ML112000663
| ML112000663 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 02/07/2011 |
| From: | Walton R NRC/RGN-III/DRS/OLB |
| To: | |
| Shared Package | |
| ML110460310 | List: |
| References | |
| Download: ML112000663 (50) | |
Text
{{#Wiki_filter:2011 KEWAUNEE POWER STATION INITIAL EXAMINATION ADMINISTRATIVE FILES
ES..201 Examination Preparation Checklist Form ES ..201*1 Facility: \<ewQ.v~ 20\\ Date of Examination: ~ 2.0\\ Developed by: Written - Facility ~ NRC 0 /I Operating - Facility ~ NRC 0 Target Chief Date* Task Description (Reference) Examiner's Initials
-180 1. Examination administration date confirmed (C.1.a; C.2.a and b) f2tLJ
-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) ~W
-120 3. Facility contact briefed on seclJrity and other requirements (C.2.c) ,~
-120 4. Corporate notification letter sent (C.2.d) Af,\J
[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 3)] tJ\A {-75} 6. Integrated examination outline(s) due, including Forms E5-201-2, 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. i.e and f; C.3.d) R'vt\J {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)} ~'V.-vJ {-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 ES-201-3 updates), and reference materials due (C.1.e. f. g and h: C.3.d) fi0
-30 9. Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.g; ES-202)
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-14 10. Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i; ES-202) " <<..\J. W
-14 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) " ~V
-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) ~\,{)
-7 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)
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-7 14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications I eligibility; and examination approval and waiver letters sent Rvt \,J (C.2.!; Attachment 5; ES-202. C.2.e; ES-204)
-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k) ~VJ,)
-7 16. Approved scenarios, job performance measures, and questions (JtU) distributed to NRC examiners (C.3.i)
- Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification 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
Dominion Energy Kewaunee, Inc. N490 Hwy 42, Kewaunee, WI 54216 Dominion Web Address: www.dom.com MAY 1 2 2011 Regional Administrator, Region III Serial No. 11-264 U. S. Nuclear Regulatory Commission LlC/NW/RO 2443 Warrenville Road, Suite 210 Docket No.: 50-305 Lisle, IL 60532-4352 License No.: DPR-43 Attention: Dell McNeil DOMINION ENERGY KEWAUNEE, INC. KEWAUNEE POWER STATION OPERATOR LICENSE POST EXAMINATION MATERIAL In accordance with the guidelines of NUREG-1 021, Revision 9, Supplement 1, ES-501, the identified post-examination material is enclosed. Forms ES-201-3, "Examination Security Agreement" If you have questions or require additional information, please feel free to contact Mr. Dan Laing at 920-388-8691 . Very truly yours, ~Ws] Steph n . Scace t'.a.~ Site Vice President, Kewaunee Power Station Enclosure Commitments made by this letter: NONE cc: Without enclosure NRC Senior Resident Inspector Kewaunee Power Station Madison, WI 53707 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 MAY 1 8 2011
ES-201 Examination Security Agreement Form E5-201-3
- 1. Pre-Examination t acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled forthe week(s) of;;'>/7-/7bt 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 ifthe 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 oflhe conditions of this agreement may result in cancellation of the examinations and/or an enforcement actionagainstme 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..?/7'-j;ty/ . 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 AgreelTlent Form ES-201-3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC lice~sing examinations scheduled for the weekes) of:</7"";~1 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 knOW~dge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the weekes) of7~-/i~<o//. 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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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 "it 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 sel~ct the training content or provide direct or indirect =
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<0 feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and N understand that violation of the conditions of this agreement may result in cancellation of the examinations andlor an enforcement action against me or w the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security co co may have been Compromised. co co en
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ES-201 ~_ _ _ _ _ _ _ Exami,..ation Security Agreement UD<t.. _13/'WvC;:; Form E5-201-3
- 1. Pre-Examination
. f acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes) of.;;('/7"-I~ 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 ilidirect 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 andlor 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 knO~dge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of~ -/[&II'//' 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 I RESPONSIBILITY DATE ~ DATE NOTE ItA Ir1t" -!: 7/;c4 ScJ""'4b
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ES*201 Examination Security Agreement Form ES-201-3
- 1. Pre-Examination 02/7~/'1/Z()(I
. I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled forthe weekes) o~q;: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 ifthe 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 ofthe 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 1f?-cC/h/ . From the date that' 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 I RESPONSIBILITY SIGNATURE (1) DATE
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ES-201 Examination Security Agreement AJ<eev .fft7,4-L Ce- P"'"'S
- Form ES-201-3
- 1. Pre-Examination
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I acknowledge that I have acquired speGialized knowledge about the .NRC licensing examinations scheduled for the week(s) of4<{#-. 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 ifthe 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 iii cancellation of the examinations andlor 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 ;;!N(4i/ . 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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- 1. Pre-Examination . o </7"1'1lz0(I t:!
I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) ~q;.(.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 ... N NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered '>;I 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 indMdual 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 '"<:> N 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 wllJ immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security CIO CIO may have been compromised. . CIO co 0'1
- 2. Post*Examination
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. To the best of my knowll!ldge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered .....
during the weekes) of47-/('00/ . 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 TITLEI RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE .7( 1. ~IO ~ (<'\ij~ ~/Ciftr..J ~4..k'~ i;;f~ ________ 32.... ll.. !1: c.,h&. L I L 6.i;:;t:Jer: e,/ e&7 r; e..: D..n ~~
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4I N G'I IIJ Co ES*201 Examination Security Agreement Form ES-201-3
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- 1. Pre-Examination . ~;-/7'frO( /
\Q I acknowle<;lge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) 0 ~<Ui- as of the date VI of my signature. I agree that 1will not knowingly divulge any Information about these examinations to any persons who have not been authorized by the co NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered '>;I these licensing examinations from this date until completion of examination administration, except as specifically noted belQw and authorized by the NRC t (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 faQility licensee's procedures) and \Q IIJ . understand that violation of the conditions of this agreement may result In cancellation of the examinations and/or an enforcement action against me or <:>
\.III the facility licensee. J will Immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security co co may have been compromised. co co
- 2. Post-Examination '"tel
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To the best of my knowledge.* I did not divulge to any unauthorized persons any information concerning the NRC licenSing examinations administered (oj (oj during the week(s) of.1h*/f'l'l.r/ . From the date that I entered into this security agreement until the completion of examin~tlon administration, I did not ...
\D instruct, evaluate. or provide perfonnance feedback to those applicants who were administered these licensing examimitlons, except as sPeciflCally noted below and authorized by the NRC.
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ES*201 ____ __ _ Examination Security Agreement Form ES*201 M3 1. Pre-Examination t acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the weekes) of e ~ -/ of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not Deen uthorized by the as of the date 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 6-c(/b1 . 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 I RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE L.{~ -t::' '~,~ 412 -:::fI'S7::A2" $ . ::;~~ J/},"iJJJ ~ JI_ _ IA.-b 3. M _ ~. ~z I Z*ZI-/I LJr 4. S,"""V . ~ ? ~ /6-1/ 15'0 5. 7...... $r.~ ~~ /7/(/ -.2:..::L?-//
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- ES-401 Tier I Group RO Randomly Selected KiA 009G2.1.25 Record of Rejected KlAs Reason for Rejection Form ES-401-4 Ability to interpret reference materials, such as graphs, curves, tables, etc.
1/1 - Cannot write discriminating question with graphsl tables for small break LOCA. One graph for RXCP #1 seal leak rate and two tables for stopping SI pumps based on subcooling. Seal leak rate graph is to simple to create a discriminating question. Would have to evaluate student calculating subcooling which does not test KiA intent. Replace with 009G2.1.20 randomly selected from same generic area. RO 006K2.01 Knowledge of bus power supplies to the following: ECCS pumps 211 Oversampled pump power supplies 008K2.02 - Knowledge of bus power supplies to the following: CCW pump, including emergency backup) randomly selected 006K2.04 Knowledge of bus power supplies to the following: ESFAS-operated valves to replace 006K2.01 RO 010A4.01 Ability to manually operate and/or monitor in the control room: PZR spray 2/1 valve. PRZR spray malfunction sampled and tested by 027G2.2.22. Selected 010A4.02 Ability to manually operate and/or monitor in the control room: PZR Heaters. 010A4.03 Ability to manually operate and/or monitor in the control room: PZR spray valve. PORVand block valves not selected because PORV operation already randomly selected 008AA2.03 . RO 028AA2.01 Ability to determine and interpret the following as they apply to the 1/2 Pressurizer Level Control Malfunctions: PZR level indicators and alarms - Oversample PZR system and malfunctions. Randomly selected 037AA2.11 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: When to isolate one or more S/Gs RO 063A2.01 Ability to (a) predict the impacts of the following malfunctions or operations 2/1 on the D.C. Electrical System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those . malfunctions or operations: Grounds. Kewaunee Power Station does not have operations procedures to correct, control or mitigate the consequences of grounds. Kewaunee operations procedures identify the grounds. Randomly selected replacement KiA from K4, A4, and Generic in 063 because these categories could be increased by one and still maintain the balance of the categories. Selected 063K4.01 - Knowledge of D.C. Electrical System design feature(s) and/or interlock(s) which provide for the following: Manual/automatic transfers of control RO 076A2.02 Ability to (a) predict the impacts of the following malfunctions or operations 211 on the SWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure. KiA duplicates the information for 076G2.4.4 that was selected: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures. Re-selected 012A2.02 - Ability to (a) predict the impacts of the following 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: Loss of Instrument Power
- ES-401, Page 27 of 33 KPS-ES401-4-S-L-01142011-088
- ES-401 RO 1/1 054AK3.05 Record of Rejected KlAs Form ES-401-4 Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): HPI/PORV cycling upon total feedwater loss replaced due to oversampling of PORV. Replaced 054AK3.04 Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Actions contained in EOPs for loss of MFW4.4/4.6 RO 008AA2.03 Ability to determine and interpret the following as they apply to the 1/1 Pressurizer Vapor Space Accident: PORV position indicators and acoustic monitors replace due to oversampling of the PORV. Reselected 008A2.015 - Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: ESF control board, valve controls, and indicators 3.9/4.2 SRO G2.3.6 Ability to approve release permits. Rejected performing approval of Generic release permit for ADMIN JPM. Reselected 2.3.11 Radiological Controls:
Ability to control radiation releases. 4.3 SRO 057AA2.07 Ability to determine and interpret the following as they apply to the Loss of 1/1 Vital AC Instrument Bus: Valve indicator of charging pump suction valve from RWST. Rejected because the valve indication for Charging pump suction from the RWST is powered from Bus 5 not the instrument bus. Replaced with 057AA2.15 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: That a loss of ac has occurred SRO IMP 4.1 SRO 1/2 060G2.1.32 Accidental Gaseous Radwaste Rei: Ability to explain and apply system limits and precautions. Asking question about venting containment in KIA 103G2.4.30. Scenario for operating exam contains LOCA with failure of containment isolation valves. Failed to develop an operationally valid question at the SRO level for accidental gaseous radwaste release which does not conflict with other areas of the exam. Reselected 032 G 2.1.32 Loss of Source Range: Ability to explain and apply system limits and precautions SRO IMP 4.0 SR02/2 068A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation. SRO IMP 3.3. Administering JPM for approval of a release permit. Scenario for operating exam has failure of isolation valves for a high radiation condition. Question for 073A4.02 on RO exam deals with the interrelation between isolation of SG blowdown valves and radiation monitors. Failed to develop an operationally valid question at the SRO level that does not conflict with other areas of the exam. Reselected 041A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the SDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Steam valve stuck open. SRO IMP 3.9 SRO 1/2 003AA2.05 Ability to determine and interpret the following as they apply to the Dropped Control Rod: Interpretation of computer in-core TC map for dropped rod location. Not able to create SRO only question with interpretation of CET MAP. Reselected 076AA2.02 - Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity: Corrective actions required for high fission product activity in RCS
- ES-401, Page 27 of 33 KPS-ES401-4-S-L-01142011-088
- ES-401 SRO 2/2 029G2.1.32 Record of Rejected KlAs Form ES-401-4 Containment Purge: Ability to explain and apply system limits and precautions. Rejected question 15 SRO, cover Containment. Tested in RO question 59. Replaced with 056G2.1.32 - Ability to explain and apply*
system limits and precautions. R02l1 005K3.05 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: ECCS. Oversampled malfunctions affecting ECCS and RHR components. Replaced with 039K3.05 Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: RCS SRO 2/1 103G2.4.30 Knowledge of events related to system operation/status that must be reported to intemal organizations or external agencies, such as the State, the NRC, or the transmission system operator. - Rejected after submittal for no credible question with application to containment other EALs which are tested in other areas of the Exam. Re-selected 062G2.4.30. Also one stated for reason for rejection 029G.1.32 was that this question also covered containment. Containment is still tested in question 59 of RO portion of the written exam
- ES-401, Page 27 of 33 KPS-ES401-4-S-L-01142011-088
Kewaunee Power Station Random Generation Technique and KIA Suppression Random Generation Technique
- 1. The technique for generating the written examination outline was similar to that described in NUREG-1021, Rev. 9, Supp. 1, ES-401 Attachment 1.
- 2. Used die to randomly select starting point for K1, K2, K3, A1, A2, G. Example die role of 3 would start at K3.
- 3. Marked each selected emergency and abnormal evolution in sequential order from starting point advancing one each time. Example 007 randomly chosen to start at K3, then 009 would be A 1, 011 not selected, 015 would be A2, 022 would be a generic.
- 4. If a category was selected that did not have any KIA ~ 2.5, then a new category was selected randomly. To balance the category then one of the previous 3 emergency and abnormal evolutions were randomly selected to move to the category from the previous emergency and abnormal evolution. Example:
System A had no KlAs in category K1 ~ 2.5. System A category is randomly reselected for category A 1. System B, C, and 0 were already selected for category A 1. System 0 is randomly chosen for category K2.
- 5. The tokens used were numbered (poker) chips that corresponded to the topics and KlAs available, as appropriate. One individual selected the chip, unseen from a basket, after scrambling of the chips was performed.
KIA Suppression A review was made of applicable systems and systems 025, Ice Condenser, and 027, Containment Iodine Removal, were removed for selection since Kewaunee Power Station does not have these systems. Additionally, during system and EPE/APE selection, KlAs with a value less than 2.5 were reviewed and rejected (not placed in the basket for selection), if it was determined that no plant specific priority existed for the item. The generic KlAs that are NOT identified in NUREG-1 021, Rev. 9, Supp. 1, ES-401 D.1.b for inclusion in the Tier 1 and Tier 2 selection, were excluded from the selection process. Additionally as the KlAs identified in NUREG 1021, Rev. 9, Supp. 1, ES-401 D.1.b, "Single-unit facilities may also eliminate KlAs 2.2.3 and 2.2.4," were also excluded from the selection process. KPS-Selection-A-L-09302010-026
ES-403 Written Examination Grading Form ES-403-1 Quality Checklist I Facility: Kewaunee Date of Exam: 2115/2011 Exam Level: RO [g] SRO [g] I Initials Item Description a b c
- 1. Clean answer sheets copied before grading
~ .~ ~
- 2. Answer key changes and question deletions justified
/t//A jJfl 3.
and documented Applicants' scores checked for addition errors "I. (reviewers spot check >25% of examinations) (~ 1J:u ~ 4~ Grading for all borderline cases (80% +/- 2% overall and 70 or 80,
+/-
as applicable, 4% on the SRO-only) reviewed in detail rJIj ~ ~
- 5. All other failing examinations checked to ensure that grades are justified I(v/Il- ~A ~
- 6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants V uo ~
Printed Name I s;gnat~~ Date
- a. Author iJlku..t.l'.&i} J;J},f.e,.Jt;.r~- .:ti..61¢t{
- b. Facility Reviewer(*) ()OYJ(~ VI;::::. a D--- .,1-/6-)(.,11
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- c. NRC Chief Examiner{*) ~/I7/~/'
- d. NRC Supervisor(*)
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(*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. ES-403, Page 5 of 5
Dominion Energy Kewaunee, Inc. N490 Hwy 42, Kewaunee, \'(11 54216 Dominion Web Address: www.dom.com WITHHOLD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390 Regional Administrator, Region III FEB 17 2011 Serial No. 11-089
- u. S. Nuclear Regulatory Commission LlC/NW/RO 2443 Warrenville Road, Suite 210 Docket No.: 50-305 Lisle, IL 60532-4352 License No.: DPR-43 Attention: Mr. Dell McNeil DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION OPERATOR LICENSE POST EXAMINATION MATERIAL AND COMMENTS In accordance with the guidelines of NUREG-1 021, Revision 9, Supplement 1, ES-501, the identified post-examination material and the written examination facility comments are enclosed. Forms ES-201-3, "Examination Security Agreement," will be forwarded as soon as the required signatures are obtained. The enclosure to this letter contains confidential information, the disclosure of which would clearly constitute unwarranted invasion of personal privacy. Pursuant to 10 CFR 2.390(a)(6), Dominion Energy Kewaunee, Inc. requests that this letter be withheld from public disclosure. If you have questions or require additional information, please feel free to contact Mr. Dan Laing at 920-388-8691. Very truly yours, Ste e . cace Site Vice President, Kewaunee Power Station Enclosure Commitments made by this letter: NONE NOTICE: The enclosure to this letter contains confidential information. Upon separation from the enclosure, this letter is DECONTROLLED.
Serial No. 11-089 Page 2 of 2 cc: Without enclosure NRC Senior Resident Inspector Kewaunee Power Station Madison, WI 53707 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Serial No. 11-089 ENCLOSURE 1 OPERATOR LICENSE EXAMINATION WRITTEN EXAMINATION FACILITY COMMENTS
'$' GRADED WRIT"rEN EXAMINATIONS AND CLEAN COpy OF ANSWER SHEETS
- j'-- MASTER SRO EXAMINATION AND ANSWER KEY LIST OF QUESTIONS ASKED AND ANSWERS GIVEN DURING EXAM ADMINISTRATION STUDENT EXAM ITEM FEEDBACK AND RESPONSE WRITTEN EXAMINATION SEATING CHART WRITTEN EXAMINATION PERFORMANCE ANALYSIS INFORMATION WRITTEN EXAMINATION GRADING QUALITY CHECKLIST
.-; / ~. ! ! -!
KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
2011 POST-NRC WRITTEN EXAMINATION COMMENTS There were no post-written examination comments. Page 1 of 1
~ ITEM STATISTICS REPORT for 2011 ILT SRO As Given Test from 2011 ILT SRO As Given Scores Test form: 0 0 D Item Admins Type p Pts Avg E.T. 1:1 8 0 0 1 1 6 MCS 0.75 0.00 0.00 0.13 0.13 0.75 1.00 89.33 0.00 0.00 92.00 92.00 89.33
-0.333 - +0.218 +0.218 -0.333 1:2 8 0 0 7 0 1 MCS 0.88 0.00 0.00 0.88 0.00 0.13 1.00 89.14 0.00 0.00 89.14 0.00 96.00
-0.655 -0.655 - +0.655 1:3 8 0 0 0 8 MCS 1.00 0.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 0.00 90.00 1:4 8 0 0 1 0 7 MCS 0.88 0.00 0.00 0.13 0.00 0.88 1.00 89.71 0.00 0.00 92.00 0.00 89.71
-0.218 - +0.218 -0.218 1:5 8 0 1 0 7 MCS 0.88 0.00 0.13 0.00 0.88 1.00 90.29 0.00 88.00 0.00 90.29
+0.218 -0.218 - +0.218 1:6 8 0 1 0 6 1 MCS 0.75 0.00 0.13 0.00 0.75 0.13 1.00 91.33 0.00 88.00 0.00 91.33 84.00
+0.667 -0.218 - +0.667 -0.655 1:7 8 0 6 0 2 MCS 0.75 0.00 0.75 0.00 0.25 1.00 90.67 0.00 90.67 0.00 88.00
+0.333 - +0.333 -0.333 Wednesday, February 16, 20119:16:23 AM 1
I ITEM STATISTICS REPORT for 2011 ILT SRO As Given Testfrom 2011 ILT SRO As Given Scores
. Overall Omits A (True) B (False) C D Item Admins Type p Pts Avg E.T.
1:8 8 0 3 5 MeS 0.63 0.00 0.38 0.63 1.00 91.20 0.00 88.00 91.20
+0.447 -0.447 +0.447 1:9 8 0 0 0 0 8 MeS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 0.00 0.00 90.00 1:10 8 0 6 2 MeS 0.75 0.00 0.75 0.25 1.00 90.00 0.00 90.00 90.00
+0.000 +0.000 +0.000 1:11 8 0 0 8 MeS 1.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 90.00 1:12 8 0 0 7 0 1 MeS 0.88 0.00 0.00 0.88 0.00 0.13 1.00 89.71 0.00 0.00 89.71 0.00 92.00
-0.218 -0.218 +0.218 1:13 8 0 0 8 MeS 1.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 90.00 1: 14 8 o o o 7 MeS 0.88 0.00 0.00 0.00 0.88 0.13 1.00 90.29 0.00 0.00 0.00 90.29 88.00
+0.218 +0.218 -0.218 Wednesday, February 16,2011 9:16:23 AM 2
ITEM STATISTICS REPORT for 2011 ILT SRO As Given Test from 2011 ILT SRO As Given Scores Overall Omits A (True) B (False) C D Item Admins Type p Pts Avg E.T. 1:15 8 0 0 8 MCS 1.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 90.00 1:16 8 o o 8 MCS 1.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 90.00 1:17 8 o o 8 MCS 1.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 90.00 1:18 8 o 8 MCS 1.00 0.00 1.00 1.00 90.00 0.00 90.00 1:19 8 o 8 MCS 1.00 0.00 1.00 1.00 90.00 0.00 90.00 1:20 8 0 0 0 7 MCS 0.88 0.00 0.00 0.00 0.88 0.13 1.00 90.86 0.00 0.00 0.00 90.86 84.00
+0.655 +0.655 -0.655 1:21 8 0 7 0 1 MCS 0.88 0.00 0.88 0.00 0.13 1.00 90.29 0.00 90.29 0.00 88.00
+0.218 +0.218 -0.218 Wednesday, February 16, 2011 9:16:23 AM 3
ITEM STATISTICS REPORT for 2011 ILT SRO As Given Test from 2011 ILT SRO As Given Scores Overall Omits A (True) B (False) C D Item Admins Type p Pts Avg E.T. 1:22 8 0 8 MeS 1.00 0.00 1.00 1.00 90.00 0.00 90.00 1:23 8 o 8 MeS 1.00 0.00 1.00 1.00 90.00 0.00 90.00 1:24 8 0 0 2 6 MeS 0.75 0.00 0.00 0.25 0.75 1.00 91.33 0.00 0.00 86.00 91.33
+0.667 -0.667 +0.667 1:25 8 0 0 0 0 8 MeS l.00 0.00 0.00 0.00 0.00 1.00 1.00 90.00 0.00 0.00 0.00 0.00 90.00 Wednesday, February 16, 20119:16:23 AM 4
ITEM STATISTICS REPORT for 2011 ILT RO As Given Test from 2011 ILT RO As Given Scores Test form: 0 o Item Admins Type p Pts . Avg E.T. 1:1 10 0 0 0 10 MeS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:2 10 o o o 10 MeS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:3 10 o o o o 10 MeS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 1:4 10 0 0 0 9 1 MeS 0.90 0.00 0.00 0.00 0.90 0.10 1.00 87.70 0.00 0.00 0.00 87.70 84.00
+0.212 - +0.212 -0.212 1:5 10 0 0 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:6 10 o 10 MeS 1.00 0.00 1.00 1.00 87.33 0.00 87.33 1:7 10 o 2 6 2 MeS 0.60 0.00 0.20 0.60 0.20 1.00 88.00 0.00 86.67 88.00 86.00
+0.156 -0.064 +0.156 -0.127 Wednesday. February 16. 2011 6:25:22 AM 1
Item Admins Type p Pts Avg E.T. 1:8 10 0 a 10 MeS 1.00 0.00 0.00 1.00 LOO 87.33 0.00 0.00 87.33 1:9 10 0 9 0 Mes 0.90 0.00 0.90 0.00 0.10 1.00 88.15 0.00 88.15 .0.00 80.00
+0.466 +0.466 -0.466 1:10 10 0 9 0 1 MeS 0.90 0.00 0.90 0.00 0.10 LOO 88.15 0.00 88.15 0.00 80.00
+0.466 +0.466 -0.466 1:11 10 0 0 0 0 10 MeS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 1:12 10 0 9 0 1 MeS 0.90 0.00 0.90 0.00 0.10 1.00 87.41 0.00 87.41 0.00 86.67
+0.042 +0.042 -0.042 1:13 10 0 1 0 9 Mes 0.90 0.00 0.10 0.00 0.90 1.00 86.96 0.00 90.67 0.00 86.96
-0.212 +0.212 -0.212 1:14 10 0 0 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 Wednesday, February 16, 2011 6:25:22 AM 2
ITEM STATIS"neS REPORT for 2011 ILT ROAs Given Test from 2011 ILT RO As Given Scores Overall Omits A (True) B (False) C D Item Admins Type p Pts Avg E.T. 1:15 10 0 10 MCS LOO 0.00 1.00 LOO 87.33 0.00 87.33 1:16 10 0 3 6 MCS 0.60 0.00 0.30 0.10 0.60 LOO 89.33 0.00 82.22 90.67 89.33
+0.467 -0.638 +0.212 +0.467 1:17 ~. 10 0 0 10 MCS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:18 10 0 0 9 0 1 MCS 0.90 0.00 0.00 0.90 0.00 0.10 1.00 87.11 0.00 0.00 87.11 0.00 89.33
-0.127 -0.127 +0.127 1:19 10 0 1 1 0 8 MCS 0.80 0.00 0.10 0.10 0.00 0.80 LOO 87.17 0.00 86.67 89.33 0.00 87.17
-0.064 -0.042 +0.127 -0.064
,+~1:20 10 0
- ~,~"'
- l.~-~-_If;,,\-\.4.;M.ii:'~~~
1:21 10 0 8 2 MCS 0.80 0.00 0.80 0.20 1.00 87.83 0.00 87.83 85.33
+0.191 +0.191 -0.191 Wednesday, February 16, 2011 6:25:22 AM 3
ITEM STATISTICS REPORT
. for 2011 ILT RO As Given Test from 2011 ILT Item Admins Type p Pts Avg E.T.
1:22 10 0 0 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:23 10 0 0 9 MeS 0.90 0.00 0.10 0.00 0.90 1.00 88.00 0.00 81.33 0.00 88.00
+0.382 -0.382 +0.382 1:24 10 0 0 0 10 MeS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:25 10 o o 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:26 10 0 0 2 8 MeS 0.80 0.00 0.00 0.20 0.80 1.00 88.67 0.00 0.00 82.00 88.67
+0.509 -0.509 +0.509 1:27 10 0 0 0 9 MeS 0.90 0.00 0.00 0.10 0.00 0.90 1.00 88.00 0.00 0.00 81.33 0.00 88.00
+0.382 -0.382 +0.382 1:28 10 0 0 0 0 10 MeS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 Wednesday, February 16, 2011 6:25:22 AM 4
ITEM STA'"ISTICS REPORT for 2011 ILT RO As Given Test from 2011 ILT RO As Given Scores Overall Omit$ A (True) B(False) , C D Item Admins Type p Pts Avg E.T. 1:29 10 0 0 9 1 MCS 0.90 0.00 0.00 0.90 0.10 1.00 87.70 0.00 0.00 87.70 84.00
+0.212 +0.212 -0.212 1:30 10 0 0 10 MCS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:31 10 0 0 I 2 7 MCS 0.70 0.00 0.00 0.10 0.20 0.70 1.00 90.10 0.00 0.00 81.33 80.67 90.10
+0.805 -0.382 -0.636 +0.805 1:32 10 0 9 MCS 0.90 0.00 0.90 0.10 1.00 88.15 0.00 88.15 80.00
+0.466 +0.466 -0.466 1:33 10 0 10 MCS 1.00 0.00 1.00 1.00 87.33 0.00 87.33 1:34 10 o o o o 10 MCS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 1:35 10 o o 9 MCS 0.90 0.00 0.00 0.90 0.10 1.00 86.96 0.00 0.00 86.96 90.67
-0.212 -0.212 +0.212 Wednesday, February 16, 2011 6:25:22 AM 5
Item Type p Pts Avg E.T. 1:36 10 . 0 0 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:37 10 o o 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:38 10 o o 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:39 10 o o 10 MeS 1.00 0.00 0.00 1.00 LOO 87.33 0.00 0.00 87.33 1:40 10 o 10 Mes 1.00 0.00 1.00 1.00 87.33 0.00 87.33 1:41 10 027 o 1 MeS 0.70 0.00 0.20 0.70 0.00 0.10 LOO 87.24 0.00. 86.00 87.24 0.00 90.67
-0.028 -0.127 -0.028 - +0.212 Wednesday, February 16, 2011 6:25:22 AM 6
ITEM STATISTICS REPORT for 2011 ILT RO As Given Test from 2011 ILT RO As Given Scores Overall Omits A (True) B (False} C D Item Admins Type p Pts Avg E.T. 1:43 10 0 10 MeS 1.00 0.00 1.00 1.00 87.33 0.00 87.33 1:44 10 0 0 9 MeS 0.90 0.00 0.10 0.00 0.90 1.00 88.00 0.00 81.33 0.00 88.00
+0.382 -0.382 - +0.382 1:45 10 0 0 0 0 10 MeS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 1:46 10 o o o 10 MeS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:47 10 0 1 0 1 8 MeS 0.80 0.00 0.10 0.00 0.10 0.80 1.00 87.67 0.00 81.33 0.00 90.67 87.67
+0.127 -0.382 +0.212 +0.127 1:48 10 0 0 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:49 10 o lO MeS 1.00 0.00 1.00 1.00 87.33 0.00 87.33 Wednesday, February 16. 2011 6:25:22 AM 7
ITEM STATISTICS REPORT for 2011 ILT RO As Given Test from 2011 ILT RO As Given Scores
~
Overall Omits A (True) B(False) '" C' D ,-. I, Item Admins Type p Pts Avg E.T. 1:50 10 0 0 0 10 MeS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:51 10 0 6 3 0 MeS 0.60 0.00 0.60 0.30 0.00 0.10 1.00 88.67 0.00 88.67 82.67 0.00 93.33
+0.312 +0.312 -0.583 +0.382 1:52 10 0 0 10 MeS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 1:53 10 o o o o 10 MeS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 1:54 10 o 10 MeS 1.00 0.00 1.00 1.00 87.33 0.00 87.33 1:55 10 o o o 9 MeS 0.90 0.00 0.10 0.00 0..00 0.90 1.00 87.70 0.00 84.00 0.00 0.00 87.70
+0.212 -0.212 +0.212
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7 Wednesday, February 16,2011 6:25:22 AM 8
ITEM STATISTICS REPORT for 2011 ILT RO As Given Test from 2011 ILT RO As Given Scores Overall Omits A (Tr~e) B (False) <,\ C D Item Admins Type p Pts Avg E.T. 1:57 10 0 0 9 1 MCS 0.90 0.00 0.00 0.90 0.10 LOO 86.96 0.00 0.00 86.96 90.67
-0.212 -0.212 +0.212 1:58 10 0 0 0 10 MCS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:59 10 0 1 0 8 1 MCS 0.80 0.00 0.10 0.00 0.80 0.10 1.00 87.83 0.00 81.33 0.00 87.83 89.33
+0.191 -0.382 +0.191 +0.127 1:60 10 0 2 1 6 MCS 0.60 0.00 0.10 0.20 0.10 0.60 1.00 88.00 0.00 86.67 82.67 93.33 88.00
+0.156 -0.042 -0.445 +0.382 +0.156 1:61 10 0 0 1 7 2 MCS 0.70 0.00 0.00 0.10 0.70 0.20 1.00 88.76 0.00 0.00 90.67 88.76 80.67
+0.416 +0.212 +0.416 -0.636 1:62 10 0 0 0 0 10 MCS 1.00 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 1:63 10 o o 10 MCS 1.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 87.33 Wednesday, February 16, 2011 6:25:22 AM 9
ITEM STATISTICS REPORT for 2011 ILT RO As Given Test from 2011 ILT RO As Given Scores Item Admins Type p Pts Avg E.T. 1:64 10 0 1 9 MeS 0.90 0.00 0.10 0.90 1.00 SS.OO 0.00 81.33 88.00
+0.382 -0.382 +0.382 1:65 10 0 9 0 0 1 MeS 0.90 0.00 0.90 0.00 0.00 0.10 1.00 88.15 0.00 88.15 0.00 0.00 SO.OO
+0.466 - +0.466 -0.466 1:67 10 0 o o o 10 MeS 1.00* 0.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 0.00 87.33 1:69 10 0 0 3 7 MeS 0.70 0.00 0.00 0.30 0.70 1.00 88.95 0.00 0.00 83.56 88.95
+0.472 -0.472 +0.472 1:70 10 0 1 0 9 MeS 0.90 0.00 0.10 0.00 0.90 1.00 88.00 0.00 S1.33 0.00 88.00
+0.382 -0.382 +0.382 Wednesday, February 16,2011 6:25:22 AM 10
rrEM STATISTICS REPORT for 2011 ILT RO As Given Test from 2011 ILT RO As Given Scores Overall . Omits A (True)B(False) C D Item Admins Type p Pts Avg E.T. 1:71 10 0 0 0 10 MCS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:72 10 o o o 10 MCS 1.00 0.00 0.00 0.00 1.00 1.00 87.33 0.00 0.00 0.00 87.33 1:73 10 0 0 9 MCS 0.90 0.00 0.10 0.00 0.90 1.00 87.11 0.00 89.33 0.00 87.11
-0.127 - +0.127 -0.127 1:74 10 0 6 0 0 4 MCS 0.60 0.00 0.60 0.00 0.00 0.40 1.00 86.89 0.00 86.89 0.00 0.00 88.00
-0.104 -0.104 - +0.104 1:75 10 0 2 1 7 MCS 0.70 0.00 0.20 0.10 0.70 1.00 89.52 0.00 82.67 81.33 89.52
+0.638 -0.445 -0.382 +0.638 Wednesday, February 16, 2011 6:25:22 AM 11
ILT Written Exam Seating Chart (SRO) I I (RO) I I (SRO) I I I ~ (SRO) (RO) (SRO) I I (SRO) I I (SRO) I G (SRO) I I (SRO). I " 0
, 2011 NRC WRITTEN EXAMINATION ITEM REVIEW DETAILED
SUMMARY
ROI-06-EX-WRT RO Written Exam
- 20. Per AOP-RC-004, "Steam Generator Tube Leak", which of the following is the LARGEST stable RCS to Steam Generator Leak rate which does NOT require isolation of the leaking Steam Generator?
(Stable is defined as a constant rate for greater than 60 minutes) A stable leak rate of ... A. 10 gallons per day. B. 25 gallons per day. C. 80 gallons per day. D. 150 gallons per day. ANSWER: C Activities required for the SG tube leak are identified based upon the (Chemistry) Action Levels as identified in AOP-RC-004. The table below is from section 1.2.2 of AOP-RC 004 and the Action Levels are also incorporated into specific operator actions within the body of the procedure. Action Level PIS Leak Rate Shutdown Time Normal Operation <5gpd N/A Increased Monitoring ~5 to <30 gpd N/A Action Level 1 ~30 to <75 gpd N/A Be in [CTS] Hot Shutdown
~75 to <100 gpd
- Action Level 2 [ITS] Mode 3, within sustained for 1 hour 24 hours Reduce Power to <50%
within 1 hour and be in
- Action Level 3 ~100 gpd [CTS] Hot Shutdown
[ITS] Mode 3, within an additional 2 hours All leak rates are for anyone Steam Generator. All leak rates are in gallons based on room temperature measurements Page 1 of6
2011 NRC WRITTEN EXAMINATION ITEM REVIEW DETAILED
SUMMARY
Isolation of the leaking SG per AOP-RC-004 will only occur if ACTION LEVEL 3 is entered and plant shutdown is directed using AOP-RC-'004 and AOP-GEN-002, Rapid Plant Shutdown. The associated leak rate for ACTION LEVEL 3 is ~ 100 gpd. If a shutdown is required due to a leak at a lower rate (ACTION LEVEL 2), AOP-RC-004 is exited by direction and the shutdown is accomplished using by OP-KW-GOP-206, Shutdown from Full Power To 35% Power, and OP-KW-GOP-205, Shutdown from 35% Power to [CTS] HOT STANDBY [ITS] MODE 3. This procedural flow path does not direct isolation of the leaking SG. The lesson plan (and associated PowerPoint presentation) for SG Tube Leak Abnormal, R04-03-LPD07, cover the actions for each of the ACTION LEVELS. The High Level Summary covers for ACTION LEVEL 2 that a normal plant shutdown to HOT SHUTDOWN is required within 24 hours using OP-KW-GOP-206, 205 and 204 as guiding documents for the shutdown. For ACTION LEVEL 3 a prompt and controlled shutdown is initiated using AOP-GEN-002. Furthermore, the High Level Summary states that in AOP-RC-004, the crew will identify and isolate the leaking SG. Candidates responded that the most selected incorrect answer was chosen based upon the conditions that a plant shutdown is required.
- 42. Given the following:
- The unit is in MODE 3.
- SP-23-100A, "Train A Containment Spray Pump and Valve Test - 1ST", is in progress.
- After starting Internal Containment Spray (ICS) Pump 'A', but before aligning ICS train 'A' for the full flow test, a Design Basis LOCA occurs.
- The crew enters the EOP network.
- Containment pressure is 25 psig and rising at the completion of immediate actions.
What is the status of the Internal Containment Spray Train 'A'? (SP-23-100A is provided as a reference) ICS pump 'A' is providing ... A. flow to ICS ring header 'A'. B. recirculation flow to the Refueling Water Storage Tank. C. no flow due to load shed and will start on the sequencer. D. no flow through the system and operating at shutoff head. Page 2 of 6
2011 NRC WRITTEN EXAMINATION ITEM REVIEW DETAILED
SUMMARY
ANSWER: D The given conditions place the Train A ICS in a condition with its discharge valve to containment closed (ICS-7A) and the normal recirculation valves to the RWST (ICS-201 and ICS-202) open. The full-flow test line is isolated with ICS-200A yet to be opened. ICS-201 and ICS-202 receive a close signal from the Containment Isolation Train A and Train B signal, respectively, when SI actuates. SI actuates at 3.6 psig in containment. A copy of SP-23-1 OOA was provided with the question. This should enable the candidate to determine the alignment of containment spray train. The lesson plan (and associated Powerpoint presentation) R02-01-LP023 for Internal Containment Spray covers the containment spray flow paths including the recirculation / test line. The lesson plan details that the full flow test lines are normally isolated by ICS-200A and ICS-200B. The lesson plan also covers the valves ICS-201 and ICS-202 and the conditions affecting the position of these valves. The lesson plan details that these valves will close, in AUTO, upon a CI signal and upon ICS actuation. Candidates responded that the most selected incorrect answer was chosen because the isolation of the recirculation valves was not recall at the time.
- 56. Which of the following lists a criteria that the 400 ft3 steam volume and 600 ft3 water volume of the Pressurizer are designed to meet?
A. Keep the Pressurizer heaters covered during a 10% step load increase. B. Prevent a reactor trip due to Pressurizer level with a 50% ramped load reduction and Steam Dumps NOT available. C. During a reactor trip Pressurizer level will remain greater than 21 % assuming steam dumps and/or Steam Generator relief valves lift as designed. D. The pressure surge from a 30% ramped load reduction with only automatic Rod Control operation will not exceed the design capacity of both Pressurizer Safeties. ANSWER A In the USAR the pressurizer design characteristics and cyclic loads are described. In section 4.1.5.3 for a step load increase and decrease of 10%, the RCS design as related to this cyclic load is discussed. This section describes for the 10% step load increase, the (primary system) decreasing pressure transient is reversed by actuation of the pressurizer heaters and eventually the system pressure is restored to its normal value. Page 3 of6
2011 NRC WRITTEN EXAMINATION ITEM REVIEW DETAILED
SUMMARY
The lesson plan (and associated PowerPoint presentation) R02-01-LP36B for the Pressurizer and Pressurizer Relief Tank covers the design characteristics for the pressurizer including the pressurizer volume. The lesson plan states that sufficient water volume is maintained to keep heaters covered during 10% step load increase. Candidates responded that they failed to recall the correct condition at the time.
- 66. Given the following:
- The unit was operating at 100% Rated Thermal Power when the reactor tripped.
- The crew has completed the required steps of E-O, "Reactor Trip or Safety Injection" and transitioned to ES-0.1, "Reactor Trip Response
- Main Steam Isolation Valves are OPEN
- The Balance of Plant Operator reports:
- MS-312A-1, Gland Seal Steam to MSRSA1 &SA2 ReliefVlvs is OPEN
- MS-312B-1, Gland Seal Steam to MSR B1 & B2 ReliefVlvs is CLOSED What actions will be required to mitigate this?
A Condenser steam dump valves will be used for controlling RCS temperature to 350°F. B. 'A' Train Condenser Steam Dump valves are still available for RCS temperature control. C. Main Steam Isolation Valves will be closed to reduce the excessive cooldown of RCS temperature. D. Steam Generator PORVs or Atmospheric Steam Dump valves will be used to control RCS temperature. ANSWER: D The question was based upon plant operating experience. With either MS-312A-1 or MS-312B-1 closed following a reactor trip, air inleakage into the secondary system resulting in lowering condenser vacuum. The loss of condenser vacuum will affect condenser steam dump operations. If condenser steam dumps are not available for maintaining primary system temperatures, the SG PORVs or atmospheric steam dumps are the proceduralized alternatives for cooling. Page 4 of 6
2011 NRC WRITTEN EXAMINATION ITEM REVIEW DETAILED
SUMMARY
The lesson plan (and associated PowerPoint presentation) R02-05-LP06C describes the function of the steam dump control system, including the interlocks required for operation of the condenser steam dumps. The lesson plan also covers the atmospheric steam dump operations. Operating events associated with the steam dump system is also discussed and the application of lessons learned applied to Kewaunee by the students. Candidates stated they failed to identify the correct affect for the valve position at the time.
- 68. Which of the following lists components that can ALL be operated from the Dedicated Shutdown Panel?
A. Fuel Oil Transfer Pump 'N CVC-15, CHRG Line To PRZR Aux Spray MS-1A, Main Steam HDR 1A Isolation Valve B. Charging Pump 'A' Battery Room Fan Coil Unit 'A' LD-13A, Reactor Coolant Filter Bypass Valve C. RHR pump 'A' BT-3A, STM GEN 1A Blowdown Iso I LD-4B, Regen HX LTDN OTLT ORIF 1B Isol D. Containment Fan Coil Unit 'B' Service Water Pump 1B 1 RHR-11, RHR Return to Loop B Cold Leg Iso I ANSWER: A Only one selection listed components that are all located on the DSP. Fuel Oil Transfer Pump A LOCAL/REMOTE switch and START/STOP control switch are on the DSP. CVC-15 LOCAL/REMOTE switch and CLOSE/OPEN control switch are on the DSP. MS-1A key-operated NORMALITRIP control switch is located on the DSP. Components NOT located on the DSP include: Charging Pump A; BT-3A; SW Pump 1B1. The components and controls operated form the DSP are covered in the lesson plans for the specific systems. The lesson plan (and associated PowerPoint presentation) R02-03-LP42A describes the controls on the DSP for the 1A DG Fuel Oil Transfer Pump. The lesson plan (and associated PowerPoint presentation) R02-05-LP06C describes the controls for CVCS at the DSP, including Aux Spray Valve, CVC-15. The lesson plan (and associated PowerPoint presentation) R02-02-LP06A for the main steam system describes the DSP switch for the MSIV, MS-1A. Page 50f6
2011 NRC WRITTEN EXAMINATION ITEM REVIEW DETAILED
SUMMARY
Candidates responded that the most selected incorrect answer was chosen because they failed to remember that the SG Slowdown Isolation Valve is Train S powered. Page 6 of6
~---
Clarifications During The Administration of the Kewaunee 2011 Initial License Written Exam on 2/15/2011. (Pen and Ink Changes)
Question 51: Added a clarification to the second condition in the question stem to state that the turbine is latched. The clarification was added based on a question from a student. Original Question
- 51. Given the following:
- The unit is at 8% NI power, performing a startup after a refueling outage.
Preparations to begin rolling the Main Turbine are in progress.
- The Balance Of Plant operator identifies that P-486, Turbine Impulse Pressure Instrument, is reading off scale high.
Shortly after the failure of P-486, RXCP A Trips.
- Annunciator 47012-J, RCS Loop A Flow Low, is LIT.
What is the expected Plant AND Operator Response? Plant Response Operator Response A. Permissive P-7 will not The operators will manually trip the reactor cause a reactor to trip B. Permissive P-8 will cause The operators will perform the a reactor trip immediate actions for a reactor trip C. Permissive P-10 will not The operators will perform a normal cause a reactor trip reactor shutdown D. Permissive P-13 will cause The operators will manually trip the turbine a reactor trip
Question with clarification
- 51. Given the following:
- The unit is at 8% NI power, performing a startup after a refueling outage.
- The Turbine is latched and preparations to begin rolling the Main Turbine are in progress.
- The Balance Of Plant operator identifies that P-486, Turbine Impulse Pressure Instrument, is reading off scale high.
- Shortly after the failure of P-486, RXCP A Trips.
- Annunciator 47012-J, RCS Loop A Flow Low, is LIT.
What is the expected Plant AND Operator Response? Plant Response Operator Response A. Permissive P-7 will not The operators will manually trip the reactor cause a reactor to trip B. Permissive P-8 will cause The operators will perform the a reactor trip immediate actions for a reactor trip C. Permissive P-10 will not The operators will perform a normal cause a reactor trip reactor shutdown D. Permissive P-13 will cause The operators will manually trip the turbine a reactor trip
Question 66 A typographical error in the stem of the question, the noun name for MS-312A-1 referred to MSR B1 and B2, should have been MSR A1 and A2. Correct the error. Original Question 66
- 66. Given the following:
- The unit was operating at 100% Rated Thermal Power when the reactor tripped.
- The crew has completed the required steps of E-O, "Reactor Trip or Safety Injection" and transitioned to ES-O.1, "Reactor Trip Response
- Main Steam Isolation Valves are OPEN
- The Balance of Plant Operator reports:
- MS-312A-1, Gland Seal Steam to MSR B1 & B2 Relief Vlvs is OPEN
- MS-312B-1, Gland Seal Steam to MSR B1 & B2 ReliefVlvs is CLOSED What actions will be required to mitigate this?
A. Condenser steam dump valves will be used for controlling RCS temperature to 350°F. B. 'A' Train Condenser Steam Dump valves are still available for RCS temperature control. C. Main Steam Isolation Valves will be closed to reduce the excessive cooldown of RCS temperature. D. Steam Generator PORVs or Atmospheric Steam Dump valves will be used to control RCS temperature.
Question 66 with typo corrected:
- 66. Given the following:
- The unit was operating at 100% Rated Thermal Power when the reactor tripped.
- The crew has completed the required steps of E-O, "Reactor Trip or Safety Injection" and transitioned to ES-0.1, "Reactor Trip Response
- Main Steam Isolation Valves are OPEN
- The Balance of Plant Operator reports:
- MS-312A-1, Gland Seal Steam to MSR A 1 & A2 Relief Vlvs is OPEN
- MS-312B-1, Gland Seal Steam to MSR 81 & 82 Relief Vlvs is CLOSED What actions will be required to mitigate this?
A. Condenser steam dump valves will be used for controlling RCS temperature to 350°F. B. 'A' Train Condenser Steam Dump valves are still available for RCS temperature control. C. Main Steam Isolation Valves will be closed to reduce the excessive cooldown of RCS temperature. D. Steam Generator PORVs or Atmospheric Steam Dump valves will be used to control RCS temperature.}}