Text

2009 Initial Examination 05000327-09-301 and 05000328-09-301, Final Administrative Documents
	ML090710673
Person / Time
Site:	Sequoyah
Issue date:	02/04/2009
From:	; NRC/RGN-II
To:	;
References
	IR-09-301
	Download: ML090710673 (76)
	v • d • e

{{#Wiki_filter:ES-201, Rev. 9E Examination Preparation Checklist Form ES-201-1 Examinations Developed by: Facility: Target Date* Sequoyah Task Description (Reference) Date of Examination: January 2009 NRC Written / Operating Test Chief Examiner's Initials -180 -120 -120 -120 [-90] {-75} {-70} {-45} -30 -14 -14 -14 -7 -7 -7 -7 1. Examination administration date confmned (C.I.a; C.2.a and b) 2. NRC examiners and facility contact assigned (C.I.d; C.2.e) 3. Facility contact briefed on security and other requirements (C.2.c) 4. Corporate notification letter sent (C.2.d) [5. Reference material due (C. I.e; C.3.c; Attachment 2)] 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-I's, ES-401-I/2, ES-401-3, and ES-401-4, as applicable (C. I.e and f; C.3.d) {7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.I.e, f, g and h; C.3.d) 9. Preliminary license applications (NRC Form 398's) due (C. I.!; C.2.g; ES-202) 10. Final license applications due and Form ES-201-4 prepared (C. I.!; C.2.i; ES-202) 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) 12. Examinations reviewed with facility licensee (C.I.j; C.2.f and h; C.3.g) 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h) 14. Final applications reviewed; 1 or 2 (if>10) applications audited to confmn qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 4; ES-202, C.2.e; ES-204) 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k) 16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i) RSB RSB RSB RSB RSB RSB RSB RSB RSB RSB RSB RSB RSB RSB RSB RSB

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 Facility: Sequoyah 1 &2 IA Examination Outline Quality Checklist Date of Examination: 1/20/2009 Form ES-201-2 Item 1. W R I T T E N 2. S I M U L A To R 3. W / T 4. G E N E R A L Task Description a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KIA categories are appropriately sampled. c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. d. Assess whether the justifications for deselected or rejected KIA statements are appropriate. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients. b. Assess whether there are enough scenario sets (and spares) to test the projected number 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 from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D. 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 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 on the form. b. Verify that the administrative outline meets the criteria specified on Form ES-301-1: (1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. d. Check for duplication and overlap among exam sections. e. Check the entire exam for balance of coverage. f. Assess whether the exam fits the appropriate job level (RO or SRO). Initials a. Author b. Facility Reviewer (*) c. NRC Chief Examiner (#) d. NRC Supervisor Note:

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

Not applicable for NRC-prepared examination outlines

ES*'201, Ex,amination 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 1/26-2106/09 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 Tothe 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 . 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. SIGNATURE (2) DATE NOTE JOB TITLE / RESPONSIBILITY R-'- i ~, " -l .,"!'"' -. - j ,~.'- -

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ES*201 1. Pre-Examination Examination Security Agreement Form ES*201*3 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 1/26-2/06/09 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)edge, I did not divulge to any unauthorized persons ,any information concerning the NRC licensing examinations administered during the week(s) of /~c,~i/lfh9 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. JOB TITLE / RESPONSIBILITY ES-201, Page 27 of 28

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) ) t ~. .') ES*20*j Examination Security Agreement Form ES*201..:3 1 ~ Pre-ExamInaiion I acknowledge Ihal rhave acquired speGializ.ed knowledge about Ihe NRC licensing exanlillalions schedu~ed ror the week(s) of 1'28*2/06100 as of lbe date ofmy sfgnalure. 1agree that I will notknowingly divulge anv infonnation abolit these examrnaliQns to any penH1J1& who have not been authoT~zed by tlle NRC c:h;efexamlner. I understand lhall aID nollO Instruct. 6varuate. or provide pefformance feedback La those app1ican15 schedufed to be administered lhes91icensing examinations fram this dale unlil oompret~on of examtnatinn adlnin'slfatfonr exr-,.aptas speclrlCalry noted bela" and aulhoriz:ed by the NRC (e.g., actlng as a s'mulator booth operator or communicator is acoepla b~e If the Individual does oot sekJct 1he lraJning ~onlent or provide direcl or IndirecL reedbac1t}~ FoP't.hermoret l am aware of the physica~ secLWily Rleasures and requiremenls (as documented in the facUity.l'censee 1s procedures) and understand 1hat vlD1ation of 100 conditions oftfl(s agreement may result in canool1atfon of the exarninatbns and/or. an enforcement action against me or file fatUily lioonsee~ I will ;mmed'ately report to faccnty Jn8.nagem8ntor the NRC chief examrner any indfcatlons Of suggesUons that exal1inatlon security may bave bee~ compromised.. . 2.. Post*Examlnation To the best: of my kno~ed~h I did not divulge to any unauthoTlz:ed persons.any information conoeming 1he NRC tioanslng examinations administered during the week(s.} of* tj.. df From th.e dale thai I entered into th~s security agreement untilloo completEon 1)f exa M~naliQn adminis1ratfDR ,I I did not. insfroctJ eva[uate.. Ofpro'Jide performance feedback [0 those applicants who wer~ administered lbese Ifcensing exarnEnatfons~except as specifical~Vno-ted below and aulhorfzed by lhe NRC. '11m IJj 1 lSI ITI -I I\\j lSI lSI 1*.0 P lSI 01 I-.:'a. -jo-i I)r "1J lSI ftJ JOB TIllE IRESPONSIBllllY IJ lSI I\\.) ........ lSI rtJ E5-201, Page 27 of 28

ES-201 1. Pre-Examination Examination Secu.rity Agreement Form ES-201-3 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 1/26-2/06/09 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 notselect 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 kno~led~) I did not divulge to any unauthorized persons ,any information concerning the NRC licensing examinations administered during the week(s) ofY(O ""' Yif!o 9From 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 NA 44~rl~qt-{ / ~v#('t!vV us/seo ., Ad /2 r)_ uo/~O ~b W5/5'£// 1J.sJs~o-'slA ,f'1-1rr ~ /1. tirl\\l4G,,~ Ops---S tJce.1J~-~ ~-te~J..el'"'\\-\\- ~D ' flo SRo*

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\\. ( ( \\ ackno"'Jledge lhat I have acquired specialized knowledge about the NRC 'rceflsfflg examinations scl1eduted fOllhe week(s) of 1/25*2106100 as of the date of my signalwe. I agree that Jwill not knowingly di\\lfllge any information abDul1h~se examinalions to arlY persons '}Jho have not been aU!horized by the NRC chief exarnlner. r undersfantl that I am n6tlo insfruct!! evaJuall3;t or provide performanoo resdbaC'J( to those appUc.anlS schEJdufed &0 be administered these licensjn,g e)(amh"laUons from this d~le UrlUr c.ompletlon ofe.xamination admlnrslraUonlt 6}(cepl as speciflcaJty ooted below and authorized by uis NRC 'e,g., acting as a simuJalcr booth operator or communicator fS accep(abre jflhe lndivJduaf does nol select the 1ramillg content or pro\\llid~ djmcl or indirect feedback). FurthermoreJ ram al.vare orlhe physicaJ sec-urity measures and requirements (as documented in the faclUlylfcensee's procedures) and undars&and that viofation or theoondilions of Ihis"agreemenl may resuJl rn canceflation or the: eXBJninarions and/or an enforcement action againstme or 1he facility Hcens-ee. J wUI fmmedJalely reporllo fadmymanagemenl or the NRC chref examinerany fndfcaUons cr suggesUans fhat examjnauaR security ms'Y have been compromised. -c-I D.- E([ 00 Ii)

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ES-201 1. Pre-Examination Examination Security Agreement Form ES-201-3 I acknowledge that Ihave acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 1/26-2/06/09 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 acceptabl.e if the individual does not select the training content or provide direct or indirect feedback). Furthermore, lam 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) off{o-¥¢9. From the date that I entered into this security agreement until the completion of examination administration,1 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 'j SIGNAT~RE(2) DATE NOTE 1. CIt LJl'tkes .D~ S~efBA- ~~t. <: tie()etJ.'~tt~ ~ ;:.~ ~Aft1_ 2. Chd5 f;.. ~~..Jr,-b. .. P[;tR~~e,.. j Q ~e~ 3. OG- S~ f

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IA ES-301 Admi*nistrative Topics O.utline Form ES-301-1 Facility: Sequovah 1 & 2 Examination Level: ROliT SRO D Date of Examination: 1/2009 Operating Test Number: NRC Administrative Topic (see Note) Conduct of Operations* Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Type Code* M,R D,R N,S M,R Describe activity to be performed 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. 2.9* / 3.9 JP*M: Evaluate Overtime* Requirements 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.3 / 4.4 JPM: Calculate Manual Makeup to the Volume Control Tank (JPM 005) 2.2.12 Knowledge of surveillance procedures. 3.7/4.1 JPM: Perform Monthly Shift Log 0-SI-OPS-OOO~003.M 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5 / 3.6 JPM: 2A RHR Heat Exchanger Radiological Work Permit and Survey Map Usage (JPM 180) N/A 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 (2= 1) (P)revious 2 exams (=:; 1; randomly selected)

AL RO Admin JPM Summary A1a Determine when conditions exist that requires approval to exceed work hour restrictions. Modified JPM A1b Perform calculation of the correct amount of water and boric acid required to manually raise the level in the VeT. Bank JPM A2 Perform a portion of Monthly Shift -Log surveillance instruction 1-SI-OPS-OOO-003.M and recognize inoperable instruments~ New JPM A3 Using a survey map and radiological work permit, determine conditions in the room and the required dose- monitoring and protective clothing required while inside the room. ModifiedJPM A4 Not Applicable

F L ES*301 Administrative Topics Outline Form ES*301*1 Facility: Sequoyah 1 & 2 Examination 'Level: RO D SRO ~ Date of Examination: 1/2009 Operating Test Number: NRC Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Type Code* M,R D,R N,S N,R M,S Describe activity to be performed 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. 2.9* / 3.9 JPM: Evaluate Overtime Requirements 2.1 .23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.3 / 4.4 JPM: Calculate Manual Makeup tothe Volume Control Tank. (JPM005) 2.2.12 Knowledge of surveillance procedures. 3.7/4.1 JP.M: Perform MO'nthly Shift Log O-SI-OPS-OOO-003.M 2.3.11 Ability to Approve Release Permits. 3.8/4.3 JPM: Approval of a Waste Gas Decay Tank *Release. 2.4.38 Ability to take actions called for in the facility emergency pl*an, including supporting or acting as emergency coordinator if required. 2.4/4.4 JPM: Classify the Event per the r{EP (High RCS Activity,Primary System Leakage Outside Containment). (JPM #018 modified) 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 (:5 3 for ROs; :5 4 for SROs &RO retakes) (N)ew or (M)odified from bank (~ 1) (P)revious 2 exams (:5 1; randomly selected)

I SRO Admin JPM Summary A1 a Determine when conditions exist that requires approval to exceed work hour restrictions. Modified JPM. A1b Perform calculation to manually raise the level in the veT. Bank JPM A2 Perform a portion of Monthly Shift Log surveillance instruction 1.:.SI-OPS-OOO-003.M and recognize inoperable .instruments. New JPM A3 Determine requirements for releasing a Waste Gas Decay Tank including hold-up time requirements, approval required in outside normal release hours, requirements with radiation monitor out of service and requirement if monitor is not repaired in identified aDeM time. New JPM A4 Evaluate plant conditions for E-Plan entry, classification, and required notifications in accordance with Radiological Emergency Plan procedures. Bank JPM #18.

, L ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Sequoyah 1 & 2 Date of Examination: 1/2009 Exam Level: RO 0 SRO-I D SRO-U D Operating Test No.: NRC Control Room'Systems@ (8 for RO); (7 for SRO-I); (2or 3 forSRO-U, including 1 ESF) System / JPM Title T'ypeCode* Safety Function a. 001 Control Rod Drive System (A2.11 4.4/4.7) Perform 0-SI-OPS-085-011.0 N,A,S 1 b. 003 Reactor Coolant Pump System (A2.03 2.7/3.1) Start #1 RCP in Mode 3 (182-AP) D,A, L,S 4P c. E02S1 Termination (EA1.1 4.0/3.9) Terminate SI and Re-establish Charging Flow M,A,S 3 (JPM 027) d. 040 Steam Line Rupture (AA2.01 4.2/4.7) Faulted SG Isolation with MSIV Stuck Open (JPM 058-AP2) M,A,S 4S e. 028 Hydrogen Recombiner and Purge Control System (A4.03 3.1/3.3) Place 1BH2 Analyzer in Service D,S 5 f. 008 Component Cooling Water System (A3.02 3.2/3.2) Swap Thermal Barrier Booster Pumps (JPM 073) D,S 8 g. 015 Nuclear Instrumentation System (A4.02 3.9/3.9) D,A, L,S Reinstate Source Range Detectors (JPM 119-AP) 7 h. 064 Emergency Diesel Generators (A1.08 3.1/3.4) Perform D/G Load Test on 1B-B DIG (JPM 077) D,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); -(3 or 2 for SRO-U) i. 004 Chemical and Volume Control System (A2.14 3.-8/3.9) Perform Boration of RCS from Outside MeR (JPM 006) j. 062 Loss of Nuclear Service Water (AK3.03 4.0/4.2) Installation of Temporary Cooling (HPFP) toCCP 1A-A or 18-8 Oil Coolers k. 064 Emergency Diesel Generators (K1.05 3.4/3 ..9) Align Starting Air for Service on 2A-A DIG (JPM 023-2) D;E,R D,E,R D 48 6 @ 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

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in~plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator t-INAL Criteria for RO / SRO-I / SRO-U 4-6 / 4-6/ 2-3 s9/s8/s4 ~1/~11~1 ~ / - / ~1 (control room system) ~1/~1/~1 ~2/~2/~ 1 s 31 s 31 s 2 (randomly selected) ~1/~1/~1 JPM S.ummary A; The rod exercise surveillance instruction will be performed for 2 banks of control rods. During the second bank movement, the rodwiH being moving without a demand and result in a trip of the reactor being required. New alternate path JPM B. With the plant in Mode 3 and the other RCPs already running, RCP #1 will be placed in service. After starting RCP #1 will experience high stator winding temperatures which will require the pump t6 be stopped. Bank alternate path low power JPM. C. With the shutdown boards being powered 'from the diesel generator, the steps to terminate ECCS flow and to re-establish charging flow in accordance with ES-1.1, SI Termination will be required. JPM will require using procedure RNOs to lock out a charging pump and to address the failure of the normal charging valve to open. Bank modified alternate path JPM. D. Response to a faulted SG with a stuck open MSIV will require completing steps to identify and isolate the faulted SG in accordance with E-2, Faulted Steam Generator Isolation. Bank modified alternate path JPM. E. 1B Hydrogen analyzer will be restored to service following maintenance in accordance with the system operating instruction. Bank JPM F. Swapping thermal barrier booster pumps will require starting the 1A-A pump and securing the 1B-B pump in accordance with 1-S0-70-1, Component Cooling Water System "A" Train. Bank JPM. G. A failed Intermediate Range channel will require -manually reinstating Source Range detectors following a reactor trip in accordance with ES-0.1, Reactor Trip Response. Bank alternate path JPM. H. An operability test of DIG 1B-B will require manually starting and loading the DIG in accordance with 1-SI-OPS-082-007.B, Electrical Power System Diesel Generator 1B-B. Bank JPM. I. Evacuation of the Main Control Room will require manually borating the RCS using the emergency boration valve in accordance with AOP-C.04, Control Room Inaccessibility. Bank JPM. J. The locations, connections, and alignment required to establish temporary cooling to CCP-1A-A in accordance with AOP-M.01 due. to a loss of ERCW. Bank JPM K. Completion of maintenance work on the 2A-A DIG starting air system will require aligning the system for service in accordance with 0-SO-82-7, Diesel Generator 2A-A Support Systems. Bank JPM.

IA ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Sequoyah 1 & 2 Date of. Examination: 1/2009 Exam Level: RO D SRO~I 0 SRO-U D Operating Test No.: NRC Control Room Systems@ (8for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. 001 Control Rod Drive System (A2.11 4.4/4.7) Perform 0-SI-OPS-085-011.0 N,A,S 1 b. 003 Reactor Coolant Pump System (A2.03 2.7/3.1) Start #1 RCP in Mode 3 (182-AP) D, A, L, S 4P c. E02 SI Termination(EA1.1 4.0/3.9) Terminate SI and Re-establish Charging Flow M,A,S 3 (JPM 027) d. 040 Steam Line Rupture (AA2.01 4.2/4.7) Faulted SG Isolation with MSIV Stuck Open (JPM 058-AP2) M,A,S 4S e. 028 Hydrogen Recombiner and Purge Control System (A4.03 3.1/3.3) Place 1B H2 Analyzer in Service D,S 5 f. 008 Component Cooling Water System (A3.02 3.2/3.2) Swap Thermal Barrier B*ooster Pumps (JPM 073) D,S 8 g. 015 Nuclear Instrumentation System (A4.02 3.9/3.9) Reinstate Source Range Detectors (JPM 119-AP) D,A, L,S 7 h. In-PlantSystems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. 004 Chemical and Volume Control System (A2.14 3.8/3.9) Perform Boration ofRCS from Outside MCR (JPM 006) j. 062 Loss of Nuclear Service Water (AK3.03 4:0/4.2) Installation of Temporary Cooling (HPFP) to CCP 1A-A or 1B-B Oil Coolers k. 064 Emergency Diesel Generators (K1.05 3.4/3.9) Align Starting Air for Service on 2A-A D/G (JPM 023-2) D,E,R D,E,R D 4S 6 @ 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

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator rfi\\JAL Criteria for RO / SRO-I / SRO-U 4-6 / 4-6 / 2-3 =59/=58/=54 ~1/~1/~1 - / - / ~1 (control room system) ~ 1 I ~ 1 I ~*1 ~2/~2/~1 =5 3 I =5 3 I =5 2 (randomly selected) ~1/~1/~1 JPM Summary A. The rod exercise surveillance instruction will be performed for 2 banks of control rods. During the second bank movement, the rod will being moving without a demand and result in a trip of the reactor being required. New alternate path JPM B. With the plant in Mode 3 and the other RCPs already running, RCP #1 will be placed in service. After starting RCP #1 will experience high stator winding temperatures which will require the pumpto be stopped. Bank alternate path low power JPM. C. With the shutdown boards being powered from the diesel generator, the steps to terminate ECCS flow and to re-establish charging flow in accordance with ES-1.1, SI Termination will be required. JPM will require using procedure RNOs to lock out a charging pump and to address the failure of the normal charging valve to open. Bank modified alternate path JPM. D. Response to a faulted SG with a stuck open MSIV will require completing steps to identify and isolate the faulted SG in accordance with E~2, Faulted Steam Generator Isolation. Bank modified alternate path JPM. E. 1B Hydrogen analyzer will be restored to service following maintenance in accordance with the system operating instruction~ Bank JPM F. Swapping thermal barrier booster pumps will require starting the 1A-A pump and securing the 1B-B pump in accordance with 1-S0-70-1, Component Cooling Water System "A" Train. Bank JPM. G. A* failed Intermediate Range channel will require manually reinstating Source Range detectors following a reactor trip in accordance with ES-O.1, Reactor Trip Response. Bank alternate path JPM. H. NOT USED I. Evacuation of the Main Control Room will require manually borating the RCS using the emergency boralion valve in accordance with AOP-C.04,Control Room Inaccessibility. Bank JPM. J. The locations, connections, and alignment required to establish* temporary cooling to CCP-1 A-A in accordance with AOP-M.01 due to a loss of ERCW. Bank JPM K. Completion of maintenance work on the 2A-AD/G starting air system will require aligning the system for service in accordance with 0-SO-82-7, Diesel Generator 2A-A Support Systems. Bank JPM.

ES-301 Operating Test Quality Checklist Form ES-301-3 Date of Examination: 1/20/09 o eratin Test Number: Initials 1. General Criteria a b* c# a. b. There is no day-to-day repetition between this and other operating tests to be administered durin this examination. c. The 0 eratin test shall not du Iicate items from the a Iicants' audit test(s. see Section D.1.a.) d. Overlap with the written examination and between different parts of the operating test is within acce table limits. e. It appears that the operating test will differentiate between competent and less-than-competent a plicants at the desi nated license level. 2. Walk-Throu h Criteria a. Each JPM includes the following, as applicable: initial conditions initiating cues references and tools, including associated procedures reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include: detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the se uence of ste s, if a Iicable b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2. The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a co is attached. a. Author d. NRC Supervisor Date John BRoden /

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

Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required. 3. Simulator Criteria NOTE: c. NRC Chief Examiner (#) b. Facility Reviewer(*)

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Sequoyah 1 & 2 Date of Exam: 1/20/09 Scenario Numbers: 1 /2/ 3/4 Operating Test No.: QUALITATIVE ATTRIBUTES a Initials b* c# 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. The scenarios consist mostly of related events. Each event description consists of

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point (if applicable) 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. The events are valid with regard to physics and thermodynamics. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives. If time compression techniques are used, the scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. The simulator modeling is not altered. 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. 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. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios). 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). The level of difficulty is appropriate to support licensing decisions for each crew position. \\ , y;,t!Jjt Target Quantitative Attributes (Per Scenario; See Section D.S.d) Actual Attributes 1. Total malfunctions (5-8) 7 / 7 / 8 / 8 2. Malfunctions after EOP entry (1-2) 2/2/2/2 3. Abnormal events (2-4) 3 / 2 / 4 / 3 4. Major transients (1-2) 1/1/1/1 5. EOPs entered/requiring substantive actions (1-2) 2/2/2/1 6. EOP contingencies requiring substantive actions (0-2) 1/1/2/0 7. Critical tasks (2-3) 2/2/3/2 f.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah 1 &2 Date of Exam: 1/26/2009 Operating Test No.: NRC A E Scenarios P V 1 2 3 4 T M P E SPARE 0 I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(* T P S A B S A B S A B S A B R I U E R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 1 1 1 1 0 NOR 1 7 2 1 1 1 2,3, 3,4, 2,3, 5,6 SROI-1 IIC 5,7, 6 9, 15 4 4 2 8,9 10 MAJ 6 5 8 3 2 2 1 TS 2,3 1,2 4 0 2 2 RX 7 1 1 1 0 NOR 1 1 1 1 1 2,3, 4,6, SROI-2 I/C 5 4,6, 9, 11 4 4 2 7,8 10 MAJ 5 8 2 2 2 1 TS 2,4 2 0 2 2 RX 1 1 1 1 0 NOR 2 1 7 3 1 1 1 RO-1 I/C 2,3, 4,7, 3,5 9 4 4 2 7,9 8 MAJ 6 5 8 3 2 2 1 TS 0 0 2 2 Paae 1 of 4 AL

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah 1 &2 Date of Exam: 1/26/2009 Operating Test No.: NRC A E Scenarios P V P E 1 2 3 4 T M L N SPARE 0 I I T CREW CREW CREW CREW T N C POSITION POSITION POSITION POSITION A I A T L M N Y U T P M(*' E S A B S A B S A B S A B R I U R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 1 1 1 1 0 NOR 1 7 2 1 1 1 2,3, 3,4, 2,3, 5,6 SROI-3 IIC 5,7, 6 9, 15 4 4 2 8,9 10 MAJ 6 5 8 3 2 2 1 TS 2,3 1,2 4 0 2 2 RX 7 1 1 1 0 NOR 1 1 1 1 1 2,3, 4,6, SROI-4 I/C 5 4,6, 9, 11 4 4 2 7,8 10 MAJ 5 8 2 2 2 1 TS 2,4 2 0 2 2 RX 1 1 1 1 0 NOR 2 1 7 3 1 1 1 RO-2 I/C 2,3, 4,7, 3,5 9 4 4 2 7,9 8 MAJ 6 5 8 3 2 2 1 TS 0 0 2 2 Paae 2 of 4 A

ES-301 Transient and Event Checklist Form ES-301-5 IFacility: Sequoyah 1 &2 Date of Exam: 1/26/2009 Operating Test No.: NRC I A E Scenarios P V P E 1 2 3 4 T M L N SPARE 0 I I T CREW CREW CREW CREW T N C POSITION POSITION POSITION POSITION A I A T L M N Y U T P M(*' E S A B S A B S A B S A B R I U R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 1 1 1 1 0 NOR 1 1 1 1 1 2,3, 2,3, SROI-5 IIC 5,7, 6 9 4 4 2 8,9 MAJ 6 5 2 2 2 1 TS 2,3 2 0 2 2 RX 1 1 1 1 0 NOR 2 1 2 1 1 1 RO-3 IIC 2,3, 4,7, 7 4 4 2 7,9 8 MAJ 6 5 2 2 2 1 TS 0 0 2 2 Paae 3 of 4 IA

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Sequoyah 1 & 2 Date of Exam: 1/26/2009 Operating Test No.: NRC A E Scenarios P V P E 1 2 3 4 T M L N SPARE 0 I I T CREW CREW CREW CREW T N C POSITION POSITION POSITION POSITION A I A T L M N Y U T P M(* E S A B S A B S A B S A B R I U R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 1 1 1 0 NOR 1 1 1 1 1 N/A I/C 2,3, 3,4 2,6, 4,6, 9, 4 4 2 9, 10 10 MAJ 7 7 7 2 2 1 TS 2,3 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 I/C malfunction can be credited toward the two IIC 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. This matrix assumes that Scenario 4 is used as the spare. If scenario 4 is used in combination with any other scenario, the minimum requirements are still met for each applicant. Page 4 of 4 FI A

ES*301 I Competencies Checklist Form ES*301*6 Facility: Sequoyah 1 & 2 Date of Examination: 01/26/09 Operating Test No.: APPLICANTS RO D RO ATC. 0 RO t3DP 0 RO D SRO-I [2] SRO-I D SRO-I D SRO-I 0 SRO-U 0 SRO-U 0 SRO-U 0 SRO-U 0 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 InterpreUDiagnose 2-9 2-8 1-6, 2-10 2,3, 2,3,5, 2,4,6, 3,4,9 4-8 4,5, 1.3.5 2,5 8,9, 6,7,9 6 8-10 7,8 ,6- Events and Conditions 10 10 Comply W'ith and ALL 1,2,4, 2-8, 1-3, 1-3, 1-3, 4,6-8. 1. 1,4, 1,4, 1,3, 1,2 5,8 10 5-7,9, 6,7,9 5,6,8 10 3-5 5.7,8 5.7, 5.7 ,5, Use Procedures .(1) 10 8 6,7 .10 Operate Control N/A N/A N/A N/A 1-4, 1-4,6 4, 1,3.4 1,5, 1,4, 3.5. 1,6 7,9 6-10 7.8 5,7 7.8 ,7, Boards (2) 10 Communicate ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL AL L and Interact Demonstrate ALL ALL ALL ALL N/A N/A N/A N/A N/A N/A N/A N/A Supervisory Ability (3) Comply With and 2,3 2,4 1,2,6 2,3 N/A N/A N/A N/A N/A N/A N/A N/A 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-301, Page 27 of 2.7

~ E8-401,Rev.9 PWR examination Outline Form E8-401-2 Facility: Date of Exam: RO KIA Category Points SRO-Qnly Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency & 2 2 1 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10 1 3 3 3 2 3 2 3 2 3 2 2 28 3 2 5 2. 1 1 1 1 1 1 1 0 1 1 l' 10 2 1 3 Plant 2 Systems Tier Totals 4 4 4 3 4 3 4 2 4 3 3 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 1 2 2 2 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO..only outlines {Le., except for one category in Tier 3 of the SRQ...only outline, the (*Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by -t 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401 , Attachment 2, for guidance regarding the elimination of inappropriate KiA statements. 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution. 5. Absent a plant*specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO--only portions, respectively. 6. Select BRO topics for Tiers 1 and 2 from the shaded systems and KIA categories. 7.

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics

must be relevant to the applicable evolution or system. 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRQ-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note

1 does not apply).

Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401*3. limitSRO selections to K/As that are linked to 10 CFR 55.43. ! 1!=====================================z:=::r::I:=================================================================!I1J

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SAO TOPIC; 4.1 4.3 DOD 0 II [J 0 DOD ~ 008AG2.4.45 Pressurizer Vapor Space Accident / 3 Reactor Trip .. Stabilization .. Aecovery 3.5 3.6 / 1 r -- Reactor trip status panel Airborne activity Ability to prioritize and interpret the significance of each annunciator or alarm. DDDD~DDD Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFA: 41.10/43.5/ 45.13) This is a Generic, no stem statement is associated.

_._----------

D~DDDLJDDDDD Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the following:(CFR: 41.7 / 45.7 /45.8) DO 3.1 3.7 Small Break LOCA I 3 007EK2.03 009EA2.10 015AA2.08 Rep Malfunctions 14 --_.._--_...--.._-_._- _._. ... 3.4 3.5 [J [J DOD 0 0 ~ 0 D D Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION)=(CFR: 41.10/ 43.51 45.13) .. ~..------.- _.., _ _-~----- When to secure Reps on high bearing temperature 022AK1.02 Loss of Ax Coolant Makeup I 2 2.7 3.1 ~ [J [J 0 0 0 0 0 [J 0 D Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) Relationship of charging flow to pressure differential between charging and ReS Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations ._ - _.................. . .-...--_.....--. ---._-- _.~..-... .. _------_.,._ _--_--.-----------_._ _ ........- 025AG2.2.36 Loss of AHA System / 4 3.1 4.2 0 DOD 0 0 DOD 0 ~ This is a Generic, no stem statement is associated. "-'-"-'-' -_._---------_. Page 1 of 3 4/1/2008 2:09 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SAO Loss of Component Cooling Water / 8 2.6 2.9 0 0 DOD 0 0 ~ DOD Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 I 43.5/ 45.13) 029EG2.1.31 ATWS / 1 4.6 4.3 0 DOD 0 DOD 0 0 ~ This is a Generic, no stem statement is associated. >>r The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup. High-energy steam line break considerations ~DDDDODDDDD Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) 3.7 3.8 Steam Line Rupture - Excessive Heat Transfer /4 026AA2.03 040AK1.06 054AK1.02 Loss of Main Feedwater I 4

_.,,---

3.6 4.2 ~ DOD DOD 0 0 0 0 Effects of feedwater introduction on dry S/G Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10 / 45.3) 055EK2.04 Station Blackout / 6 -- .... .._--_.,._-- o ~ 0 0 0 0 0 0 0 0 0 Pumps Knowle9ge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the following:(CFR: 41.7 /45.7/45.8) 056AA1.11 --_.__._-_...------ Loss of Off-site Power /6 3.7 3.7 DOD 0 0 0 ~ 0 0 0 0 Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/ 45.6) HPI system Page 2 of 3 4/1/2008 2:09 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SRO TOPIC: 057AK3.01 Loss of Vital AC Inst. Bus /6 4.1 4.4 D 0 ~ ODD 0 0 0 [] 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/ 41.10 I 45.6 I 45.13) Actions contained in EOP for loss of vital ac electrical instrument bus --- 058AA1.01 Loss of DC Power / 6 3.4 3.5 [J [] 0 D [J 0 ~ D DOD Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 / 45.5/ 45.6) Cross-tie of the affected dc bus with the alternate supply >> Knowledge of the reasons for the following responses as they apply to (ABNORMAL Pu\\NT EVOLUTION):(CFR: 41.5/ 41.10 / 45.6/ 45.13) 062AK3.04 -_....._.--_ ..----------_..- --- .. . - -

................- ..._----,-~--

.._.._--_.. ...,._..._........_----- Loss of Nuclear Svc Water /4 3.5 3.7 D 0 ~ 0 0 0 DOD [J D Effect on the nuclear service water discharge flow header of a loss of CCW - ,.,---------.._---------

_.__...._----_._-_.-----.__._._._----_._._-----._..---------,--

065AK3.04 Loss of Instrument Air / 8 3 3.2 0 0 ~ [J D 0 [J 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10 I 45.6 I 45.13) Cross-over to backup air supplies 077AA1.03 Generator Voltage and Electric Grid Disturbances J6 - "--- 3.8 3.7 D [J 0 0 0 0 ~ [] DOD Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 / 45.5/ 45.6) Voltatge regulator controls ..._---,--,-_. ----. WE11 EK2.1 Loss of Emergency Coolant Recirc. I 4 3.6 3.9 D ~ 0 0 0 0 0 0 0 0 0 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8)

_..-- .-------------- -

Components and functions of control and safety systems, including instrumentation, signals, intertocks, failure modes and automatic and manual features. Page 3 of 3 4/1/2008 2:09 PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: -- >>" TOPIC:

_._--..-_._---

Tech-Spec limits on rod operability CRDS ._---_*.--------_.. [JDODDD~DD[JD Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 / 45.5/ 45.6) 3.2 4.3 0 0 ~ ODD 0 [] 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10 I 45.6/ 45.13) 3.6 3.4 fR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RD SRO Continuous Rod Withdrawal / 1 001AK3.02 005AA1.01 _*..*._.__.- _.-- ---- Inoperable/Stuck Control Rod I 1 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/ 45.13)

..

-

.__..

....*_.- _._."-_._.~---.- o 0 0 0 0 0 0 ~ 0 [] 0 Whether boron flow and/or MOVs are malfunctioning from plant conditions 3.8 4.1 Emergency Boration / 1 024AA2.01 ---, ..._-_._-,.._-_....._---_. 036AK3.01 Fuel Handling Accident / 8 3.1 3.7 D D ~ 0 0 0 0 0 DOD Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.101 45.6/ 45.13) Different inputs that will cause a reactor building evacuation 059AK1.02 Accidental Liquid RadWaste ReI. / 9 2.6 3.2 ~ 0 DOD 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10 145.3) Biological effects on humans of various types of radiation, exposure levels that are acceptable for nuclear power plant personnel and the units used for radiation- intensity measurements and for radiation exposure levels -., ..-.....- ._--------, 067AG2.1.31 Plant Fire On-site /98 4.6 4.3 DOD [J DOD DOD ~ This is a Generic, no stem statement is associated.

, .. ~ ...-.....__.-------

Ability to locate control room switches) controls and indications and to determine that they are correctly reflecting the desired plant lineup. Page 1 of 2 411/2008 2:09 PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 " TOPIC: Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features. Components, capacity, and function of emergency systems. 3.8 3.8 0 0 0 0 0 0 ~ 0 0 0 0 Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.7 / 45.5/ 45.6) 3.3 3.6 ~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PIJ\\NT EVOLUTION):(CFR: 41.8 to 41.10 / 45.3) IR K1 K2 K3 K4 K5 KG A1 A2 A3 A4 G RO SAO WE08EA1.1 RCS Overcooling * PTS 14 _____ ._.__...,, ..._....__ __.__.__u,______ .. .__ ,____ _.." ..__*u . ..,.. . WE10EK1.1 Natural eire. With Seam Void! 4 KA NAME / SAFETY FUNCTION:

~_. '--._'

--

,

WE14EK2.1 LossofCTMTlntegrity/5 3.4 3.7 0 ~ 0 DODD 0 D D 0 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the following:(CFR: 41.7/45.7/45.8) Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features. Page 2 of 2 4/1/2008 2:09 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION: T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RD SAO TOPIC: FORM ES-401-2 _-...-,~_.- -.- .,- ------_ _~.~ -- .--_._--- _-----_._ _-..------._ ---------------._..-. ~

_." --

2.5 2.7 DOD ~f-tj-D 01"J-0 0 [J-"'-' Prevention'~oicold water-accidents or-transfent-s----*----- Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7) 003A1.04 003K4.02 004A3.16 Reactor Coolant Pump Reactor Coolant Pump Chemical and Volume Control 2.6 2.5 0 0 0 0 0 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/ 45.5) 3.8 4.2 0 0 DOD 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7 / 45.5) Rep oil reservoir levels Interpretation of emergency borate valve position indicating lights -n --~-- ~_.-._-_._--_._ __ -_.. ,-----_..~ - ----... _._ _ -. -------_ _._---_ _-------_ ,----_ - .. ~._.._--------_ _......------_--. . 005K6.03 Residual Heat Removal 2.5 2.6 D DOD 0 ~ 0 D [J 0 0 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7 /45.7) RHR heat exchanger .-----_.....---- - _._---- _ -- ----- _._-., ..- -_._-----------._. __ ..._ -- -_-_._._ , _---- _ _-----_ _.... . __ _--_._._ _----_.._..... ..__...--..-----_ _---_.._---------- _ _ _----- -- --_.._.._ --- ..-..----- 006A3.06 007A2.05 Emergency Core Cooling Pressurizer Relief/Quench Tank 3.9 4.2 [] 0 DOD D [J [J ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 3.2 3.6 0 0 0 0 0 [J 0 ~ DOD Ability to (a) predict the impacts of the following on'the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/ 43.5/ 45.3/45.13) Page 1 of 5 Valve lineups Exceeding PRT high-pressure limits 4/1/2008 2:09 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION: T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO FORM ES-401-2 TOPIC: 008A3.04 008K1.04 010A2.01 Component Cooling Water Component Cooling Water Pressurizer Pressure Control 2.9 3.2 DOD 0 0 DOD ~ 0 D Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7 / 45.5) 3.3 3.3 ~ 0 0 0 DOD 0 0 0 [] Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 3.3 3.6 0 DOD 0 u 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct~ control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) Requirements on and for the CCWS for different condi~ tions of the power plant Res, in order to determine source(s) of ReS leakage into the CCWS Heater failures T1--- r

_...._-----------_.-.__._--_._-----

._---- _--_ -..----_ _----_._._ ------_ --- --_ _----_ _----. 012K2.01 Reactor Protection 3.3 3.7 [J ~ 0 0 DOD DOD 0 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) RPS channels, components and interconnections .-------..-.--------_._ ..-------_._. ....--------_. ..__...._----_._---_. 013G2.4.46 Engineered Safety Features Actuation 4.2 4.2 DODD 0 0 0 0 0 0 ~ This is a Generic~ no stem statement is associated. Ability to verify that the alarms are consistent with the plant conditions. .------. . _---------_ . 022K4.03 Containment Cooling 3.6 4.0 DOC ~ 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) Page 2 of 5 Automatic containment isolation 4/1/2008 2:09 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RD SRO TOPIC: 025K502 Ice Condenser 2.6 2.8 0 0 0 0 ~ 0 0 0 DOD Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):{CFR: 41.5/45.7) Heat transfer Upper and lower doors of the ice condenser Containment spray pumps 3.4 3.6 0 0 DOD ~ DOD 0 [J Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7)

_.

... .._...._._._-_. 3.4 3.6 0 ~ 0 0 DOD 0 0 0 0 Knowledge of electrical power supplies to the following:(CFR: 41.7) Ice Condenser Containment Spray 025K6.01 026K2.01 026K3.02 Containment Spray 4.2 4.3 D 0 ~ 0 DOD ODD 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7 / 45.6) Recirculation spray system 039K5.05 Main and Reheat Steam 2.7 3.1 0 DOD ~ DOD DOD Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7)

_._--_.,,----- ------

Bases for RCS cooldown limits 059K3.04 Main Feedwater 3.6 3.8 0 0 ~ 0 DOD 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) Res 061K3.01 Auxiliary/Emergency Feedwater 4.4 4.6 0 0 ~ DOD DOD D 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR; 41.7/45.6) Page 3 of 5 4/1/2008 2:09 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SAO TOPIC: 061K5.03 Auxiliary/Emergency Feedwater 2.6 2.9 0 DOD ~ 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) Pump head effects when control valve is shut 062K1.02 063G2.4.8 AC Electrical Distribution DC Electrical Distribution 4.1 4.4 ~ D 0 [J 0 [J 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foUowing:(CFA: 41.2 to 41.9/45.7 to 45.8) 3.8 4.5 0 DOD 0 D DOD D ~ This is a Generic, no stem statement is associated. ED/G

_._--.--_.-.

. ----_._--.-- Knowledge of how abnormal operating procedures are used in conjunction with EOPs. -- .----_....._._--------_.._._. Fuel consumption rate with load 2.5 2.8 0 0 0 0 [] 0 ~ 0 DOD Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5 / 45.5) Emergency Diesel Generator 064A1.02 064K1.04 -_._....... _~ -.....--.. --.~~~- ....-. Emergency Diesel Generator _._-- 3.6 3.9 ~ ODD 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) DC distribution system Process Radiation Monitoring 073A4.02 ---"._....._--_._------_. 3.7 3.7 [] DOD 0 0 0 0 0 ~ D Ability to manually operate and/or monitor in the control room:(CFA: 41.7 / 45.5 to 45.8) Radiation monitoring system control panel 076A4.01 Service Water 2.9 2.9 0 0 0 0 [J [J D D 0 ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) SWSpumps Page 40f 5 4/1/2008 2:09 PM

ES..401, REV 9 KA NAME / SAFETY FUNCTION: T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO FORM ES-401*2 TOPIC: 078K2.02 Instrument Air 3.3 3.5 0 ~ 0 DOD 0 0 0 0 0 Knowledge -of electrical power supplies to the following:(CFR: 41.7) Emergency air compressor --_..__._-.-------_._~._.----- 103A1.01 Containment 3.7 4.1 DDDDDD~DDDD Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/ 45.5) Page 5 of 5 Containment pressure, temperature and humidity 4/1/2008 2:09 PM ---

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RD SAO TOPIC: 011K1.02 Pressurizer Level Control 3.7 3.8 ~ DOD DOD 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) Res 014K5.02 015K3.04 Rod Position Indication Nuclear Instrumentation 2.8 3.3 0 DOD ~ DOD 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):{CFR: 41.5/45.7) 3.4 4.0 0 0 ~ 0 0 0 0 0 DOD Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFA: 41.7 145.6) independent of demand position --- r ...------_..-.~---_ .._..------ Reading of NNIS channel values outside control room 2.8 2.9 0 0 0 &lJ 0 0 [J 0 [1 D D Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7) Non-nuclear Instrumentation 016K4.01

_ ..._----.-----

.....__.------_. 017A3.02

.._.-----

In-core Temperature Monitor 3.4 3.1 LJDDODDDD~DD Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7 / 45.5) Measurement of in-core thermocouple temperatures at panel outside control room D~OD[]DDDDD[J Fans Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 3.1 3.4

_.._.._----_.__._.-

.. -------.---.__.- -.._-------- Containment Iodine Removal 027K2.01 035K6.02 ._......--------_... -.-._--- Steam Generator 3.1 3.5 0 0 0 0 0 ~ 0 DOD 0 KnOWledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7 / 45.7) Secondary PORV Page 1 of 2 4/1/2008 2:09 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION: T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SAO FORM ES-401-2 TOPIC: 041A1.02 Steam DumpITurbine Bypass Control 3.1 3.2 0 DOD D 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/ 45.5) Steam pressure

._._--------- --------_.._._--

. _-_-._ _--_ _-_.._.._..----- _.---_.....**._---_ -.--_.*.- _-.--_ _ -_ -- 071 A4.16 Waste Gas Disposal 2.5 2.2 0 0 0 0 0 0 0 [J 0 ~ D Waste gas decay tank shifts Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) ---_.._-.. ------_......- .._---_..._----_. 045G2.1.25 Main Turbine Generator 3.9 4.2 DOD 0 0 DOD D 0 ~ This is a Generic, no stem statement is associated. Page 2 of 2 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data. 4/1/2008 2:09 PM --- r

ES-401, REV 9 KA NAME I SAFETY FUNCTION: f3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3~ FORM ES-401;t' ljl?.jOq TOPIC:

_.._

..*... -_._...._...." .-._._,-.-._--_.- G2.1.14 G2.1.3 Conduct of operations Conduct of operations 3.1 3.1 0 0 0 0 0 0 0 0 0 0 ~ 3.7 3.9 [] [J 0 [J DOD 0 0 0 ~ Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.

.*_--._ .._--....-....----------

Knowledge of shift or short term relief turnover practices. " 4.3 4.6 0 0 DOD DOD 0 0 ~ G2.1.37 -_......_...-_....._.-.._ ....-...',...................__........._. -......_..._......---- -_....__..._...... Conduct of operations ._-----_..._,._.._...._.__._.....------- Knowledge of procedures, guidelines or limitations associated with reactivity management G2.2.13 Equipment Control 4.1 4.3 DOD 0 0 0 DOD 0 ~ Knowledge of tagging and clearance procedures. r _. ----.__ -._.._-- - ------_._----- G2.2.37 Equipment Control 3.6 4.6 0 DDD[J[JDD~ .........._ ...-........-.-.-.--.--_._- Ability to determine operability and/or availability of safety related equipment G2.3.11 Radiation Control 3.8 4.3 0 DOD DOD DOD ~ to control radiation releases. 3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~ .__., ...-._.-- .--.'..---.- ._-.--_._-----

_.-.._.._-----,~-_ ...-----

G2.3.4 Radiation Control Page 1 of 2 Knowledge of radiation exposure limits under normal and emergency conditions 4/1/2008 2:09 PM

ES*401, REV 9 KA NAME / SAFETY FUNCTION: T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RD SRO 3~ FORM ES-401-( 1// '1..101 TOPIC: G2.4.13 Emergency Procedures/Plans 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of crew roles and responsibilities during EOP usage. 3.4 4.4 [J D [J 0 DOD 0 0 0 ~ G2.4.23 Emergency Procedures/Plans _..__._--_.-,_*._--_._.. ._--_..*..-._------ --*..- .._------_. Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations. .... r Emergency Procedures/Plans G2.4.38

*-----*-**,-*-----**-'-,*------**------~4--~4.DOD DOD [J [J 0 0

~ AbilitYto-takeactions-caliedforinthefacilityemergency .- _.. plan, including supporting or acting as emergency coordinator. Page 2 of 2 4/1/2008 2:09 PM

ES*401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC: 008AG2.4.2 Pressurizer Vapor Space Accident / 3 4.5 4.6 DOD 0 0 0 DOD 0 ~ This is a Generic, no stem statement is associated. Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

_.__.*_._---------------- ----------._-_.__.

..._-----------_.

_._._----------.._----_.._---------

4.2 4.5 [J 0 0 DOD 0 ~ [] 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 I 43.5/ 45.13) Existence of adequate natural circulation T~--- >> r PTS are violated Actions to be taken if limits DDDDDDD~D[JD Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 / 43.5/ 45.13) 3.6 4 Small Break LOCA / 3 Large Break LOCA /3 009EA2.37 011EA2.14 015AA2.01 Rep Malfunctions I 4

..._-------------- ---_.

3 3.5 0 DOD 0 0 0 ~ 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 I 43.5/ 45.13) Cause of Rep failure

M__** '

- - - __ .~_.

_ _. ~ ~ , ~ ~ _. 022AG2.1 .28 Loss of Rx Coolant Makeup / 2 4.1 4.1 0 DOD 0 DOD [J 0 ~ This is a Generic, no stem statement is associated. Knowledge of the purpose and function of major system components and controls. ,---_. --....._----- This is a Generic, no stem statement is associated.

_ **__ w., __ ***

__*

_ 4.1 4.3 0 0 DOD 0 0 0 0 0 ~ Ability to prioritize and interpret the significance of each annunciator or alarm. 077AG2.4.45 Generator Voltage and Electric Grid Disturbances / 6 Page 1 of 1 4/1/2008 2:10 PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC: 068AG2.4.47 Control Room Evac. /8 4.2 4.2 [J DOD D DOD 0 0 ~ This is a Generic, no stem statement is associated. Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

_.....-.----_......-...-------_...---..--

Knowledge of abnormal condition procedures. 2.6 3 4.0 4.2 [] 0 0 [J DOD 0 [J 0 ~ High Reactor Coolant Activity / 9 This is a Generic, no stem statement is associated. 076AA2.04 -~.-~- ~---------...------.., .-----.....-....-......- ..--------.-----.- . ...----- Process effluent radiation chart recorder D[JDD[JD[l~DD[l Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.101 43.5 1 llfX'Z.. 45.13) _____.2~. Lt._,(_r:..t~~ , . ....._.. .._.__.. ...... .. ....... . , we01 E~ Rediagnosis /3

.... ,. ...... ...........__._.... 4_.........._ ...

__....

.... ~_ ** _. ._.__* ....... " ** ... , .._ ..........._ ....., ........ - ................. ._~~...._ WE16EA2.1 High Containment Radiation / 9 2.9 3.3 0 0 0 0 0 0 0 ~ 0 D 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 I 43.5 / 45.13) Facility conditions and selection of appropriate procedures during abnormal and emergency operations. Page 1 of 1 4/1/2008 2:10 PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO TOPIC: 026G2.4.20 Containment Spray _..._._-_._----_._--- ---_._----.-._------

_..._-"..._.. ---_.._-------_....._---

"

.._---------_....-

Problems associated with Rep motors, including faulty motors and current, winding and bearing temperature problems Knowledge of operational implications of EOP warnings, cautions and notes. Flow paths of steam during a LOCA This is a Generic, no stem statement is associated. O'DD[JDDDDDO~ 2.7 3.1 0 DOD 0 0 0 ~ DOD Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/ 43.5/ 45.3/ 45.13) 3.8 4.3 3.1 3.2 0 [] 0 D' 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/ 43.5/ 45.3 / 45.13) Reactor Coolant Pump Main and Reheat Steam 003A2.03 039A2.01 ,---- ..-----_.__...__. "--"-" ._. _.._-- 062G2.4.18 AC Electrical Distribution 3.3 4.0 0 DODD 0 0 0 0 0 ~ Knowledge of the specific bases for EOPs. This is a Generic, no stem statement is associated. _.__._-------'.._.. .__.".._--_..__._-----_ _------_ __.._..------_ _.----_. 076A2.02 Service Water 2.7 3.1 0 [] 0 0 0 0 0 &l] 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/ 43.5/ 45.3145.13) Service water header pressure Page 1 of 1 4/1/2008 2:10 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 055G2.4.49 Condenser Air Removal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RD SRO 4.6 4.4 D DOD 0 DOD 0 0 ~ This is a Generic, no stem statement is associated. FORM ES-401*2 TOPIC: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. -- ---._-------_ _.~._---

_

--..____ .,...---

_ ----.-- -----

._ ,.-----_ __ - -.- -_ _ _.--------- " " 071A2.05 072A2.02 Waste Gas Disposal Area Radiation Monitoring 2.5 2.6 0 DOD 0 [] 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on'the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 2.8 2.9 0 [J DOD 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions t use procedures to correct control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/ 43.5 / 45.3/ 45.13) Page 1 of 1 ._---_._----_._- Power failure to the ARM and PRM Systems Detector 4/1/2008 2:10 PM ">> r

ES..401, REV 9 KA NAME / SAFETY FUNCTION: SRO T3 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 KG A1 A2 A3 A4 G RO SAO 5fJ&rZ- FORM ES-401,E 1/1'2./09 TOPIC: G2.1.25 Conduct of operations 3.9 4.2 0 D D DOD DOD 0 ~ Ability to interpret reference materials such as graphs. monographs and tables which contain performance data.

_...,---- .,-----

.....

_..

_....._--_.. .,.,......- ..._._------- ... -_._--,_......_.._-_._- G2.2.21 G2.2.6 G2.3.13 Equipment Control Equipment Control Radiation Control 2.9 4.1 0 [J DOD DOD 0 D ~ 3.0 3.6 [] DOD DOD [l 0 0 ~ 3.4 3.8 DOD 0 0 0 lJ 0 D 0 ~ Knowledge of pre- and post-maintenance operability requirements. Knowledge of the process for making changes to procedures ....__..._-............_- ....-..... . - ........_.... _---~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control ,----------_.......__...--,----- ---- 3.4 3.8 0 DOD DDDDD~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal. or emergency conditions or activities Emergency Procedures/Plans G2.4.27 -,_._ - _..-.. , __ --_.- _ ..-. _, _ ---... - ,...----------_ , ...-.

. _....- ..

3.4 3.9 0 0 0 0 DOD DOD ~ KnOWledge of "fire in the plant" procedures. 3.2 4.1 0 D 0 [] [l 0 0 0 0 0 ~ Emergency Procedures/Plans G2.4.28 ---...-,----------------.-.---..--.

.-..--.--

-*..-*-------KnOwledgeot-procedures relating to emergency---*_*...._-_*_-

response to sabotage. Page 1 of 1 4/1/2008 2:10 PM

ES-401 IA Record of Rejected KIAs Sequoyah 2009 RO exam Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KIA 1/1 062 AK3.04 Service water discharge header flow effected by loss of CCW. Difficulty in writing a quality question because losing CCW would only cause less heat transfer to the ERCW and the discharge header flow would be the same. Replaced by Chief Examiner on 09/02/08 with KA 062 AK3.03 2/1 004 A3.16 This KIA is similar to 024 AA2.01 which was also selected for the exam. Replaced by ChiefExaminer on 09/02/08 with KA 004 A3.11 2/2 017 A3.02 Measurement of Incore thermocouples outside MCR.. Thermocouples can be read outside MCR via the PEDS programs on desktop computers. Difficult to write a quality question. Replaced by ChiefExaminer on 09/02/08 with KA 017 A3.01 3 G2.4.38 The KIA importance rating is 2.4 (less than 2.5) Replaced by Chief Examiner on 09/02/08 with KA G2.4.39

ES-401 AL Record of Rejected KJAs Sequoyah 2009 SRO exam Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KIA 1/2 076AA2.04 No process effluent radiation chart recorder for RCS activity Replaced by Chief examiner on 09/02/08 with KA 076 AA2.02 2/2 055 G2.4.9 No immediate operator actions for condenser air removal system unless can write question relating to turbine trip criteria. Replaced by Chief examiner on 09/02/08 with KA 055 G2.4.3

F A Outline Development Methodology Outlines for the Sequoyah Nuclear Plant - Reactor and Senior Reactor Operator Initial Examinations- 05000327/2009301 and 05000328/2009301 written examinations were developed by the NRC.

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Sequoyah 1 & 2 Date of Exam: 1/2009 Exam Level: RO[0 SRO ~ Initial 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). 9. Question content conforms with specific KIA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are *ustified. New 31 / 16 CIA 60 / 60 21 / 8 Modified 40 / 40 Memory Bank 23 / 1 Item Description NRC KlAs are referenced for all questions. Facility learnin objectives are referenced as available. 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 KIAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right. Bank use meets limits (no more than 75 percent 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. a. b. 7. a. Author b. Facility Reviewer (*) c. NRC Chief Examiner (#) d. NRC Regional Supervisor 8. References/handouts provided do not give away answers or aid in the elimination of distractors. 10. Question psychometric qualit and format meet the guidelines in ES Appendix B. 11. The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet. 6. 2. 5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate: _ the audit exam was systematically and randomly developed; or _ the audit exam was completed before the license exam was started; or _ the examinations were developed independently; or _ the licensee certifies that there is no duplication; or _ other (explain) 3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 1. Questions and answers are technically accurate and applicable to the facility. 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.

I ~/ . SEQUOYAH"INITIAL D~Y REVIEW <.J_lpJ!C Instructions [Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.] 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level. 2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable). 3. Check the appropriate box if a psychometric flaw is identified: The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements. The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem). 4. Check the appropriate box if a job content error is identified: The question is not linked to the job requirements (Le., 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 (Le., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). 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). 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward KIA Only RO QUESTIONS Do NOT change order ofthe actual examination from the order in which these questions appear here! 007EK2.03, New 1 H 3 S KA matches What does "stead" mean on page OPT200ANN Rev 3, page 30 of 131, reference provided? Should that read as steady?

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues TIF Credo Partial Job- Minutia

1

Back- Q= SRO utEIS Explanation Focus Dist. Link units ward KIA Only In this situation are these the ONLY alarms that come in associated with he Steam Generators? What is the logic for Rx Trip associated with hem? /VOl .JC;v~

ft..~

A~ Otherwise appears ok. /I~tI If 4-~hlf.4rrJ~ 008AG2.4.45, NEW KAmatches r-he stem of the question, is worded very awkwardly. IT seems t~at we ~re trying to ask what is the NEXT annunciator that would come in, that-. ~ould identify that an additional event occurred. This seems a better fit.: Discuss! Distractor B is not plausible. The information in the stem, does not lead 2 H 2-3 E anyone to believe anything has gone wrong with the ROD control System, so why would anyone choose this. The indications are for pressure of RCS, PRT and pressurizer level. Why would this be considered a good answer. This needs to be changed. ~hy in distractors A and B (not plausible) the entire window used as was- in distractors C and D. Add that additional information to A that is necessary, ie. TS-68-309. Currently distractor B has no additional info necessary, since it represents the window now. Distractor D is not entirely correct. in that. there is NO space between the" 5 and the DIE on the annunciator window. 009EA2.10, Bank 3 F 2-3 E KAmatches Change stem of question to read, In accordance with AOP-R.05, "RCS Leak and Leak Source " fY.)-' D~ D'f.-Ptf' D'S oJ-' z.,\\tdo1

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only Identification," ~hich one of the following.... Irhis will make the reader identify what procedure he/she is using to begin ~ith. - Otherwise appears ok 015AA2.08, Modified Bank Same comment as question 3, place the procedure in front of the actual . question. In accordance with (lAW) AOP-R.04, "Reactor Coolant Pump . Malfunction," ~hich one of the following..... 4 F 2 E States it's a modified question, however the answer is the same, the question was made easier. Change distractor C to 220 deg F, Plausible because 220 psid is also an: alarm. Can be confused. Change distractor B to 200 Very low level fundamental question, almost a 1. 022AK1.02, Modified Bank KAmatches / Add parenthesis around noun name of EA-62-5 in initial conditions, and 5 H 3 E 2-FCV-62-89 in stem. Also add to the column titles in the first colum~FCV... GY Second column, charging flow to the Regen hea exchangere. A",~ .4 d-A . ..- 1'1 uJ- ~l(. O,,*j) p,}-' 0'(... j)J--0'V \\ \\(, O~ 7' l'tt/J..... '()"- V./ ~" t- PtJtj a-~7h~It{p-

1. I 2. Q# I LOK LOD t--......--'-~--,----r-----tr----.---,-- ......--+--,-- (F/H) (1-5) 7. Explanation 6 H 3 iOtherwise appears ok 1025AG2.2.36, NEW KAmatches E ~s described above, bring to the front of the stem, . IF RHR pump 1B-B trips when a start is attempted, OOlF (Which one of the following) identifies.. "', ' I 'Otherwise appears ok ~Jf/ pel- O~ Meets modification criteria. S J sti,l' I 1\\)- V /r' Y ,(I/.' }1/ ) 7~ ~,. >lJ. I ... lit '-ro T J~ /YI-0p - 12-/1(" ~ Hfbll1/.a~ tJK '-VI ..d he 440 gpm can be removed from each of the distractors because it is common, and place in the stem. . IS there another AFW flow that could be used in A and B? IF so, that 'ould make them more plausible. ,026AA2.03, Bank Modified KAmatches Disagree with analysis of distractors A and B, in that, why would anyone lassume from the information provided that an SI had occurred? Need to understand why this was considered plausible. Discuss.. Need to either add information in stem that would make the applicant think ithis is plausible. Or, replace those 2 distractors. HEN would the Faulted SG b~feQjf it is know to be faulted? Would this Inot disqualify distractors A and B from being plausibleTDlscul;s. 3 3 2-3 F H H 7 9 8

1. I 2. Q# I LOK LOD I---,....-.....:.,..---,....---r---+---r----"T---r---+---r- (F/H) (1-5) 7. Explanation 1- rn. Il/It OJ{ ~ LJt-{ sn* -f'J,vO 0-' /t4t('? Discuss with licensee. Even though this was used before, does not make it correct if distractors re no plausible. Discuss with licensee. Distractor A does not seem plausible. could you use information concerning the potential DP Irate MSL signal causing a MSIV isolation? Do you or DID you have this r;tr~5D ~I!J . In the stem, change establish to re-establish feed water. ~ 1055ek2.04. NEW II.M

,

KAmatches ~~ -~r Does any of the other distractors have an A-AUTO position? If NOT. then hey my not be plausible. ppears ok /1./I J. Even though this question was used in Summer in 06, this does not meet he new requirements for distractors C and D to be plausible. These don't make sense to me as being plausible. What in the stem would cause Isomeone to believe that a RED path was occurring? Maybe if TC emperatures were increasing. If they are stable with Bleed and Feed why 'ould it go RED? D is more plausible than C.

S 2-3 2-3 F H 10 11 12 H 3 S 1056AA1.11, Bank KAmatches

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only Appear ok ./' v::~ 57Ak3.01, Modified

7

13 H 3 S KAmatches ,r' . . ~ Appears ok /' r

2~~1y 058AA1.01, Bank f'JJ /I.".} KAmatches JIOIUf .q~ii~~ Of,;,) IJ 1 I~ '/2- 14 F 3 X E Disagree with Distractor 0 analysis, how can the operator make the mistake of evaluating this as a 1 vice a 2 when the TS information provided only identifies a 2 hour time frame..;;;:;,does not make sense.. C>K""!4 Distractor 0 needs to be changed. {,, ~ 062AD3.03, NEW, 12--libr~c.~ KA Put parenthesis around noun name for AOP-M.01. 15 H 3 E It seems that the reason in the answer is not correct. The reason is that he UNIT will have a faster heat up rate and is more time critical. The, reason needs to be changed to reflect this. Otherwise appears ok 065AK3.04, NEW J KA I}>' 16 F 3 E V~tJ Jl(. Change the stem to add WOOTF is the reason ... Otherwise appears ok. l/ 077AA1.03, MODIFIED ~~:J" '7 1. \\0 17 H 2-3 S KAmatches ~t-l Appears ok ~ t>f., W/E11EK2.1, BANK / '18 H 3 E KA I Does the applicant have to assume that BOTH Spray pumps are running in the current condition? IT seems so, however, the stem does not state

[!1 t:\\~ &\\~ 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. / 7. Q# LOK LOD (FtH) (1-5) Stem Cues TtF Credo Partial Job- Minutia

t

Back- Q= SRO utEtS Explanation Focus Dist. Link units ward KIA Only ~ I ~/ ) thilf. Maybe it is necessary to have that in the initial conditions in order to ..- )1£ ~_1 ~. lP 1 Y ~.....V ully describe the plant conditions prior to step 8. 1 /~ ,..,/ ,nD1 ~-tD / ~re the operators expected to know from memory the table listed in Step ~

.,...,

8? tJ::~ ~h'1 ... t~ --- . rt Be very clear in each distractor to identify that you are starting or stopping __ .L_u. Jf4{ .../': ~ 1.,.,. V ~ containment spray pump, don't say start or stop one pump. This .- I 1'- _.- - appears in distractor Band D. -./~. ,/ K ~( Change distractor B to stop both pumps when less than 8%. This makesv \\. 1\\1 he stopping the pumps correct, but not to continue to run them. ~ ~"'l 001AK3.01, New 19 H 2-3 ~ S KAmatches I" ft>.ppears ok 005AA1.01, Bank KAmatches 20 F 2 S ~ppears ok Can not imagine anyone getting this incorrect. Not very discriminating. 024AA2.01, New KAmatches Since FCV-62-138 appears in all distractors it can be taken out and placed ~bove the distractors. It can be written FCV-62-138 ... 21 H 2-3 S stopped opening... 'tlt\\~ a. b. stopped opening... C. should be... d. should be... Otherwise appears ok 036AK3.01, Modified I ~ i/ ~. / ./ v'

[j 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

1

Back- Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only \\ d ~ l- f-. h..., ....eC lIt l' ~-J ~Ol !.-t...- C. KAmatches IT ....... - In distractors Band D, it would seem that it would be better to state that it J .l- /1...1/. ff- ./. f;;;A ~)..?J" was ONLY required to notify the Refueling SRO and NOT say that the ... ) v . - ..... ;t) announcement is NOT required. Discuss. Kind of awkward to say it this - ( IV way. /2.. 1, 11 ~()8 Ae.d. 7r:r I~ ....-' ...~ cr--. i--' .I II Also the procedure states the Fuel Handling Supervisor, not the Refueling SRO, does it matter? Ask licensee. ~ ~ ~; ~ n<::...eGo~~I~_et.JA Otherwise appears ok. .,. ./JI Q.fl.- . t 059AK1.02, Modified - ( 23 F 3 S KAmatches Appears ok. 097AG2.1.31, Modified 24 F 2-3 S KAmatches ( Appears ok .~ ~ IE08EA1.1, Bank KAmatches 1tot.J ~J. V ~ h Question was modified such that loop 2 was Ch~ loop 1, but this \\ 4 ~ '( allowed the same answer, at least change this loop or 4 to have a 25 H 3 ~ ~I ifferent valve that opens. . ~~I ~ s for distractors nd, what system has~d1ii'iiti'CValve operation, ~ hat would ope valv and ~R-r~r rna al operation to close the -\\ alve. Are t re any v I~in the p nt ~ as this type of feature? *IF, N"V- OT I do ' believe th plausible. is needs to be changed. 1( . \\ l\\VrC ........ Y W/E10EK1.1, Modified - \\C; ~, ~ '~ KAmatches 26 F 2-3 ~ U. Not sure but, it appears thJ)istractor could be correct. If you look at EPM-3-ES-0.4, ERG Basis, it states that "...Only allowing the pressurizer' ~ o fill to a maximum of 90% (starting at a level above the top of the heaters), This will ensure continued pressurizer pressure control." . \\-f' ({/ \\J'

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 UlE/S Explanation Focus Dist. Link units ward KIA Only Distractor C states "Facilitates pressure control by ensuring the PZR is maintained at saturation conditions." This is close to the above. Take a look and see if it is truly incorrect. Could have 2 answers. Discuss with licensee. WE14EK2.1, Bank j KAmatches 27 F 3 S Appears to be ok, need licensee to help with the logic diagram, it seems hat the hand written valves are different than the answer. ' HELP! tJf. LJLA /L'/ 'iFf f>.,~~ 003A1.04, New \\ .... KAmatches ~ The stem asks for 2 actions, however: each distractor provides 3. The ./ ~ stem needs to be changed. ~ For example, 1. Pump pocket sump level down and 2. Monitor pocket sump level for significant change in rate of rise, 28 F 3 .~ E/S and, 3. Request Electricians to determine if the oil level is high or low. J I How can you pump it down if the electricians state the sump is low? ~ r!J Is this a fair question to require operators to know ARI steps from memory? Discuss with licensee: IF they believe it is ok, then will agree Iwith question as is. I realize this is recall of actions of the ARI but want to make sure the licensee wants this. 003K4.02, New KAmatches 29 H E Distractor A needs to be changed to remove everything after the comma and swap with "and can be started in current plant conditions." Do this change in distractor C also. A1 ()£ ~/AI ~ vf'IJrvvl} ~ t7 ~'\\ O~

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO UlE/S Explanation Focus Dist. Link units ward KIA Only Irhe second parts of Band D should be the same, B states" and a steam' bubble, and D states "but a steam bubble," make them the same.

If changes accepted, will be ok Ole. Wi L). 004A3.11, Modified ~ H 3 S M~~~ I ~ppears ok 005K6.03, Bank 31 H 3 S KA matches V ~ppears ok 006A3.06, Modified ~ /Jr?1' It. . M matches pf-~ l' . 32 F 3 E I ~erstand the analysis for the answer in this question. Need licensee to explain. Otherwise appears ok 007A2.05, Bank 33 H 2-3 S KA matches ~ppears ok 008A3.04, Modified Mmatches 34 H 3 OV I It is not necessary to have in the stem that the blackout loads sequencin~ II.!"" back on. It can be stated that DG 1A-A starts and loads normally. This' \\\\'1 ~~ ~ information is considered teaching and is not necessary.

l L-- Otherwise appears ok ~8K1.~.N~ I 35 H 3 S Mmatches o~ j /)0\\(.,

~:t? ~1l.1t ' 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (FtH) (1-5) Stem Cues TtF Credo Partial Job- Minutia

t

Back- Q= SRO U/EtS Explanation Focus Dist. Link units ward KIA Only I I hppears ok I £ A/ K- ~ -- -vA~ I 010A2.01. New '7 ~ ( KA does not match! Do not understand what procedure is being used ~ hen the answer is to leave the controller in auto and basically don't do anything. Discuss with licensee. I/....()~ _/.. , ~ he stem is indented on the second and third sentences. Remove the 36 H 2 l?t0 "U r-' - h-l r;- indent. Need to replace entire question. ,'-- "'~, ~-4"'4..c..... - ~ -/ . 012K2.01. Bank / 37 H 3 S KAmatches IAppears ok 013G2.4.46. Modified KA i( If 38 H 3 E IAdd parenthesis around the noun name of FR-S.1. ~ .. Otherwise appears ok. rY 022K4.03. Bank 39 F 2-3 S KAmatches IAppears ok 5K50~N~ I 40 F 2 S KA matches ppears ok =025K6.01,N.. I 41 F 3 S KAmatches

r/~ ~ I.J~' .~v'~ 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 0# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- 0= SRO utE/S Explanation Focus Dist. Link units ward KIA Only ppears ok I 026K2.01, Modified 42 H 3 S KAmatches Appears ok 026K3.02, Modified 43 H 3 S KAmatches Appears ok 039K5.05, New '/{ 44 H '3 S KAmatches Appears ok D-1~ L1 ~- 'IJ ~ ~~ Q't,p. ;;I!I/'L Pb4 ,j- /-.

0304. Book

x{ J

0(.- f l' fut ~ I"""~' .... r: In the stem, should isolates be plural like it isi singular? 0 -; P4'k ~ .~ Is it necessary to identify the time that "Initial'(considers. This has been a 45 H 2-3 - - E problem in the past, and sometimes we need a time frame. Discuss with .- ~-j ~ if 1/11il---l~ If-rz. " ahJ~r-rll"t -"-A- Jrrl licensee to see if this is necessary. - To make it more interesting, we could change from indicated level to ~'i- OJ< ... rJj ~ ((1- actual level. Discuss! ;VO,/l.Ij;t...4~ '/ 7;h' lh .... .1 -. ( ~ {t.. 1/..... Otherwise appears ok 061K3.01, Bank KAmatches Distractor D does not appear to be plausible. Just because other plants " 46 H 2-3 E lare susceptible to this, does not mean that it matters to an operator at SON. Discuss why this is credible at SON with licensee. Each distractor has a primary concern but it also has a basis for that concern. Do we have to change the stem to include this as well? I think Iwe do! Discuss. 1 061 K5.03, Bank I

'1J

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. ..)-.1\\ Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO utE/S Explanation l ~. Focus Dist. Link units ward KIA Only KAmatches 4'{* ,t/ Appears ok Ou// ~ ,I\\. A-J. ,l. 062K1.02, Modified, .. I, t> ~ KAmatches 48 F 2-3 ~ f'\\ .,I)' ~0 .;;tJ ~ ~ t) ~ The amount load carried by the DG in the stem is 4.6, this is / below the 2 hour requirement. .Not sure why then, 2 hours is the ~O rt ~ \\ limit. Discuss Otherwise appears ok 063G2.4.8, New / KAmatches ~ t Continuous performance of AOP-PO.2 is common to all distractors, can 49 H 2-3 ~ bring up to the top and remove from each of the distractors. Discuss with ~ licensee. ~ ) 063G2.4.8, New Continued Ov fi\\ppears ok 064A1.02, NewJ 50 H 2-3 S KAmatches fi\\ppears ok 51 H 3 S 064K1.04, Bank j KAmatches Appears ok 1- ::) 073A4.02, New ~" KAmatches ) 52 H 3 ~ { In the stem, add parenthesis around the noun names for the rad monitor ~" and the hand switch. The text provided identifies that Pulled out is also a position, on 0-SO-90-2 p 18 of 27. Does the work position need to be added to distractors A and If" l A '0\\-"III ~~

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only B, C and D? Ask licensee. / Otherwise appears ok 076A4.01, Modified KA fA,dd to the stem in accordance wth 0-SO-67-1 ~ to ensure we are all on th& I /~mepage. ~ 53 H 3 /7' Looking at distractors Band 0, it seems that we could say "Do not move' \\ (., ..s pr reposition switch 0-XS-67-286.< Lj~ [I/.,; 1\\l Discuss with licensee. 078K202, New, KAmatches 1 54 H 3

\\~

jt' !The stem does not reflect what is being answered in each distractor. You 1\\1 ~ are not asking the status of the power supplies but which if any air \\

,

compressor has power. This needs to be fixed. Discuss with licensee to ensure this is correct LJ'C~I~ .. _..l:~ ~ ~ NLJ 103A1.01,Modified op-11 _ "I ~_ ~ KA matches /.- ~ -=> ", - Disagree with plausibility of ~8~, w~ would applicants mix this up? 55/ "r Explain? ~ tpis - 3 Use parenthesis around noun name of the valves being addressed: 11_ __ ../!L L.i * lJ i-,,A- F-7 H hy would anyone believe a valve that gets an automatic closure signal rr {) -- ould also get an automatic open si~nal, do other isolation valves in the plant work this way? Discuss Dn:..{ ~r f'r,..I-s~ - A d ~ 011 K1.02, Modified 56 H 3 S KA matches fA,ppears ok ~MKUL~ffi~ I KAmatches ~J ~I g~~

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

1

Back- Q= SRO U/E/S Explanation Focus Dist. Link units ward KIA Only ppears ok I 015K3.04, New 58 F 2-3 S KAmatches ~ppears ok 016K4.01. New 59 F 3 S KAmatches I ~ppears ok, would like licensee to explain. ~.LN_ I 60 H 3 . S KA matches ppears ok ,a.LN_ I 61 F 3 S .KA matches ppearok 035K6.02, Bank 62 H 2-3 S KAmatches ~ppears ok 041A1.02, Modified J.H.;) J~ /A I KA M ~ ..-'J- " , " -". .- In the stem, teaching concerning the Steam dumps in the pressure control -- mode. Remove words "set to automatically control RCS Tavg at the no H load setpoint." Is this notJrue when its in that mode? Are these words 63 (!) 2-3 S necessary? Discuss. Disagree with higher cog. More of a fundamental, its really window ~ressing that is covering up the knowledge of just knowing what no load steam pressure is. Ok as fundamental knowledge

1. I 2. 7. Q# I LOK LOD (F/H) (1-5) Q= SR~ Explanation KIA Only 045G2.1.25m, Modified 64 I H I 3 I I I I I I I I I I I S KAmatches ppears ok 65 H 3 ~l~~ s 071A4.16, New ~ II -~ i . ~ynatches t-fow about changing all distractors to remove the value of 135 or 100 psig respectively. If we underline the words prior or past the setpoint, then the' lindividuals need to know from memory what it was. Discuss with licensee. Iwith requested change, appears ok 66 F 2 G2.1.14, New, S IKA matches ~ppears ok, 67 F 2-3 ~I~ ~ S G.2.1.3, Modified KA In stem, put parenthesis around noun name of OPDP-1. ~ppearok ~ / -i.U . ~/ 68 F 2 ~ ~" S G2.1.37, New KAmatches / IAdd parenthesis around noun name IAppears ok 69 F 2-3 aIL ¥o A-t ( G2.2.13, Bank KA ~ dd parenthesis around noun name for the valve. / ~ dd to the stem, what valve you are asking about vice "the valve" a[1d add .> the procedure that you are expected to do it in accordance with... Each distractor that identifies air isolation, it is done differently, A just does he valve in the ODen Dosition, D de pressurizes it, B does somethina

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only differently. I think these need to be the same. Discuss With changes appears ok 22.~,N~ I 70 H 3 * S KA matches ppears ok ~"~B.k I 71 F 3 S KA matches ppears ok kk- ~ VI. ~ jc:. J~....t~ ~ PI G2.3.4, Bank

.. ,..

KA 8 72 H 3)-tI.A- ~t? t-~ - ~ l.:Ct.-I-- ' ~ i I't-rt'L- lh" '/:. S ITYPO in EPIP-15 Rev 9, page 7 EXCE'7 vice Exceed . ~ ,. IAppears ok piIJ.- G2.4.13, New II KAmatches 73 F 0~ 5 IAdd parenthesis to noun names in stem. Appears to be ok . G2.4.23, Bank KAmatches 74 H 3 S IAdd Noun name parenthesis's IAppears ok G2.4.39, New, tJt KA , ti- '" '. ,/ 75 F 7./0 - Y' Distractor C, how does the CRO get back into the MCR if he does not ~ ~wipe? Does this make sense, and therefore IS If plausl6le? Need to add to the stem that lAW EPIP-8. ~tI 0lL- fino. \\ ~. ,.,\\ rtf

B 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (FtH) (1-5) Stem Cues TtF Credo Partial Job- Minutia

t

Back- Q= SRO utEtS Explanation Focus Dist. Link units ward KIA Only Discuss with licensee. I I SRO ONLY QUESTION I 008AG 2.4.2, New Question. 76 H 3 X S Not sure this is SRO ONLY, is it a requirement that ROs know the FOLD out page requirements by heart? Ask Licensee. OJ<... 4.5'. Otherwise it appears to be ok. 4()J(. 1f.ILttl.('1.Ld. ~ A~- ( 009EA2.37, Modified Bank Co' Question appears to be ok. 1/ IThe question analysis for the answer uses ES 1-1, but the question covers 77 H 3 ~ ES 1-2? The analysis needs to be changed. . ~\\( Change the stem to read "transition thaedirected" vice "transition. 1;\\ S hat will be made" S k,ov leo( ~ %~ fll,lso, add parenthesis around the noun names for each procedure in each <..--" answer. LJ irr ~ ~ ~ ,. -- .., "~t Cl/.....A -- t. 011 EA2.14, New

>0

- ..L J /J) I.>, £'~ ~, ~ ,.k ... A. The way this question is written makes the transition back to step in. ' ~ - , , - effect. This is really not SRO knowledge. The question should have a 78 H 3 /J' A RHR flow of less than 300 gpm. And then this could be used. Change the -- stem to the A RHR pump flow is 200 gpm, have pressure higher or a r c ~ ~ ..- l:z... /tr- eason for the pump to be at a reduced flow. But with the pump not- running I believe this is RO knowledge. KA seems to be a stretch. Discuss with licensee. 015AA2.01, New, KAmatches 79 H 3 S fll,ppears to be ok. IAJ- o~* ~Vf {~ 'j~..\\ JA'(

~ .~ urr ~F"-~ ~J# 'J:~

/

.(!)t:. AJlu-J. Explanation 7. his question does not appear to meet the KA and it does not seem to be SROONLY. he question is based on a basic knowledge that on a MCR evacuation EOPS are NOT followed. That eliminates A and B. i022AG2.1.28, Bank Modified. dd to the ste~he initial procedure the plant would have been in before' his occurred. J 4-JI <> 0';/.I1t..AJCc>r<-I- ~;: Is it necessary to state whakhe temperature of the exit thermocouples ere at the beginning of this event? ,is the information concerning the PCB remaining closed something you ould expect an SRO would know from Memory? This seems to be omething that they would have to look up in a reference. >~~~O/~H he answer does not make sense, is it true that the Load Dispatcher etermines OPERABILITY? Does not seem to match the KA, how does the question all0'1::S,~JL\\ ~/~VI'~ prioritize and interpret annunciators? /!z-ff,z..-.,J ~ 7 r T~ r 0 . IShould Kv be KVall caps. yw* ppears to be added info in the 3rd bullet that's teaching, "Main voltage to pike upward" most likely is NOT necessary. This can be removed. As~ Ithe licensee if this is ok to do so. he second Annunciator listed has only one' and not" as that item starts JI,/ ith a double parenthesis.

kV after 161 should this be all caps, ie KV ,,/

( ~ \\) 3 2 H H 81 82 1. I 2. Q# I LOK LOD (F/H) (1-5) ,. 80 I I Of<:. I I H 3 vutt~

-yr 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Creel. Partial Job- Minutia

1

Back- Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only Is the tense for instruments in both C and D. should this be instrument or instruments? ~ ~I () \\6 I(s , ~) fJ*f ~ 076AA2.04, Bank Modified, C ~ ~ ~\\ .. ~ ~ Vu. ~ )1 ~ KA listed on the exam item is not the KA, listed KA is AA2.02 not AA2.04.* ~ 2.04 does not match this question. Slit> 4 t...O ~ 2.0"2.. .. ' 83 M 2 1'-- Parts of the basis could be added to make this question more challenging. / For example, the 2 hour requirement small fraction of Part 100, and use his with Part 20 to make it more challenging. his is a SRO question but not written very well, Iw/E01 EG 2.4.11, New 84 H 2-3 S KAmatches, I IAppears to be ok. Iw/E16 EA2.1, Modified BankI 85 H 3 S KAmatches IAppears to be ok, 003A2.03, NEW, ,/' 86 H 3 S KAmatches; IAppears to be ok. ci 026G2.4.20, New 87 H 3 ~f<c. E KAmatches, \\ The way the stem is written, it does not seem like the first part of answers P.}lllo'"'f ASA~ '7~

1. I 2. Q# I LOK LOD I---r--:...,....---r---r---+--r----,---r-=--J-..:...-::r-=- (F/H) (1-5) 7. Explanation C and D is worded correctly. Is it possible to re write those two answers o look like it does in A and B. "Due to implementing ECA 1.3 the pump ill be restarted.... IOtherwise it appears to be ok I039A2.01, New, 88 89 H H 3 3 Il./a-.H .S In the initial conditions, how can the .pressure rise and cause a Safety Injection, but the pressure it went and stabilized at 2.4 psi. Does the SI Istart at 1.54? I am not sure of this number, have to ask. Is it necessary in the stem to state that MSIVs are open? It seems like it i Iteaching, and should not be listed. Ask licensee. I don't believe that this is necessary and would like to have it deleted. Distractor B, the word exist should be plural "exists."./ In the bulleted item, when determining if... there is two spaces there. Re write the answers C and D to state that the auto signal should NOT have initiated, rather than would NOT have been initiated. 062G2.4.18, Modified Bank hy are the procedure names in each distractor not in parenthesis, this ineeds to be done. hy was the bullet stating that there are NO other RED paths present? his was not in the other question and I don't believe it is necessary. If it is not stated then it should not be assumed that it happened. Remove I this, discuss with licensee. Currently distractor B would be discounted because there are no other higher RED paths, this would not be considered when taking the test. his can be re written to say Remain in H-1 to recover and establish a Iheat sink with the TD-AFW pump. ( v ~

/ .; dl.-. 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia

/

Back- Q= SRO UlE/S Explanation Focus Dist. Link units ward KIA Only In distractor D, this does not seem plausible because well, does FRH.1 restore power? I don't have a copy of this, will need to ask licensee if H.1 oes restore power. 076A2.02 Bank KAmatches 90 H 3 S Is it expected that the SROs should know each section of the procedure and what it is? y£-s If,$ .t<. ppears to be ok .LkA 94,",,-- 91 F 3 E he working of the stem and the distractors is awkward. One distractor you ~nd another is~is u~ow about making them the same. Otherwise it appears to be ok 071A2.05, Modified Bank

"OC..A. ......c"'o)p,.~~

- . U . In distractors C and D, it stare: there is an alarm, for manual termination 92 F 2-3 o take place. WHY would anyone determine that this is a reasonable answer? Is there a system that works this way? Ask Licensee. If not hen distractors C and D are not plausible. 072A2.02, Modified Bank It does not seem like the KA matches, why is it believed that procedures q are used to correct this action. It seems that the answer is that you don't ($J ll.- l;r have to do something. Discuss with licensee. 93 F 2-3 Can we use ONLY Train A is initiated? Would that be a reasonable distractor? Why do we only have B train? Did not have info with me to determine why B is the correct train. Not so sure that this is a fundamental question. It seems that there is more than just memory in order to answer this.

1. I 2. Q# I LOK LOD t--.....--.:.~--.----,----ir--r---.---.....--+--.--- (F/H) (1-5) 7. Explanation he auestion is not actuallv what I would call Higher Cog, this is really his question, while you have to calculate something, it sure is not hard, II you have to do is plot those two points and see where it falls on the raph. G2.2.6, Modified Bank, .dd the word procedure in front of 1-S0-64-1, / IT seems that an RO would be required to know the basis for the points on hat curve also, and when is the worst case. This does not appear to be n SRO ONLY question. Will discuss with BC and Licensee. hat makes this an SRO ONLY question? Does the RO have to understand this process also? Discuss with licensee to determine why this is considered SRO ONLY. Question is ok but is NOT SRO ONLY. (jODtJ ~"'-~11@ 1.t./JHDj> In the stem, the Work Order(WO), missing a space. hy would anyone decide that the Work week manager would be a person to sign this off?? WHY? Disagree with it being plausible. S ~ 15 i q~vl o 2 2 F F F H 95 98 97 96 94 o

(Jl/A 0\\1....i

-

fl" Explanation 7. his question does not appear to be an SRO only question. The part that 'individuals need to be in line of site, should have been covered in training

or all operators and would be expected to be known by the RO's.

recalling 2 trivial facts from two procedures, if you don't know that linformation, I don't believe you could figure out the answer. That being aid, this question will be allowed as a memory level question. During the review, did not have the entire procedure to verify if 23 psi \\J. pressurization was in the procedure. r ccepted as a fundamental question. Will discuss with licensee during Dec 16-19 meeting. G2.4.27, New KA Matches In the stem of the question, underline the word minimum, this needs to be one to prevent the applicants from NOT reading this, like I did. In formatting this question, indent the (1) and (2) in the stem to offset it rom the actual distractors. Right now it is hard to read. I think this may Ihelp. I think this question needs to be tightened up in order to prevent someone rom arguing that distractor C is also a correct answer. I say this because here really is no feel for the time frame that this is taking place. Discuss ith licensee if disagrees. During review did not have AO~hatdoes step 19 state, as NOTE iin AOP-N.01 identifies. Does tlils matter? OJ( . btherwise appears to be ok, if made more clear. he way the distractors Band 0 are worded, it would imply that 2 plant personnel of some type were sent. It does not imply that 2 wete sent. IT would seem that distractors A and C would have to be looked at to Idetermine IF 2 operators were sent. But that does not really say either, it 'ust states that one has to be aualified. All the distractors need to be 6. ~ 5. Other

1 IBack-I Q= ISRO I UlE/S

units ward KIA Only 4. Job Content Flaws cred'l PartialIJob-I Minutia Dist. Link s T/F F F 1. I 2. 3. Psychometric FI~w!': LOK LOD (F/H) (1-5) Stem Cues Focus 99 Q# 100

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem,lcuesl T/F Ic~ed*lpartial JOb-I MinutiaI #1;IBack- Q= ISRO U/E/S Explanation Focus Dlst. Link units ward KIA Only ightened up. EEEHEEEEHHm I EEEHEEEEHHm I EEEHEEEEHHm I EEEHEEEEHHm I I EEEHEEEEHHm II EEEHEEEEHHm I I EEEHEEEEHHm I I ~IIIII~ I

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem;ICuesI TIF Ic~ed*1 Partial JOb-I MinutiaI #1 iIBack- Q= ISRO UlE/S Explanation Focus Dlst. Link units ward KIA Only EEEEEEEEEEEErrB I

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem;ICuesI TIF Ic~ed*1 Partial JOb-I MinutiaI #1;IBack- Q= ISRO UlE/S Explanation Focus Dlst. Link units ward KIA Only ttl I I I I I I I I I 1+1

ES-403 Written Examination Grading Quality Checklist Form ES-403-1 Facility: Sequoyah Date of Exam: 02/04/2009 Exam Level: RO ~ SRO ~ Initials Item Description a b c 1. Clean answer sheets copied before QradinQ MJ"R N/A 164 2. Answer key changes and question deletions justified M~R N/A ~ and documented 3. Applicants' scores checked for addition errors MJR N/A ~ (reviewers spot check> 25% of examinations) 4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, IMJl"Z- N/A 4M as applicable, +/-4% on the SRO-only) reviewed in detail 5. All other failing examinations checked to ensure that grades N/A /6-J'f are justified M:\\1\\ 6. Performance on missed questions checked for training N/A ~ deficiencies and wording problems; evaluate validity IM~K of questions missed by half or more of the applicants Printed Name/Signature Date a. Grader Mark J. Riches 1ltlJ l. ~2 02/13/2009 0 b. Facility Reviewer(*) N/A c. NRC Chief Examiner (*) Richard S. Baldwin 1~~---. dr¥J/o-i d. NRC Supervisor (*) Malcolm T. Widmann 1 (*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required. }}

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