 41.71 45.5/45.6) Page 3 of 12
2008 RO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description APE005 2.4.6 Inoperable/Stuck Control Rod T/G 1 12 RO 3.7 SRO 4.7 20 526 APE005 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) APE024 AK1.04 Emergency Boration T/G 1 12 RO 2.8 SRO 3.6 21 527 Knowledge of the operational implications of the following Low temperature limits for born concentration ................... . concepts as they apply to Emergency Boration: (CFR 41.8/41.10/45.3) APE033 AK1.01 Loss of Intermediate Range Nuclear Instrumentation T/G 1 12 RO 2.7 SRO 3.0 22 528 Knowledge of the operational implications of the following Effects of voltage changes on performance .......................... . concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: CFR 41.8 1 41.10 1 45.3) APE037 AA2.03 Steam Generator (S/G) Tube Leak T/G 1 12 RO 3.4 SRO 3.9 23 529 Ability to determine and interpret the following as they That the expected indication on main steam lines from the S/Gs should show apply to the Steam Generator Tube Leak: (CFR: 43.5 1 increasing radiation levels ..................... . 45.13) EPE074 EA1.01 Inadequate Core Cooling T/G 1 12 RO 4.2 SRO 4.4 24 530 Ability to operate and monitor the following as they apply RCS water inventory ............................................. . to a Inadequate Core Cooling: (CFR 41.7/45.5/45.6) APE036 AK3.03 Fuel Handling Incidents T/G 1 12 RO 3.7 SRO 4.1 25 531 Knowledge of the reasons for the following responses as Guidance contained in EOP for fuel handling inciqent ................. . they apply to the Fuel Handling Incidents: (CFR 41.5,41.10/45.6/45.13) WE03 EK2.1 LOCA Cooldown and Depressurization T/G 1 12 RO 3.6 SRO 4.0 26 532 Knowledge of the interrelations between the (LOCA Components, and functions of control and safety systems, including Cooldown and instrumentation, signals, interlocks, failure modes, and automatic and manual Depressurization) and the following: features. (CFR: 41.7/45.7) Page 4 of 12
2008 RO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System TierlGroup Importance RO/SRO KIA Description WE09 EK3.3 Natural Circulation Operations T/G 1 12 RO 3.5 SRO 3.6 27 533 Knowledge of the reasons for the following responses as Manipulation of controls required to obtain desired operating results during they apply to the (Natural Circulation Operations) abnormal, and emergency situations. (CFR: 41.5/41.10, 45.6,45.13) SYS003 A2.02 Reactor Coolant Pump System (RCPS) T/G 2 I 1 RO 3.7 SRO 3.9 28 534 Ability to (a) predict the impacts of the following Conditions which exist for an abnormal shutdown of an RCP in comparison to malfunctions or operations on the RCPS; and (b) based a normal shutdown of an RCP .................. . on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) SYS004 A1.01 Chemical and Volume Control System T/G 2 I 1 RO 2.9 SRO 3.8 29 535 Ability to predict andlor monitor changes in parameters Activity levels in primary system (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5/45.5) SYS004 K1.34 Chemical and Volume Control System T/G 2 I 1 RO 2.7 SRO 2.9 30 536 Knowledge of the physical connections andlor cause- Interface between CVCS and reactor coolant drain tank; and PZR PCS .... effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9/45.7 to 45.8) SYS005 K4.11 Residual Heat Removal System (RHRS) T/G 2 I 1 RO 3.5* SRO 3.9* 31 537 Knowledge of RHRS design feature(s) andlor interlock(s) Lineup for low head recirculation mode (external and internal) which provide or the following: (CFR: 41.7) SYS006 A1.05 Emergency Core Cooling System (ECCS) T/G 2 I 1 RO 2.9 SRO 3.3 32 538 Ability to predict andlor monitor changes in parameters CCW flow (establish flow to RHR heat exchanger prior to placing in service (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5/45.5) Page 5 of 12
2008 RO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS007 2.4.6 Pressurizer Relief Tank/Quench Tank System (PRTS) T/G 2 1 1 RO 3.7 SRO 4.7 33 539 SYS007 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) SYSOOB K3.03 Component Cooling Water System (CCWS) T/G 2 1 1 RO 4.1 SRO 4.2 34 540 Knowledge of the effect that a loss or malfunction of the RCP .......................................................... . CCWS will have on the following: SYSOOB K4.09 Component Cooling Water System (CCWS) T/G 2 11 RO 2.7 SRO 2.9 35 541 Knowledge of CCWS design feature(s) and/or interlock(s) The "standby" feature for the CCW pumps ........................... . which provide for the following: (CFR: 41.7) SYS010 2.1.25 Pressurizer Pressure Control System (PZR PCS) T/G 2 1 1 RO 3.9 SRO 4.2 36 542 SYS010 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) SYS012 A2.02 Reactor Protection System (RPS) T/G 2 1 1 RO 3.6 SRO 3.9 37 543 Ability to (a) predict the impacts of the following Loss of instrument power ........................................ . malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 1 43.5 1 45.3 145.5) SYS012 K5.01 Reactor Protection System (RPS) T/G 211 RO 3.3* SRO 3.B 38 544 Knowledge of the operational implications of the following DNB .......................................................... . concepts as the apply to the RPS: (CFR: 41.5/45.7) SYS013 K6.01 Engineered Safety Features Actuation System (ESFAS) T/G 2/1 RO 2.7* SRO 3.1* 39 545 Knowledge of the effect of a loss or malfunction on the Sensors and detectors ........................................... . following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8) Page 6 of 12
2008 RO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS022 K2.02 Containment Cooling System (CCS) T/G 211 RO 2.5* SRO 2.4* 40 546 Knowledge of power supplies to the following: (CFR: Chillers 41.7) SYS025 A4.01 Ice Condenser System T/G 2 11 RO 3.0* SRO 2.7* 41 547 Ability to manually operate and/or monitor in the control Ice condenser isolation valves .................................... .. room: (CFR: 41.7 /45.5 to 45.8) SYS026 A1.03 Containment Spray System (CSS) T/G 2 I 1 RO 3.5 SRO 3.5 42 548 Ability to predict and/or monitor changes in parameters Containment sump level .......................................... . (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5/45.5) SYS026 K1.01 Containment Spray System (CSS) T/G 2 I 1 RO 4.2 SRO 4.2 43 549 Knowledge of the physical connections and/or cause- ECCS ......................................................... . effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) SYS039 K5.01 Main and Reheat Steam System (MRSS) T/G 2 11 RO 2.9 SRO 3.1 44 550 Knowledge of the operational implications of the following Definition and causes of steam/water hammer ....................... . concepts as the apply to the MRSS: (CFR: 441.5/45.7) SYS059 A4.11 Main Feedwater (MFW) System T/G 2 11 RO 3.1 SRO 3.3 45 551 Ability to manually operate and monitor in the control Recovery from automatic feedwater isolation ....................... . room: (CFR: 41.7/45.5 to 45.8) SYS061 A3.03 Auxiliary I Emergency Feedwater (AFW) System T/G 2 I 1 RO 3.9 SRO 3.9 46 552 Ability to monitor automatic operation of the AFW, AFW S/G level control on automatic start ........................... . including: (CFR: 41.7/45.5) Page 7 of 12
2008 RO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KJA Number KJA System Tier/Group Importance RO/SRO KJA Description SYSOS2 A3.01 AC Electrical Distribution System T/G 2 / 1 RO 3.0 SRO 3.1 47 553 Ability to monitor automatic operation of the ac Vital ac bus amperage ............................................ . distribution system, including: (CFR: 41.7/45.5) SYSOS3 K2.01 DC Electrical Distribution System T/G 2/1 RO 2.9* SRO 3.1* 48 554 Knowledge of bus power supplies to the following: (CFR: Major DC loads 41.7) SYSOS3 K3.01 DC Electrical Distribution System T/G 2 / 1 RO 3.7* SRO 4.1 49 555 Knowledge of the effect that a loss or malfunction of the ED/G DC electrical system will have on the following: (CFR: 41.7/45.6) SYSOS4 A3.07 Emergency Diesel Generator (ED/G) System T/G 2/1 RO 3.S* SRO 3.7* 50 556 Ability to monitor automatic operation of the ED/G Load sequencing ................................................ . system, including: (CFR: 41.7/45.5) SYSOS4 KS.07 Emergency Diesel Generator (ED/G) System T/G 2 / 1 RO 2.7 SRO 2.9 51 557 Knowledge of the effect of a loss or malfunction of the Air receivers ................................................... . following will have on the ED/G system: (CFR: 41.71 45.7) SYS073 A2.02 Process Radiation Monitoring (PRM) System T/G 2 / 1 RO 2.7 SRO 3.2 52 558 Ability to (a) predict the impacts of the following Detector failure ............................................... .. malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor- rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 41.5/43.5 145.3 1 45.13) Page 8 of 12
2008 RO NRC Examination ES401, Rev 9 Combined PWR Written EXamination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS076 K2.01 Service Water System (SWS) T/G 2/1 RO 2.7* SRO 2.7 53 559 Knowledge of bus power supplies to the following: (CFR: Service water ................................................... . 41.7) SYS078 K3.02 Instrument Air System (lAS) T/G 2 1 1 RO 3.4 SRO 3.6 54 560 Knowledge of the effect that a loss or malfunction of the Systems having pneumatic valves and controls ....................... . lAS will have on the following: (CFR: 41.7 / 45.6) SYS103 K1.07 Containment System T/G 2 1 1 RO 3.5* SRO 3.7* 55 561 Knowledge of the physical connections and/or cause- Containment vacuum system ...................................... . effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) SYS001 K2.02 Control Rod Drive System T/G 2 1 2 RO 3.6 SRO 3.7 56 562 Knowledge of bus power supplies to the following: (CFR: One-line diagram of power supply to trip breakers .................... . 41.7) SYS011 A1.02 Pressurizer Level Control System (PZR LCS) T/G 2 1 2 RO 3.3 SRO 3.5 57 57 563 Ability to predict and/or monitor changes in parameters Charging and letdown flows ....................................... . (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5/ 45.5) SYS016 K1.12 Non-Nuclear Instrumentation System (NNIS) T/G 2 1 2 RO 3.5* SRO 3.5* 58 564 Knowledge of the physical connections and/or cause- S/G ........................................................... . effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) SYS017 K3.01 In-Core Temperature Monitor (ITM) System T/G 2 1 2 RO 3.5* SRO 3.7* 59 565 Knowledge of the effect that a loss or malfunction of the Natural circulation indications .................................... . ITM system will have on the following: (CFR: 41.7/45.6) Page 9 of 12
2008 RO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS027 K5.01 Containment Iodine Removal System (CIRS) T/G 2/2 RO 3.1* SRO 3.4* 60 566 Knowledge of the operational implications of the following Purpose of charcoal filters ....................................... . concepts as they apply to the CIRS: (CFR: 41.7 /45.7) SYS035 2.2.40 Steam Generator System (S/GS) T/G 2 12 RO 3.4 SRO 4.7 61 567 SYS035 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5
/45.3)
SYS045 A3.05 Main Turbine Generator (MT/G) System T/G 2 1 2 RO 2.6 SRO 2.9 62 568 Ability to monitor automatic operation of the MT/G Electrohydraulic control system, including: (CFR: 41/7/45.5) SYS071 K4.01 Waste Gas Disposal System (WGDS) T/G 2 1 2 RO 2.6 SRO 3.0 63 569 Knowledge of design feature(s) and/or interlock(s) which Pressure capability of the waste gas decay tank provide for the following: (CFR: 41.7) SYS079 A4.01 Station Air System (SAS) T/G 2 1 2 RO 2.7 SRO 2.7 64 570 Ability to manually operate and/or monitor in the control Cross-tie valves with lAS ........................................ .. room: (CFR: 41.7/45.5 to 45.8) SYS086 K6.04 Fire Protection System (FPS) T/G 2 1 2 RO 2.6 SRO 2.9 65 571 Knowledge of the effect of a loss or malfunction on the Fire, smoke, and heat detectors .................................... . Fire Protection System following will have on the: (CFR: 41.7/45.7) GEN2.1 2.1.45 GENERIC - Conduct of Operations T/G 3 1 0 RO 4.3 SRO 4.3 66 572 Ability to identify and interpret diverse indications to validate the response of Conduct of Operations another indication. (CFR: 41.7 / 43.5 / 45.4) Page 10 of 12
2008 RO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System TierlGroup Importance ROISRO KIA Description GEN2.1 2.1.8 GENERIC - Conduct of Operations T/G 3 I 0 RO 3.4 SRO 4.1 67 573 Conduct of Operations Ability to coordinate personnel activities outside the control room. (CFR: 41.10 145.5/45.12/45.13) GEN2.2 2.2.2 GENERIC - Equipment Control T/G 3 I 0 RO 4.6 SRO 4.1 68 574 Equipment Control Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2) GEN2.2 2.2.39 GENERIC - Equipment Control T/G 3 I 0 RO 3.9 SRO 4.5 69 575 Equipment Control Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) GEN2.3 2.3.11 GENERIC - Radiation Control T/G 3 I 0 RO 3.8 SRO 4.3 70 576 Radiation Control Ability to control radiation releases. (CFR: 41.11 143.4/45.10) GEN2.3 2.3.4 GENERIC - Radiation Control T/G 3 I 0 RO 3.2 SRO 3.7 71 577 Radiation Control Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4/45.10) GEN2.3 2.3.7 GENERIC - Radiation Control T/G 3 I 0 RO 3.5 SRO 3.6 72 578 Radiation Control Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10) GEN2.4 2.4.13 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 4.0 SRO 4.6 73 579 Emergency Procedures 1 Plan Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 1 45.12) GEN2.4 2.4.22 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.6 SRO 4.4 74 580 Emergency Procedures 1 Plan Knowledge of the bases for prioritizing safety functions during abnormal/emergencyoperations. (CFR: 41.7 141.10 143.5/45.12) Page 11 of 12
2008 RO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description GEN2.4 2.4.42 GENERIC - Emergency Procedures I Plan T/G 3/0 RO 2.6 SRO 3.8 75 581 Emergency Procedures / Plan Knowledge of emergency response facilities. (CFR: 41.10 /45.11) Page 12 of 12
rltJkG 2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description EPE007 EK2.03 Reactor Trip T/G 1 1 1 RO 3.5 SRO 3.6 1 507 Knowledge of the interrelations between a reactor trip Reactor trip status panel and the following: (CFR 41.7 1 45.7) EPE009 EA2.10 Small Break LOCA T/G 1 11 RO 3.1 SRO 3.7 2 508 Ability to determine or interpret the following as they apply Airborne activity ................................................ . to a small break LOCA: (CFR 43.5/45.13) EPE011 2.4.30 Large Break LOCA T/G 1 11 RO 2.7 SRO 4.1 3 509 EPE011 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1 1 1 RO 2.7 SRO 3.1 4 510 Knowledge of the operational implications of the following Relationship of charging flow to pressure differential between charging and concepts as they apply to Loss of Reactor Coolant RCS ................................ . Makeup: (CFR 41.81 41.10/45.3) APE025 2.4.30 Loss of Residual Heat Removal System (RHRS) T/G 1 1 1 RO 2.7 SRO 4.1 5 511 APE025 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10/43.5/45.11) APE026 AA2.03 Loss of Component Cooling Water (CCW) T/G 1 1 1 RO 2.6 SRO 2.9 6 512 Ability to determine and interpret the following as they The valve lineups necessary to restart the CCWS while bypassing the portion apply to the Loss of Component Cooling Water: (CFR: of the system causing the abnormal condition ................. . 43.5/45.13) APE027 AA1.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 11 RO 3.9* SRO 3.6* 7 513 Ability to operate and 1 or monitor the following as they Pressure recovery, using emergency-only heaters .................... . apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 1 45.5 1 45.6) Page 1 of 16
2008 SRO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description EPE029 2.4.34 Anticipated Transient Without Scram (ATWS) T/G 1 1 1 RO 4.2 SRO 4.1 8 514 EPE029 GENERIC Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13) EPE038 EK1.02 Steam Generator Tube Rupture (SGTR) T/G 1 1 1 RO 3.2 SRO 3.5 9 515 Knowledge of the operational implications of the following Leak rate vs. pressure drop concepts as they apply to the SGTR: (CFR 41.8 / 41.10 / 45.3) APE057 AA2.13 Loss of Vital AC Electrical Instrument Bus T/G 1 11 RO 3.0 SRO 3.4 10 516 Ability to determine and interpret the following as they VCT level and pressure indicators and recorders .................... .. apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5/ 45.13) APE058 AA1.02 Loss of DC Power T/G 1/1 RO 3.1* SRO 3.1 11 517 Ability to operate and / or monitor the following as they Static inverter dc input breaker, frequency meter, ac output breaker, and apply to the Loss of DC Power: (CFR 41.7 / 45.5 / 45.6) ground fault detector ............................ . APE062 AK3.03 Loss of Nuclear Service Water T/G 1 11 RO 4.0 SRO 4.2 12 518 Knowledge of the reasons for the following responses as Guidance actions contained in EOP for Loss of nuclear service water .... they apply to the Loss of Nuclear Service Water: (CFR 41.4,41.8 /45.7) APE065 AK3.03 Loss of Instrument Air T/G 1 1 1 RO 2.9 SRO 3.4 13 519 Knowledge of the rea~ons for the following responses as Knowing effects on plant operation of isolating certain equipment from they apply to the Loss of Instrument Air: (CFR 41.5,41.10 instrument air .................................... .
/45.6/45.13)
Page 2 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description APE077 AA1.01 Generator Voltage and Electric Grid Disturbances T/G 1 1 0 RO 3.6 SRO 3.7 14 520 Ability to operate and/or monitor the following as they Grid frequency and voltage ........................................................ . apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10/45.5,45.7, and 45.8 ) WE04 EK2.2 LOCA Outside Containment T/G 1 1 1 RO 3.8 SRO 4.0 15 521 Knowledge of the interrelations between the (LOCA Facility*s heat removal systems, including primary coolant, emergency coolant, Outside the decay heat removal systems, and relations between the proper operation Containment) and the following: of these systems to the operation of the facility. (CFR: 41.7/45.7) WEOS EK3.1 Loss of Secondary Heat Sink T/G 1 11 RO 3.4 SRO 3.8 16 522 Knowledge of the reasons for the following responses as Facility operating characteristics during transient conditions, inciudingDcoolant they apply to the (Loss of Secondary Heat Sink) chemistry and the effects of temperature, pressure, and reactivity changes and (CFR: 41.5/41.10, 45.6,45.13) operating limitations and reasons for these operating characteristics. WE11 EK2.1 Loss of Emergency Coolant Recirculation T/G 1 11 RO 3.6 SRO 3.9 17 523 Knowledge of the interrelations between the (Loss of Components, and functions of control and safety systems, including Emergency instrumentation, signals, interlocks, failure modes, and automatic and manual Coolant Recirculation) and the following: features. (CFR: 41.7/45.7) WE12 EK1.3 Uncontrolled Depressurization of all Steam Generators T/G 1 1 1 RO 3.4 SRO 3.7 18 524 Knowledge of the operational implications of the following Annunciators and conditions indicating signals, and remedial actions concepts as they apply to the (Uncontrolled associated with the (Uncontrolled Depressurization of all Steam Generators). Depressurization of all Steam Generators) (CFR: 41.8/41.10/45.3) APE001 AA1.06 Continuous Rod Withdrawal T/G 1 12 RO 3.0* SRO 2.9* 19 525 Ability to operate and / or monitor the following as they Rod transfer switches ............................................ . apply to the Continuous Rod Withdrawal: (CFR 41.7 / 45.5/45.6) Page 3 of 16
2008 SRO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KiA Number KiA System Tier/Group Importance RO/SRO KiA Description APE005 2.4.6 Inoperable/Stuck Control Rod T/G 1 12 RO 3.7 SRO 4.7 20 526 APE005 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) APE024 AK1.04 Emergency Boration T/G 1 12 RO 2.8 SRO 3.6 21 527 Knowledge of the operational implications of the following Low temperature limits for born concentration ................... . concepts as they apply to Emergency Soration: (CFR 41.8/41.10/45.3) APE033 AK1.01 Loss of Intermediate Range Nuclear Instrumentation T/G 1 12 RO 2.7 SRO 3.0 22 528 Knowledge of the operational implications of the following Effects of voltage changes on performance .......................... . concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: CFR 41.8 / 41.10 / 45.3) APE037 AA2.03 Steam Generator (S/G) Tube Leak T/G 1 12 RO 3.4 SRO 3.9 23 529 Ability to determine and interpret the following as they That the expected indication on main steam lines from the S/Gs should show apply to the Steam Generator Tube Leak: (CFR: 43.5/ increasing radiation levels .................... .. 45.13) EPE074 EA1.01 Inadequate Core Cooling T/G 1 I 2 RO 4.2 SRO 4.4 24 530 Ability to operate and monitor the following as they apply RCS water inventory ............................................ .. to a Inadequate Core Cooling: (CFR 41.7/45.5/45.6) APE036 AK3.03 Fuel Handling Incidents T/G 1 12 RO 3.7 SRO 4.1 25 531 Knowledge of the reasons for the following responses as Guidance contained in EOP for fuel handling incident ................ .. they apply to the Fuel Handling Incidents: (CFR 41.5,41.10/45.6/45.13) WE03 EK2.1 LOCA Cool down and Depressurization T/G 1 12 RO 3.6 SRO 4.0 26 532 Knowledge of the interrelations between the (LOCA Components, and functions of control and safety systems, including Cooldown and instrumentation, signals, interlocks, failure modes, and automatic and manual Depressurization) and the following: features. (CFR: 41.7/45.7) Page 4 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description WE09 EK3.3 Natural Circulation Operations T/G 1 12 RO 3.5 SRO 3.6 27 533 Knowledge of the reasons for the following responses as Manipulation of controls required to obtain desired operating results during they apply to the (Natural Circulation Operations) abnormal, and emergency situations. (CFR: 41.5/41.10, 45.6,45.13) SYS003 A2.02 Reactor Coolant Pump System (RCPS) T/G 2 1 1 RO 3.7 SRO 3.9 28 534 Ability to (a) predict the impacts of the following Conditions which exist for an abnormal shutdown of an RCP in comparison to malfunctions or operations on the RCPS; and (b) based a normal shutdown of an RCP .................. . on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) SYS004 SYSOO4 A1.01 Chemical and Volume Control System T/G 2/1 T/G 2 11 RO 2.9 SRO 3.8 29 535 Ability to predict and/or monitor changes in parameters Activity levels in primary system (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5 145.5) SYSOO4 SYS004 K1.34 Chemical and Volume Control System T/G 2/12 11 RO 2.7 SRO 2.9 30 536 Knowledge of the physical connections and/or cause- Interface between CVCS and reactor coolant drain tank; and PZR PCS effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) SYS005 K4.11 Residual Heat Removal System (RHRS) T/G 2 1 1 RO 3.5* SRO 3.9* 31 537 Knowledge of RHRS design feature(s) and/or interlock(s) Lineup for low head recirculation mode (external and internal) which provide or the following: (CFR: 41.7) SYS006 A1.05 Emergency Core Cooling System (ECCS) T/G 2 11 RO 2.9 SRO 3.3 32 538 Ability to predict and/or monitor changes in parameters CCW flow (establish flow to RHR heat exchanger prior to placing in service (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5/45.5) Page 5 of 16
2008 SRO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS007 2.4.6 Pressurizer Relief Tank/Quench Tank System (PRTS) T/G 211 RO 3.7 SRO 4.7 33 539 SYS007 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10/43.5/45.13) SYSOOB K3.03 Component Cooling Water System (CCWS) T/G 211 RO 4.1 SRO 4.2 34 540 Knowledge of the effect that a loss or malfunction of the RCP .......................................................... . CCWS will have on the following: SYSOOB K4.09 Component Cooling Water System (CCWS) T/G 211 RO 2.7 SRO 2.9 35 541 Knowledge of CCWS design feature(s) and/or interlock(s) The "standby" feature for the CCW pumps ... ........................... . which provide for the following: (CFR: 41.7) SYS010 2.1.25 Pressurizer Pressure Control System (PZR PCS) T/G 2 I 1 RO 3.9 SRO 4.2 36 542 SYS010 GENERIC Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) SYS012 A2.02 Reactor Protection System (RPS) T/G 2 I 1 RO 3.6 SRO 3.9 37 543 Ability to (a) predict the impacts of the following Loss of instrument power ........................................ . malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.5) SYS012 K5.01 Reactor Protection System (RPS) T/G 2 I 1 RO 3.3* SRO 3.B 38 544 Knowledge of the operational implications of the following DNB .......................................................... . concepts as the apply to the RPS: (CFR: 41.5/45.7) SYS013 K6.01 Engineered Safety Features Actuation System (ESFAS) T/G 2/1 RO 2.7* SRO 3.1* 39 545 Knowledge of the effect of a loss or malfunction on the Sensors and detectors ........................................... . following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8) Page 6 of 16
2008 SRO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS022 K2.02 Containment Cooling System (CCS) T/G 211 RO 2.5* SRO 2.4* 40 546 Knowledge of power supplies to the following: (CFR: Chillers ....................................................... . 41.7) SYS025 A4.01 Ice Condenser System T/G 2 11 RO 3.0* SRO 2.7* 41 547 Ability to manually operate and/or monitor in the control Ice condenser isolation valves ..................................... . room: (CFR: 41.7/45.5 to 45.8) SYS026 A1.03 Containment Spray System (CSS) T/G 2 I 1 RO 3.5 SRO 3.5 42 548 Ability to predict and/or monitor changes in parameters Containment sump level .......................................... (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5 1 45.5) SYS026 K1.01 Containment Spray System (CSS) T/G 2 11 RO 4.2 SRO 4.2 43 549 ' Knowledge of the physical connections and/or cause- ECCS effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) SYS039 K5.01 Main and Reheat Steam System (MRSS) T/G 2 I 1 RO 2.9 SRO 3.1 44 550 Knowledge of the operational implications of the following Definition and causes of steam/water hammer ....................... . concepts as the apply to the MRSS: (CFR: 441.5/45.7) SYS059 A4.11 Main Feedwater (MFW) System T/G 2 11 RO 3.1 SRO 3.3 45 551 Ability to manually operate and monitor in the control Recovery from automatic feedwater isolation ....................... . room: (CFR: 41.7/45.5 to 45.8) SYS061 A3.03 Auxiliary I Emergency Feedwater (AFW) System T/G 2 I 1 RO 3.9 SRO 3.9 46 552 Ability to monitor automatic operation of the AFW, AFW S/G level control on automatic start ........................... . including: (CFR: 41.7/45.5) Page 7 of 16
2008 SRO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS062 A3.01 AC Electrical Distribution System T/G 2 1 1 RO 3.0 SRO 3.1 47 553 Ability to monitor automatic operation of the ac Vital ac bus amperage ........................................... .. distribution system, including: (CFR: 41.7/45.5) 48 SYS063 K2.01 DC Electrical Distribution System T/G 2/1 RO 2.9* SRO 3.1* 554 Knowledge of bus power supplies to the following: (CFR: Major DC loads 41.7) 49 SYS063 K3.01 DC Electrical Distribution System T/G 2 1 1 RO 3.7* SRO 4.1 555 Knowledge of the effect that a loss or malfunction of the ED/G DC electrical system will have on the following: (CFR: 41.7/45.6) SYS064 A3.07 Emergency Diesel Generator (ED/G) System T/G 2 1 1 RO 3.6* SRO 3.7* 50 556 Ability to monitor automatic operation of the ED/G Load sequencing ................................................ . system, including: (CFR: 41.7/45.5) SYS064 K6.07 Emergency Diesel Generator (ED/G) System T/G 211 RO 2.7 SRO 2.9 51 557 Knowledge of the effect of a loss or malfunction of the Air receivers ................................................... . following will have on the ED/G system: (CFR: 41.71 45.7) SYS073 A2.02 Process Radiation Monitoring (PRM) System T/G 211 RO 2.7 SRO 3.2 52 558 Ability to (a) predict the impacts of the following Detector failure ................................................ . malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor- rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45.13) Page 8 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS076 K2.01 Service Water System (SWS) T/G 2/1 RO 2.7* SRO 2.7 53 559 Knowledge of bus power supplies to the following: (CFR: Service water .................................................. .. 41.7) SYS078 K3.02 Instrument Air System (lAS) T/G 2 / 1 RO 3.4 SRO 3.6 54 560 Knowledge of the effect that a loss or malfunction of the Systems having pneumatic valves and controls ...................... .. lAS will have on the following: (CFR: 41.7/45.6) SYS103 K1.07 Containment System T/G 2/ 1 RO 3.5* SRO 3.7* 55 561 Knowledge of the physical connections and/or cause- Containment vacuum system ...................................... . effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) SYS001 K2.02 Control Rod Drive System T/G 2 / 2 RO 3.6 SRO 3.7 56 562 Knowledge of bus power supplies to the following: (CFR: One-line diagram of power supply to trip breakers .................... . 41.7) SYS011 A1.02 Pressurizer Level Control System (PZR LCS) T/G 2 / 2 RO 3.3 SRO 3.5 57 563 Ability to predict and/or monitor changes in parameters Charging and letdown flows ...................................... .. (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5/ 45.5) SYS016 K1.12 Non-Nuclear Instrumentation System (NNIS) RO 3.5* SRO 3.5* 58 T/G 2/2 564 Knowledge of the physical connections and/or cause- S/G ........................................................... . effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) SYS017 K3.01 In-Core Temperature Monitor (ITM) System T/G 2 / 2 RO 3.5* SRO 3.7* 59 565 Knowledge of the effect that a loss or malfunction of the Natural circulation indications .................................... . ITM system will have on the following: (CFR: 41.7/45.6) Page 9 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KiA Number KiA System Tier/Group Importance RO/SRO KiA Description SYS027 K5.01 Containment Iodine Removal System (CIRS) T/G 2/2 RO 3.1* SRO 3.4* 60 566 Knowledge of the operational implications of the following Purpose of charcoal filters concepts as they apply to the CIRS: (CFR: 41.7/45.7) SYS035 2.2.40 Steam Generator System (S/GS) T/G 2 / 2 RO 3.4 SRO 4.7 61 567 SYS035 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10/43.2/43.5 145.3) SYS045 A3.05 Main Turbine Generator (MT/G) System T/G 2 / 2 RO 2.6 SRO 2.9 62 568 Ability to monitor automatic operation of the MT/G Electrohydraulic control system, including: (CFR: 41/7/45.5) SYS071 K4.01 Waste Gas Disposal System (WGDS) T/G 2 / 2 RO 2.6 SRO 3.0 63 569 Knowledge of design feature(s) and/or interlock(s) which Pressure capability of the waste gas decay tank provide for the following: (CFR: 41.7) SYS079 A4.01 Station Air System (SAS) T/G 2 / 2 RO 2.7 SRO 2.7 64 570 Ability to manually operate and/or monitor in the control Cross-tie valves with lAS ......................................... . room: (CFR: 41.7/45.5 to 45.8) SYS086 K6.04 Fire Protection System (FPS) T/G 2 / 2 RO 2.6 SRO 2.9 65 571 Knowledge of the effect of a loss or malfunction on the Fire, smoke, and heat detectors .................................... . Fire Protection System following will have on the: (CFR: 41.7/45.7) GEN2.1 2.1.45 GENERIC - Conduct of Operations T/G 3 / 0 RO 4.3 SRO 4.3 66 572 Conduct of Operations Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 1 43.5 145.4) Page 10 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description GEN2.1 2.1.8 GENERIC - Conduct of Operations T/G 3 I 0 RO 3.4 SRO 4.1 67 573 Conduct of Operations Ability to coordinate personnel activities outside the control room. (CFR: 41.10
/45.5/45.12/45.13)
GEN2.2 2.2.2 GENERIC - Equipment Control T/G 3 I 0 RO 4.6 SRO 4.1 68 574 Equipment Control Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2) GEN2.2 2.2.39 GENERIC - Equipment Control T/G 3 I 0 RO 3.9 SRO 4.5 69 575 Equipment Control Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) GEN2.3 2.3.11 GENERIC - Radiation Control T/G 3 I 0 RO 3.8 SRO 4.3 70 576 Radiation Control Ability to control radiation releases. (CFR: 41.11 /43.4 / 45.10) GEN2.3 2.3.4 GENERIC - Radiation Control T/G 3 I 0 RO 3.2 SRO 3.7 71 577 Radiation Control Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 / 45.10) GEN2.3 2.3.7 GENERIC - Radiation Control T/G 3 I 0 RO 3.5 SRO 3.6 72 578 Radiation Control Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10) GEN2.4 2.4.13 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 4.0 SRO 4.6 73 579 Emergency Procedures / Plan Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 / 45.12) GEN2.4 2.4.22 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.6 SRO 4.4 74 580 Emergency Procedures / Plan Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CFR: 41.7 /41.10 /43.5 /45.12) Page 11 of 16
2008 SRO NRC Examination ES401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description GEN2.4 2.4.42 GENERIC - Emergency Procedures I Plan T/G 310 RO 2.6 SRO 3.8 75 581 Emergency Procedures / Plan Knowledge of emergency response facilities. (CFR: 41.10 / 45.11) EPE009 2.2.25 Small Break LOCA T/G 1 11 RO 3.2 SRO 4.2 76 582 EPE009 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5/41.7/43.2) EPE011 2.2.36 Large Break LOCA T/G 1 1 1 RO 3.1 SRO 4.2 77 583 EPE011 GENERIC Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 /43.2 / 45.13) APE026 AA2.05 Loss of Component Cooling Water (CCW) T/G 1 11 RO 2.4* SRO 2.5* 78 584 Ability to determine and interpret the following as they The normal values for CCW-header flow rate and the flow rates to the apply to the Loss of Component Cooling Water: (CFR: components cooled by the CCWS ....................... . 43.5/45.13) APE057 2.4.21 Loss of Vital AC Electrical Instrument Bus T/G 1 1 1 RO 4.0 SRO 4.6 79 585 APE057 GENERIC Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12) APE058 AA2.03 Loss of DC Power T/G 1 1 1 RO 3.5 SRO 3.9 80 586 Ability to determine and interpret the following as they DC loads lost; impact on ability to operate and monitor plant systems .... apply to the Loss of DC Power: (CFR: 43.5/45.13) APE077 AA2.09 Generator Voltage and Electric Grid Disturbances T/G 1 1 0 RO 3.9 SRO 4.3 81 587 Ability to determine and interpret the following as they Operational status of emergency diesel generators ....................... . apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 /45.5,45.7, and 45.8) Page 12 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description APE024 2.2.39 Emergency Boration T/G 1 12 RO 3.9 SRO 4.5 82 588 APE024 GENERIC Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/43.2/45.13) APE068 2.4.21 Control Room Evacuation T/G 1 I 2 RO 4.0 SRO 4.6 83 589 APE068 GENERIC Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12) APE069 AA2.01 Loss of Containment Integrity T/G 1 12 RO 3.7 SRO 4.3 84 590 Ability to determine and interpret the following as they Loss of containment integrity ..................................... . apply to the Loss of Containment Integrity: (CFR: 43.5/ 45.13) WE16 EA2.1 High Containment Radiation T/G 1 12 RO 2.9 SRO 3.3 85 591 Ability to determine and interpret the following as they Facility conditions and selection of appropriate procedures during abnormal apply to the (High Containment Radiation) and emergency operations. (CFR: 43.5/45.13) SYS003 A2.01 Reactor Coolant Pump System (RCPS) T/G 211 RO 3.5 SRO .39 86 592 Ability to (a) predict the impacts of the following Problems with RCP seals, especially rates of seal leak-off ............. . malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45/13) SYS026 2.4.47 Containment Spray System (CSS) T/G 2 I 1 RO 4.2 SRO 4.2 87 593 SYS026 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/ 45.12) Page 13 of 16
2008 SRO NRC Examination ES 401, Rev 9. Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group TierlGroup Importance RO/SRO KIA Description SYS039 A2.02 Main and Reheat Steam System (MRSS) T/G 2 1 1 RO 2.4 SRO 2.7* 88 594 Ability to (a) predict the impacts of the following Decrease in turbine load as it relates to steam escaping from relief valves. malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.13)
~-------------------------
SYS062 2.1.20 AC Electrical Distribution System T/G 211 RO 4.6 SRO 4.6 89 595 SYS062 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10/43.5/45.12) SYS076 A2.02 Service Water System (SWS) T/G 2 1 1 RO 2.7 SRO 3.1 90 596 Ability to (a) predict the impacts of the following Service water header pressure .................................... .. malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or. operations: (CFR: 41.5/43.5/45/3/45/13) SYS033 2.2.22 Spent Fuel Pool Cooling System (SFPCS) T/G 2 1 2 RO 4.0 SRO 4.7 91 597 SYS033 GENERIC Knowledge of limiting conditions for operations and safety limits. (CFR: 41.51 41.5/ 43.2/45.2) SYS072 A2.02 Area Radiation Monitoring (ARM) System T/G 2 12 RO 2.8 SRO 2.9 92 598 Ability to (a) predict the impacts of the following Detector failure ............................................... .. malfunctions or operations on the ARM system- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/43.31 41.5/43.5/43.3/ 45.13) Page 14 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS086 A2.01 Fire Protection System (FPS) T/G 2 I 2 RO 2.9 SRO 3.1 93 599 Ability to (a) predict the impacts of the following Manual shutdown of the FPS ..................................... .. malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13) GEN2.1 2.1.14 GENERIC - Conduct of Operations T/G 3 I 0 RO 3.1 SRO 3.1 94 600 Conduct of Operations Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CFR: 41.10/43.5/ 45.12) GEN2.1 2.1.36 GENERIC - Conduct of Operations T/G 3 I 0 RO 3.0 SRO 4.1 95 601 Knowledge of procedures and limitations involved in core alterations. (CFR: Conduct of Operations 41.10/43.6/45.7) GEN2.2 2.2.15 GENERIC - Equipment Control T/G 3 I 0 RO 3.9 SRO 4.3 96 602 Equipment Control Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.10 / 43.3 / 45.13) GEN2.2 2.2.3 GENERIC - Equipment Control T/G 3 I 0 RO 3.8 SRO 3.9 97 603 Equipment Control (multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5/41.6/41.7/41.10/45.12) GEN2.3 2.3.13 GENERIC - Radiation Control T/G 3 I 0 RO 3.4 SRO 3.8 98 604 Radiation Control Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12/43.4 / 45.9 / 45.10) Page 15 of 16
2008 SRO NRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description GEN2.3 2.3.14 GENERIC - Radiation Control T/G 3 I 0 RO 3.4 SRO 3.8 99 605 Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 /43.4 /45.10) GEN2.4 2.4.3 GENERIC - Emergency Procedures I Plan T/G 3 I 0 RO 3.7 SRO 3.9 100 606 Emergency Procedures / Plan Ability to identify post-accident instrumentation. (CFR: 41.6 /45.4) Page 16 of 16
ES-401, Rev. 9 Record of Rejected KJAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KA 1/2 APE076 AK3.06 (Q25) There is a question that was used on the 2006R (exam bank #148) which would meet this but within 2 years. It deals with demineralizers which is the only real action in AP/18. Replaced with KIA APE036 AK3.03 2/1 SYS008 K4.07 Q(35) No such component at eNS. KIA replacements originally provided 4.04 and 4.08 are not high enough value (2.1 and 2.3) Replaced with KIA SYS008 K4.09 1/0 APEO?? AA2.04 Q(81) Duplicate KA of RO exam #14. Replaced with KIA APEO?? AA2.09 1/1 APE025 2.2.39 Q(82) Cannot write an SRO question. Replaced with KIA APE024 G2.2.22 1/2 APE069 AA2.02 Q(84) Cannot write an SRO question. Replaced with KIA APE069 AA2.01 2/2 SYS086 A2.01 Q(93) Cannot write an SRO question. Replaced with KIA SYS086 A2.04
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: ~~A Date of Exam: '1-/t>,f II r Exam Level: ROO SRO~ Initial Item Description a b* q#
- 1. Questions and answers are technically accurate and applicable to the facility. Y l{f { f II ..1:
- 2. a.
b. NRC KJAs are referenced for all questions. Facility learning objectives obLectives are referenced as available. tv" ~~IJ'1 D
- 3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 IV IfJ.s!'
{'J-.st" -< 1-<1 ~
- 4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office). .
j
- 5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
<f1A cI
_ the audit exam was systematically and randomly developed; or _ the audit exam was completed before the license exam was started; or
~e examinations were developed independently; or
_ the licensee certifies that there is no duplication; or I~~
~~
_ other (explain)
- 6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only question distribution(s) at right.
I~ / I <1 / r 41/ 23 JI? ~rJ( J
- 7. Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly h j~
selected KJAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right.
~S- / S- 't 6 / 2-D ~r(
1t'1~ .~ i1 It'l~ h
- 8. References/handouts provided do not give away answers or aid in the elimination of distractors.
f
~ b~ .>~ ~
- 9. Question content conforms with specific KJA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
- 10. Question psychometric quality and format meet the guidelines in ES Appendix B. i1 w ~ ~\ j)#
. \
V,I
- 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. 4'( bif )
Printed Name /,~ / Signature Date
- a. Author jo~ k'...~
_~jo~ ~. ~ I~L -;j..J. - II/M/Ol
- b. Facility Reviewer (*) I5~JAN D.
"BielAN M i I...L f 12 '-v/k<-
D.Mil...lfl2 ZI/bo-~ ~ --h. ~ t;Ih /di{'/l>~
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- c. NRC Chief Examiner (#) (~i3i2Af2D
(~~ ~r L..45~A~l\.,~ Lk5C61Y/..lV.,;,.,1/ li..t::::,kd! 11!141&u 11/14/&i.£
- d. NRC Regional Supervisor r lI/f[)'uA.f '" J T 12\
t1.JAtcdu.;.-r: 1l/!J),{jAAIA.1 /J\ J..,
.J." !~/t.f(
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Note:
- The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
# Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
F1}/{tL ES-401, Rev. 9 Catawba 2008-301 RO Written Examination Review Worksheet Form ES-401-9
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD ~--~~~--r---.---~--.----.---r---; (FIH) (1-5) Stem Cues T/F Stem Icuesl Focus T/F I Credo Partial Job-cred'lpartiall Dist. JOb-I Minutia Link Minutia I #1 Back- Q=
#1 I Back-I units ward KIA Q= I SROSRO Only IS utE! Explanation Instructions
[Refer to Section 0 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.
12.2. Enter the level of difficulty (LaD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 2-
- 4 range are acceptable).
b.
- 13. 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).
k14. 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 KIA 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.
Is.15. Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable). I
!6. ,6. Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 7. At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met).
I::;r,~.,d{~.n~;t::~t~l;*'lit;]t;~!:;l; ;,: ii:; ;2'1~~"li;fll ~ OQ71,~Ii~2;!O~I;Bo[m~rilin~'Kli/.f;.;\m~i
Q# 1. 1. LOK I 2. LOD
- 3. Psychometric Flaws 4. Job Content Flaws
- 2. ~--,-~.---~--~--~---.----~--~--~
~I---.---r--~----r---4---~--~--~---4
- 5. Other 6. 7.
Explanation (F/H) (1-5)
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Sack- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 009EA2.1 Question appears to match KiA. 2 H 2 X E Distractors A and B may not be plausible. Is there any time that Safety Injection Actuated light is lit that the operators would not go to E-O besides a loss of aIlAC? NEW Licensee stated that there are times that the SI S light would be lit, and the operators would go to another procedure besides E-O. (accumulators isolated) The licensee added an RCS Pressure, and temperature to allow the applicant to decide which procedure was applicable. SAT 11/03/2008. 011 EG2.4.30 SAT BANK - 2005 NRC exam. 3 F 2 S 022AK1.02 Question kind of matches KiA. "SAT. 4 H 2 S This question could be easily modified. BANK - 2005 NRC exam. 025AG2.4.30 Question appears to match KiA. I 5 H 2 X E think this was also on the 2007 exam will check to ensure. OMP 1-7 states two are required without a procedure. This action will be outside the procedure, therefore someone could argue 0 is also correct (more conservative. NEW? S Licensee changed stem to have the question deal in accordance with the sites procedure OMP-1-7. (Changed all distractors) SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 026AA2.03 Question appears to match KIA. SAT 6 H 2 S NEW 027AA1.04 Question appears to match KIA. SAT 7 F 2 S NEW 029EG2.4.34 Question appears to match the KIA. 8 F 2 E Question needs some enhancements. The operator need only know that the motor generator out put breaker needs to be opened and D is the answer. Change the distractors to be 1 and 2 only, 1, 2, and 3 only 1, 2, and 4 only and 1, 2, 3, and 4. NEW Licensee made changes as requested. SAT S 11/03/2008. 038EK1.02 Question kind of matches KIA. 9 H 2 S BANK - 2005 NRC exam Please change the answers so that the Correct answer is different than C. OS7AA2.13 Question appears to match KIA. SAT 10 F 2 S NEW
Q# 1. 1. LOK I 2. 2. LOD
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other I 6. 7.
Explanation (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO U/EI Focus Dist. Link units ward KIA Only S 058AA1.02 Question appears to match KIA. SAT 11 F I 2 E (Is the time limit in accordance with a procedure? If so, this should be stated). NEW S ILicensee Licensee added lAW OP/lIAl6350/008. SAT 11/03/2008. 065AK3.03 Question appears to match KIA. I S I065AK3.03 13 H 2 S assume the crew entered AP/O/A/5500/022 due to air leak? You might need to say this. NEW Licensee Made NO changes. SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ 8ack- 0= SAO utEi Explanation Focus Dist. Link units ward KIA Only S 077AA 1.01 Question appears to match KIA. This 14 H 2 E may be considered a direct look up. I will have another examiner review and comment. NEW Licensee has blacked out the information on the S referenced graph that would make the question a direct lookup. SAT 11/03/2008. W/E04EK2.2 Question appears to match KIA. 15 H 2 S Modified from 2004 NRC exam. SAT Modified. SAT 11/03/2008. W/E05EK3.1 Question matches KIA. SAT I 16 F 2 S I NEW SAT 11/03/2008. W/E11EK2.1 Question appears to match KIA. Are 17 F 2 S the defeat buttons in distractor C labeled correctly? Otherwise question appears to be SAT. NEW Added FWST to C distractor now labeled correctly. SAT 11/03/2008. W/E12EK1.3 Question Kind of matches KIA. Is an 18 F 2 E annunciator received when the MSIVs are closed or a MSLI is received? Using one of these indications would match the KIA better. NEW S Changes made as requested. SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LaD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 19 H 2 E 001 AA 1.06 Question does not really meet the KIA, however it is a good attempt, and the switch involved does transfer some control of the rods. The stem should state lAW whatever procedure is applicable for example lAW AP-15. S NEW Licensee added lAW AP-15. SAT 11/03/2008. 20 F 2 S 005AG2.4.6 Based on a previous discussion AP actions were determined to be acceptable to satisfy Keff this KIA. Is there any occurrence of Mode 2 with Ketti 2': 1.0? If not this may not be acceptable. Will Discuss. NEW I Licensee stated that TS3.1.6 does have actions that refer to the above. No other changes made. SAT 11/03/2008. , 21 H 2 S 024AK1.04 Question appears to match KIA. SAT NEW SAT 11/03/2008. I 22 F 2 S 033AK1.01 Question appears to match KIA. SAT NEW SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 8ack- Q= SRO utEl Explanation Focus Dist. Link units ward KIA Only S 23 H 2 E 037AA2.03 Question appears to match KIA. Need to add a specific power level for the Unit. 60% or so, some one could make the assumption that power had been reduced to a level where the N-16 monitors may not be the first indication. Otherwise SAT. Modified from a 2003 NRC exam. S Added the crew has stabilized the plant at the runback target per Al1/5500/003 (Load Rejection) SAT 11/03/2008. 24 H 4 S 074EA1.01 Question kind of matches KIA. Change
#2. to read: Why are these conditions more restrictive than earlier transition conditions Otherwise SAT. (Is this RO knowledge?)
NEW Licensee made changes as requested. SAT 11/03/2008.
Q# 1. LOK LOK I 2. LOD LOD II--.-----=-....--,----.---i----.-----"T----r--l
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
(F/H) (1-5) Explanation WE03EK2.1 E03EK2.1 Question appears to match KIA. Need 26 H 2 add ReS temperature. Used on the 2004 NRC exam under KIA 005K4.02 BANK Made changes as requested. SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- 0= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S WE09EK3.3 Question does not meet KIA. The KIA H 2 X U 27 asks for reasons. Why do they stop depressurization when RVLlS is less than 73%? From 2006 NRC exam. Modified S Added a basis for stopping the depressurization. SAT 11/03/2008. 003A2.02 Question appears to match KIA. Very H 2 X similar to question # 86 (SRO). The only difference 28 is the initiating event. What procedure directs these actions? It seems to me that there is not a correct answer. AP-4 does direct the actions listed in choice C, but you would have to go to the procedure to perform them. Question symmetry does not look S right. One of these needs to be changed. 2004 NRC exam BANK Discussed with Licensee. Determined based on discussion that question as written is SAT. Shuffled distractors. SAT 11/03/2008.
Q# 1. LOK LOK I I2. 3. Psychometric Flaws 4. Job Content Flaws LODI----r--....;..,.----,-____,r__-~__r--_r_____,r____I LOD
- 5. Other 6. 7.
(F/H) (1-5) Explanation H I 22 I XX I I I~~ ..... 004K1.34 34 Question appears to match KIA. Need to 30 I E place in the stem Excess letdown is in service and aligned gned to the VCT, or someone could make the assumption that excess letdown was aligned to the NCDT to begin with. Otherwise okay. S SINEWNEW Licensee made changes as requested. SAT 11103/2008. I SS 1005K4.11 K4.11 Question appears to match KIA. SAT this 31 I F I I2 2 is a fundamental level question. NEW SAT T 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 006A 1.05Question appears to match KIA. Please 32 H 2 E add automatically to the stem. 'What is the earliest time that KC flow is automatically aligned to the NO heat exchanger?" NEW S Licensee made changes as requested. SAT 11/03/2008. 007G2.4.6 Question Does not match KIA. The KIA 33 H 2 X U system is Pressurizer Relief Tank and how EOP mitigating strategies relate. This question is an H.1 question describing what constitutes a bleed and feed. NEW S Licensee replaced question. Chief Examiner allowed AOP actions to satisfy the KIA. (Normally EOPs do not address this). Otherwise the KIA appears to match. SAT 11/03/2008. 008K3.03 Question appears to match the KIA. 34 H 2 E Change Distractor C to read ... Open the #1 seal bypass valve to restore seal cooling. Change distractor 0 to read All seal cooling to NCP1 C is lost. Secure NCP 1C to prevent further seal damage. SAT 2004 NRC exam. BANK S Made changes as requested. Shuffled distractors. SAT 11/03/2008.
--I....--
Q# 1. 1. I LOK I 2. 2. LOD
- 3. Psychometric Flaws 4. Job Content Flaws I 5. Other I 6. I 7.
Explanation (F/H) (1-5) Stem T/F Credo Partial Job- Minutia #1 Back- Q= SRO U/EI U/Eil Focus Dist. Link units ward KIA Only S 008K4.09 Question appears to match the KIA. SAT 35 H 2 S 12007 NRC Exam Modified. I I I I I I I I I I I SAT 11/03/2008. 01 OG2.1.25 Question appears to match the KIA. 36 H 2 S SAT IS ISATNEW NEW I I 2 I I I I I I I I I SAT 11103/2008. 2A2.02 Question appears to match KIA. NEW 012A2.02 37 I H I 2 I X I I X I Will the OTOT bistables be in if just the lower I E IWili etector on N-42 failed low? If not, and the bistables detector have not been placed in a tripped condition, the reactor may not trip, and C would be correct. Please explain. NEW Ran on simulator at BOL and EOL conditions and S confirmedrmed that with only the lower detector failing low the OTDT bistable would still come in. SAT 11103/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD ~--~~--~----~--~~----~~~~ (F/H) (1-5) Stem Cues T/F Stem Icuesl Focus I T/F Credo Partial I JOb-I cred*1 Partial Dist. Job- Minutia Link Minutia I #1 8ack- Q=
#1 I Back-I SRO I u/EI Q= I SRO units ward KIA Only u/EI S
Explanation 013K6.01 3K6.01 Question appears to match KIA. SAT. 39 H 2 005 NRC Exam. S 12005 BANK SAT 11/03/2008. 025A4.01 Question appears to match KIA. Appears 41 I F 1212 IS to be SAT. Ito NEW SAT 11/03/2008. 026A1.03 Question appears to match KIA. SAT 42 I F 1212 1 SSiNEW NEW SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Credo Partial Job- Minutia #1 Stem Icuesl T/F I Cred.IPartiallJOb-IMinutial Back- Q=
#1 I Back-I Q= I SRO UlEi SRO IUlEI Explanation Focus Dist. Link units ward KIA Only S 026K1.01 Question appears to match KIA. Very 43 H 2 xX wordy.
E Iword Y. Attempt to get rid of most of the BOP reports. Actual stem needs some modification Which one of the following describes the status of the 1A NS pump pu at 1245, and the earliest time that NO Aux spray can be placed in service? NEW S ILicensee Licensee made changes as requested. SAT 11/03/2008 11/03/2008.. 059A4.11.11 Question appears to meets KIA. 45 I F I 2 I I S 12003 NRC exam question. BANK Licensee shuffled distractors as requested. SAT 11/03/2008. 061A3.03 1A3.03 Question appears to meets KIA. SAT. 46 F 2 S NEW IS INEW I 2 I I I I I I I I I I SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 8ack- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 062A3.01 Question appears to meet KIA. Change 47 H 2 E 2B Amps to 2B output amps. (field amps will decrease as voltage is lowered. NEW S Added output to 2B amps. SAT 11/03/2008. 063K2.01 Question appears to meets KIA. There 48 F 1 X U are no plausible distractors. Only one power supply is DC @ 125 volts, and the correct answer (250V). Almost all emergency lube oil pumps in the industry are DC. Need to have more plausible distractors. As written very little discriminatory value. NEW S Replaced question. Very simple. Appears to match KIA. SAT 11/03/2008. 063K3.01 Question appears to match KIA. 49 F 2 X E Distractor B does not appear to be plausible. 2004 NRC exam. BANK S Licensee changed distractor B to be more plausible. SAT 11/03/2008. 064A3.07 Question appears to match KlA.SAT 50 H 2 S NEW SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 8ack- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S 064K6.07 Question appears to match KIA. SAT 51 F 2 E 2003 NRC exam question. Add automatically and manually started to D. BANK S Licensee made changes as requested. SAT 11/03/2008. 073A2.02 Question kind of matches KIA. What 52 H 2 X ? E procedure is used to mitigate the failure? The actions should be lAW a procedure. It appears that Ctmt. ventilation is isolated and must be restored. NEW S Licensee made changes, SAT 11/03/2008. underlined not 076K2.01 Question appears to match KIA. Do any 53 F 1 S of these busses supply 1 ETA? If so it is also a correct answer. NEW SAT 11/03/2008. i 078K3.02 Question appears to match KIA. Some of 54 F 2 S the information in the stem is window dressing. SAT NEW SAT 11/03/2008. 103K1.07 Question kind of matches KIA. What is 55 F 2 E the significance of the second part of the question? Do you have a containment vacuum system? Which one of the following foliowinQ describes a condition that
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 8ack- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S would automatically close 1VQ-1 0, and what would the consequence be if the valve failed to close? NEW S Licensee changed all distractors and stem. SAT 11/03/2008. 001 K2.02 Does not match the KIA. This question 56 F 2 X U really asks what happens if both bypass breaker are closed, not power supplies. NEW S Replaced Question with a new question. Appears to match the KIA. SAT 11/03/2008. 011 A 1.02 Question kind of matches KIA. The 57 H 2 E question should be at approximately what time does charging/letdown have to be returned to service to prevent exceeding a T/S limit. 2005 NRC exam Modified. S After discussion with licensee, OK leave as is. SAT 11/03/2008. 016K1.12 Question appears to match KIA. Not sure 58 H 1.5 E if all of these are plausible. Will discuss. BANK Licensee shuffled all distractors, discussed question and distractor plausibility. SAT S 11/03/2008. 017K3.01 Question appears to match KIA. SAT. 59 H 2 S 2003 NRC exam.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S BANK Shuffled distractors. SAT 11/03/2008. 027K5.01 Question appears to match KIA. Stem 60 F 2 E Focus - Radiation monitoring teams would measure actual dose not projected dose. Could we change distractor 0 to read heaters are de-energized? 2003 NRC exam. BANK Licensee changed distractor D. Shuffled distractors, removed projected from stem. SAT 11/03/2008. 035G2.2.40 Questions appears to match KIA. 2005 61 F 2 S NRC exam. SAT BANK Shuffled distractors as requested. SAT 11/03/2008. 045A3.05 Question appears to match KIA. 62 H 2 X X S Distractors C and 0 are not plausible. Is there such a thing as a manual runback? Are you talking about manually ramping load off of the turbine? This question needs some work. NEW Stem was changed by eliminating the concerns of the chief examiner. SAT 11/03/2008.
Q# 1. LOK LOK I I 2. LOD
- 3. Psychometric Flaws 4_ Job Content Flaws 4.
LOD~--'-~---'---'---+--'----'--'---~
- 5. Other
- 6. 7.
(F/H) (1-5) Explanation 079A4.0101 Question kind of matches KIA. There is 64 I H I 2 I no I E Ino sequence in the distractors, they are all in the same order. At what pressure do the valves perform the swap? How can an operator monitor them with out knowing the pressure that should operate? Not very discriminating. 2003 NRC exam question. BANK Made changes as requested. Need to shuffle S Idistractors distractors around. SAT 11/03/2008. 086K6.04 Question appears to match KIA. SAT. 65 I F I 2 I ISS INEW NEW SAT 11/03/2008. G2.1.45 Question appears to match KIA. Do you 66 I H I 2 I IE Ihave a % steam flow indicator? I don't think so? Need another name for #1. Otherwise it is not plausible. NEW S Iucensee Licensee informs NRC that they do indeed have
% steam flow meter. SAT 11/03/2008.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Back- Q= SRO U/EI Explanation Focus Dist. Link units ward KIA Only S G2.1.8 Question appears to match KIA. SAT 67 F 2 S NEW SAT 11/03/2008. G2.2.2 Question appears to match KIA. SAT 68 F 2 S NEW SAT 11/03/2008. G2.2.39 Question appears to match KIA. SAT 69 F 2 S 2003 NRC Exam. Modified SAT 11/03/2008. G2.3.11 Question appears to match KIA. SAT 2003 70 F 2 S NRC Exam BANK SAT 11/03/2008. G2.3.4 Question appears to match KIA. SAT 2004 71 F 3 S NRC exam. BANK SAT 11/03/2008. G2.3.7 Question appears to match KIA. 2003 NRC 72 H 2 E exam. BANK This question can be easily modified to be some what different than the bank question. BANK Licensee shuffled distractors but did not change the basic question. SAT 11/03/2008.
-~--
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD , (FIH) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ Back- er- SRO U/EI Explanation Focus Dist. Link units ward KIA Only S G2.4.13 Question appears to match KIA. Distractors 73 F 2 X Band 0 are not plausible. Everyone with a license is responsible for CSFs. So why would a procedure not allow someone else with a license to be given the task of monitoring CSFs. Need better distractors. NEW S Revised question appears to be acceptable. SAT 11/03/2008. G2.4.22 Question appears to match KIA. SAT 74 H 2 S NEW SAT 11/03/2008. G2.4.42 Question appears to match KIA. SAT 75 F 2 S NEW SAT 11/03/2008. I 39 Sats, 10 Unsats, and 26 Enhancements I Generic Comments: Need all originals of modified questions. All bank questions should have the answers rotated from original (i.e. if the answer was originally A, swap the correct answer to B, C, or D.
~;JJkU ES-401, Rev. 9 Catawba 2008-301 SRO Written Examination Review Worksheet Form ES-401-9
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD ~----~~~----~----~----~----~----~-----r----~ (F/H) (1-5) Stem Stem Icuesl Cues T/F Credo Partial T/F ! cred.! partial! Job- Minutia #1 JOb-! Minutia! #1 ! Back-! Back- Q=Q= ! SRO U/EI SRO I U/EI Explanation Focus Dist. Link units ward KIA Only S Instructions [Refer to Section 0 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 KIA 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 KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable).
- 6. Based on the reviewer's judgment, is the question as written (U}nsatisfactory (requiring repair or replacement), in need of (E}ditorial enhancement, or (S}atisfactory?
- 7. At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met).
Q# 1. LOK LOK I I2. LOD LOD
- 3. Psychometric Flaws 4. Job Content Flaws I---.,...---.:....,.----.r---.---.j----,.--~-._____I
- 5. Other 6. 7.
(F/H) (1-5) Explanation E ,011 011 EG2.2.36 Question appears to match the KIA. 77 H 3 x Reference for question 77 could help answer question 76. Appears to be SRO only. Stem Focus is also confusing. Try "assuming that components remain inoperable." Second question discussing ECCS Criteria. Enhancements needed. NEW Licensee made enhancements as requested, changed anged question 76. SAT 11.05/2008
1.
- 1. I 2.
2.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other I 6. 7.
0# LOK (F/H) LOD (1-5) Stem Focus T/F Credo Partial Job- Minutia #1 Back-Dist. Link units ward 0= KIA SRO SRO Only Iu/EI u/EI S Explanation 78 H I 2 I X I TEE 026AA2.05 Question Kind of matches KIA. There is not really a loss of the CCW system, but it is a loss of a control function of the system that effects CCW flow to the NO system. Stem Focus, second part of stem should read and what system is required to be declared inoperable? NEW Licensee made changes as requested. SAT,T 11/05/2008
1.
- 1. I 2.
2.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other I 6. 7.
Q# LOK (F/H) LOD (1-5) Stem Cues Focus T/F Cred. cred.! Partial Dist. partial! Job- Minutia #1 JOb-! Minutia! Link Back- Q=
#1 ! BaCk-!
units ward KIA SRO Q= ! SRO Only Iu/EI u/EI S Explanation 80 I F? I 2 I X I TsS 058AA2.03 Question does not really meet the KIA. What DC loads were lost? I am sure that if the unit trips that some loads were lost. I also realize that th entering of E-O implies that the loss of dc (impact) caused the reactor to trip. Question was also marked as a memory level question. A reference is also provided. If this is a memory level question then a reference should not be required. NEW Monitoring Voltage is what the licensee considered as the impact on ability to operate and monitor plant systems. OK. (Reference removed) Question is SAT 11/05/2008
Q# 1. LOK I 2. LOD I 3. Psychometric Flaws 4. Job Content Flaws r---,---.----.----r---;---.-----r--,r-~
- 5. Other 6. 7.
(F/H) (1-5) Explanation
Q# 1. LOK I I2. 3. Psychometric Flaws 4. Job Content Flaws LOD I---.--~----'r---.----I-.....,.--,.--.-----l
- 5. Other
- 6. 7.
(F/H) (1-5) Explanation E16EA2.1 Question does not totally meet the KIA. 85 F 2 x x re is no procedure selection. The applicant is given what procedure is to be implemented in the Stem. However, there is some value in the setpoint requires entry into the procedure, this is RO knowledge. The basis statements are really the nction of a charcoal filter. This is also RO function (radiation worker knowledge). Therefore the question is not SRO only. NEW Licensee rewrote question, changed setpoints to be more realistic, and added actions to perform at would mitigate the event. Appears to match that KIA. Appears to be SRO only. SAT 11/05/2008
1.
- 1. I 2.
2.
- 3. Psychometric Flaws 4. Job Content Flaws 5. Other I 6. 7.
Q# LOK (F/H) LaD (1-5) Stem Cues Focus T/F Credo Partial Job- Minutia #/ Back-Dist. Link units ward Q= KIA SRO SRO Only IU/EI U/EI S Explanation 86 H I 2 TE uu",..*,,:~.01 I\J\J.~,.., .... 01 Question appears to match KIA. Appears be SRO only. What makes the procedure selection lection in C plausible? NEW Licensee changed distractor C. SAT 11/05/2008 S 026G2.4.47 .47 Question appears to match KIA. 87 H 2 pears to SRO only. SAT NEW
Q# 1. 1. LOK (F/H) I 2. 2. LaD (1-5)
- 3. Psychometric Flaws Stem Cues T/F
- 4. Job Content Flaws Credo Partial Job- Minutia #1 Back- Q=
- 5. Other SRO I 6.
u/EI 7. Explanation Focus Dist. Link units ward KIA Only S 076A2.02 Question appears to match KIA. Appears 90 H I 2 to be SRO knowledge. SAT. NEW SAT 11/05/2008
Q# 1. LOK I 2. I 3. Psychometric Flaws 4. Job Content Flaws LOD i---,-----,r---r---.----t---.------.----.----1
- 5. Other 6. 7.
(F/H) (1-5) Explanation
.1.14 Question appears to match KIA. Do not see 94 H 3 x how this is a general emergency. If a site uation is always precluded by a site assembly, evacuation why would anyone choose B or D. There is not a release etc. Question needs some work. Modified S ILicensee changed distractors band d (added non-essential personnel) SAT 11/05/2008
Q# 1. LOK LOK I I2. LOD
- 3. Psychometric Flaws 44. .ioh Job Content Flaws LOD ~--,-~.---.---~--~---.----.---,---~
- 5. Other 6. 7.
(F/H) (1-5) Explanation
Q# 1. LOK LOK I 2. I 3. Psychometric Flaws 4. Job Content Flaws LOD ~--T-~r---r---~--~--~--~---r--~ LOD
- 5. Other 6. 7.
(F/H) (1-5) Explanation 99 F 2 E IG2.3.14 Question appears to match KIA. Appears to be SRO only. Both of the Notifications are required. Need to change to soonest required notification, or something similar. NEW S S 'Licensee Licensee added first to stem. SAT 11/05/2008
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #/ 8ack- Q= SRO UJE/ Explanation Focus Dist. Link units ward KIA Only S G2.4.3 Question appears to match KIA. Not SRO 100 F 1 X U only knowledge. All operators are required to know PAM indicators and the why is obvious. Discussed changing the basis statements for C and D will look at again on prep week. 11/04/2008. 2 Sats, 15 Unsats, and 8 Enhancement =60 % unsatisfactory. Overall 29% of questions were deemed to be unsatisfactory before discussing with licensee. (SRO and RO combined.)
ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Catawba 2008-301 Date of Exam: 12/10/2008 Exam Level: RO/SRO Initials Item Description a b c
- 1. Clean answer sheets copied before grading
- 2. Answer key changes and question deletions justified and documented
- 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
- b. Facility Reviewer(*)
- c. NRC Chief Examiner (*)
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(Jllz~/II'
- d. NRC Supervisor (*)
(*) The' facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
ES-403 Written Examination Grading Form ES-403-1 Quality Checklist v*n ,t} Facility: {'1}--r/1 l/' j} /2))&'/0 Date of Exam: /2-))&,)0 <J
<[ ROGXj SROM Exam Level: RO[b(.l SROW Initials Item Description a b c
- 1. Clean answer sheets copied before grading IJ'~v
- 2. Answer key changes and question deletions justified and documented l)ltV
- 3. Applicants' scores checked for addition errors (reviewers spot check> 25% of examinations) :,(t;[)
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- 4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail 7(!!/
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- 5. All other failing examin~tions checked to ensure that grades are justified Xt{J
- 6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants )10 Printed Name/Signature Date
- a. Grader X$C£&~ ) 2-/;ljt2'[
- b. Facility Reviewer(*)
- c. NRC Chief Examiner (*)
- d. NRC Supervisor (*)
(*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. ES-403, Page 6 of 6}}