ML11168A108

2010 Clinton Power Station Initial License Examination Outline Submission

ML11168A108
Person / Time
Site:	Clinton
Issue date:	11/04/2010
From:	NRC/RGN-III
To:
References
Download: ML11168A108 (25)

Text

2010 CLINTON POWER STATION INITIAL EXAMINATION OUTLINE SUBMITTAL

• Clinton Power Station 8401 Power Road Clinton , IL 61727 U-603966 J uly 2 I 20 1 0 Regional Administrator U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle , Illinois 60532-4352 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Submittal of Initial License Training Examination Outline Nuclear 10CFR55.40 Enclosed are the examination outlines supporting the Initial License Examination scheduled

• for the weeks of 11/1/2010 through 11/12/2005 at Clinton Power Station. This submittal includes all appropriate Examination Standards forms and outlines in accordance with NUREG-1 021 , "Operating licenSing Examination Standards for Power Plants," Revision 9 Supplement

1. In accordance with NUREG-1 021, Section ES-201 , "Initial Operator Licensing Examination Process", please ensure that these materials are withheld from public disclosure until after the examinations are complete.

Should you have any questions related to this information, please contact Mr. Tallion French at (217) 937-3234. F. A. Kearney Site Vice President Clinton Power Station EET/bif cc: (w/o attachments)

Chief, NRC Operator Licensing Branch NRC Senior Resident Inspector

-Clinton Power Station JUl 1 2 2010

• *

• U.S. Nuclear Regulatory Commission U-603966 July 2 , 2010 Page 2 of 2 Attachments: (Hand delivered to NRC Region III Chief Examiner)

Examination Security Agreement (Form ES-201-3), Administrative Topics Outline (Form ES-301-1), Control Room/In-Plant Systems Outline (Form ES-301-2), BWR Examination Outline (Form ES-401-1), Generic Knowledge and Abilities Outline (Tier 3) (Form ES-401-3)

Operational Scenarios Outline (Form ES-O-1), Record of Rejected KlAs (Form ES-401-4), Examination Outline Quality Checklist (Form ES-201-2), and Transient and Event Checklist (Form ES-301-5).

Outline Methodology for 2010 Clinton Power Station Written NRC Exam

• *

• ES-201 Examination Outline Quality Checklist Form ES-201-2 <-Facility: YJ.fo11 Date of Examination

. ) l (L l Item 1. W R I T T E N 2. S I M U L A T 0 R 3. W 1 T 4. G E N E R A L a. b. c. d. a. Task Description Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KIA categories are a p propriately sampled. Assess whether the outline over-emphasizes any systems, evolutions , or generic topiCS. Assess whether the justifications for deselected or rejected KIA statements are appropriate. 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 scenar i o 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 scenar i os 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

b. c. a. b. c. d. e. f. 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 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 (3i no more than one task is repeated from the last two NRC licensino examinations 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. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. Check for duplication and overlap among exam sections.

Check the entire exam for balance of coverage. Assess whether the exam fits the appropriate job level (RO or SRO). a. Author IAwrAi KAJ b. Facility Reviewer (*) -;::; ., .. C tJ.A"{AJtl-l

(... c. NRC Chief Examiner (#) d. NRC Supervisor NOTE: # Independent NRC Reviewer initial items in Column " c"; chie f examiner concurrence required.

• Not applicable for NRC-prepared examination outlines . a I U Initials b* c#

• ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Clinton Date of Examination

11/01/2010 Initials Item Task Description a b* c# 1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. W A b. Assess whether the outline was systematically and randomly prepared in accordance with (( f4-. I Section 0.1 of ES-401 and whether all KIA categories are appropriately sampled. T i-T c. Assess whether the outline over-emphas i zes any systems, evolutions, or generiC topics. flty.. E N d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.

11 a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number 2. of normal evolutions, instrument and component failures , technical specifications, /If f--tw. S and major transients. I b. Assess whether there are enough scenario sets (and spares) to test the projected number M U and mix of applicants in accordance with the expected crew composition and rotation schedule ()f L without compromising exam integrity, and ensure that each applicant can be tested using tHk A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants

' audit test(s), and scenarios will not be repeated on subsequent days. 0 To the extent possible , assess whether the outline(s) conform(s) with the qualitative A c. 1f and quantitative criteria specified on Form ES-301-4 and described in Appendix D. 3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2: (1 ) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form 1 (2) task repetit i on from the last two NAC exam i nations is within the lim i ts spec i f i ed on the form 1f K T (3) no tasks are duplicated from the applicants

' audit test(s) (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power , emergency, and ACA tasks meet the criteria on the form b. Verify that the administrative outline meets the criteria specif i ed on Form ES-301-1 : (1 ) the tasks are distributed among the topics as specified on the form 1{ f. (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 f1J'/ 1. tM of IWplicants and ensure that no items are duplicated on subsequent days. 4. a. Assess whether plant-specific priorities (including PAA and IPE insights) are covered )f R in the appropriate exam section. G b. Assess whether the 10 CFA 55.41/43 and 55.45 sampling is appropriate. /[( f!.. E N c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. !W tJUt( E 1 SC/, j) A d. Check for duplication and overlap among exam sections. A e. Check the entire exam for balance of coverage. !){ ;!-/It( L f . Assess whether the exam fits the appropriate job leve ({AO):>r SAO). ,l a. Author . 1{:ltu" 1 Signature 9.f: J D b. Facility Aeviewer (*)

..fJ.. U:/'-f () c. NAC Chief Examiner (#) {"Nll It'IXAlF:.. ( "7flm.p ,.,

"* d. NRC Supervisor

/./;Y/), A, Uk"",;, / //7 V -; NOTE: # Independent NAC Aeviewer initial items in Column " c"; chief examiner concurrence required.

• Not applicable for NAC-prepared examinat i on outlines.

ES-201, Page 26 of 28 17¥:J;s 'IS -me:. g.C; -£s-ZP( -Z-wAs

?/(zlra WI:i7+ %Jf1}L TFJ CU'faAlG,.

TAJ 11ft..

GS-UI-Z.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Clinton Date of Examination

11/01/10 Examination Level: SRO 0 Operating Test Number: 2010301 Administrative Topic Type Describe act i vity to be performed (See Note) Code* Conduct o f Operations M , S JPM 412 / Generic 2.1.18/ 3.6 Conduct a panel walkdown 3601 Conduct of Operations N , R JPM 409/ Generic 2.1.4/ 3.3 Perform license maintenance check Equipment Contro l M , R JPM 411 / Generic 2.2.13/ 4.1 Print reading errors in tagout Radiat i on Control M , R JPM 410/ Generic 2.3.7/ 3.5 Read survey map Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO appl i cants r equire only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room , (S)imulator, or Class(R)oom (D)irect from bank C:s. 3 for ROs; :s. 4 for SROs & RO retakes) (N)ew or (M)odified from bank (::: 1) (P)revious 2 exams (:s. 1; randomly selected)

ES 301, Page 22 of 27 ES-301 Control Room/In-Plant Systems Out l ine Form ES-301-2 Facility: Clinton Date of E x amination:

11/0 1/1 0 Exam Leve l: RO SRO-I D SRO-U D Operat i ng T e st Number: 2010301 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 f or SRO-U , i nc l uding 1 ESF) System 1 JPM Title Type Code* Safety Function a. 201005 A2.02 1 2.8 JPM 413 Control Rod Timing Restoration N,A,S 1 b. 209002 A4.031 3.8JPM 228 Defeat HPCS Level 8 i s olation D , C 2 c. 241000 A4.191 3.5 JPM 415 Perform tubine online tests D , S 3 d. 217000 A2.071 3.1 JPM 221 Start up RCIC tank to ta n k loss of lube oil D,A,S 4 e. 223002 A4.061 3.6 JPM 217 Verify a Group 8 isolation D , A , S 5 f. 264000 A4.041 3.7 JPM 414 Parallel a diesel N,A,S 6 g. 212000 A4.141 3.8 JPM 227 Reset a scram A,D , S.L 7 h. 288000 A4.011 3.1 JPM 106 S/U CCP P , D,A,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. 295037 EA 1.05/3.9 JPM 054 Bypass CRD filters for reactivity control D , E , L ,R 1 j. 295024 EA 1.18/3.6 JPM 022 Vent containment to spent f u el pool P , D,E,L ,R 5 k. 262002 2.1.301 4.4 JPM 252 Restore UPS 1 B D ,R 6 @ All RO and SRO-I c on t rol room (and in-pl a nt) s y stems must be d i ff e r e nt a nd se rve d iff e r e nt sa f e t y funct io n s; all 5 SRO-U sy stems must serve different s af ety f un ction s; in-p la n t sy st ems a nd f unc ti ons m ay overl a p th o se tested in the control room.

• Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-61 4-6 1 2-3 (C)ontrol room (D)irect from bank 1 (E)mergency o r abnormal in-plant 1 1 1 1 (EN)gineered safety feature / 1 (control room system (L)ow-Power 1 Shutdown 1 1 1 (N)ew or (M)odified from bank including 1(A) 1 (P)revious 2 exams 3 1 1 2 (randomly selected) (R)CA 1 1 > 1 1 1 (S)imulator ES-3 0 1 , Pa g e 23 of 27 ES-301 Transient and Event Checklist Form ES-301-5 Facility: Clinton Date of Exam: 11/01/2010 Operating Test Number: 2010301 A E Scenarios P V 1 2 3 Spare T M P E L N CREW CREW CREW CREW 0 I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T 0 R T 0 R T 0 R T 0 U T P 0 C P 0 C P 0 C P 0 C P M(*) E R I U RX 3 1 1 1 0 RO jgJ NOR 1 1 1 1 1 1 SRO-I IIC 4 4 4 2 0 2, 4 3,5 4 ,5 SRO-U MAJ 7 , 8 7,8,9 7 5 2 2 1 0 TS 0 2 2 RX 2 2 1 1 1 0 RO jgJ NOR 1 1 1 1 1 SRO-I IIC 0 5,6 4 ,6 3 , 6 4 4 4 2 SRO-U MAJ 7,8 7,8,9 7 5 2 2 1 D TS 0 2 2 RX 1 1 0 RO D NOR 1 1 1 SRO-I IIC 4 4 2 0 SRO-U MAJ 2 2 1 0 TS 0 2 2 RX 1 1 0 RO 0 NOR 1 1 1 SRO-I IIC 4 4 2 0 SRO-U MAJ 2 2 1 0 TS 0 2 2 Instructions:

1. Check the afElicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; 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/G) malfunctions and one major transient , in the ATC position. If an Instant SRO additionatrr serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for he ATC position. 2.

manipulations may be conducted under normal or controlled abnormal conditions (refer to Section .5.d) but must be sign i ficant per Section C.2.a of Appendi x D. P Reactivity and normal evolutions may be replaced with additional instrument or component mal unctions 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 r equirements specified for the applicant's license level in the right-hand columns. ES-301, Page 26 of 27 ES-401 Written Examination Outline Form ES-401-1

• Facility:

09-0 1 NRC Exam Date of Exam: ;:/0/ b ttJ/o RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G I 2 3 4 5 6 I 2 3 4

• Total A2 G* Total I. I 3 3 4 3 3 4 20 7 Emergency 2 I 1 I I I 2 7 3 & Plant Tier Evolutions Totals 4 4 5 4 4 6 27 \0 I 3 2 2 2 3 2 3 2 2 2 3 26 5 2. Plant 2 1 I I I I 1 I I 1 I 2 12 3 Systems Tier Totals 4 3 3 3 4 3 4 3 3 3 5 38 8 3. Generic Knowledge

& Abilities I 2 3 4 I 2 3 4 Categories 10 7 2 3 3 2 Note: I. Ensure that at least two topics from every applicable K/ A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each 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 +/-I 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 sy s tems that are not included on the outline should be added. Refer to section D.I.b of ES-40 I, for guidance regarding 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 evo l ution. 5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions , respectively. 6. Select SRO topics for Tiers I and 2 from the shaded s ystems and KIA categories.

7.* The generic (G) KI As in Tiers I and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.I.b of ES-40 I for the applicable KIA's 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (lR) for the applicable license level , and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to IOCFR55.43

• *

• ES-401 2 09-01 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1 Group 1 EAPE # / Name Safety Function Ki A Topic(s) E K 1.0 I -K now l edge of the operationa l 295030 Low S u ppression P oo l X i mp l ications of the follow in g conce p ts as 3.8 Water Level /5 th ey a pp ly to LO W SUPP R ESS I ON P OOL W ATE R LE V EL: Steam co nd e n sa ti o n E K 1.02 -Kn owledge of t he o p eratio n a l 295024 High D rywe ll P r ess ure / 5 X im p l i cations of the fo ll owing co n cep t s as 3.9 t h ey app l y to H I G H DR Y WELL PRESSU R E : Con t ai n me n t bui l ding integrity:

Mark-III A K 1.03 -Kn owledge of the ope r atio n a l 295 004 P art i a l or T ota l Loss of DC im p l icat i ons of th e fo ll ow in g co n cep t s as P wr/6 X th ey ap pl y t o P A RTI AL O R C O MP LE T E 2.9 LO S S OF D.C. POWE R: E l ectrical b u s div i s i o n a l se p a r at i o n A K 2.02 -Kn ow l edge of t he i n terre l a ti ons 295023 R efue lin g Acc Coo li ng X betwee n REFUE LI NG ACCIDENTS a nd t h e 2.9 M ode/8 fo ll owi n g: F u e l poo l coo li ng a n d clea nup syste m EK2.01 -Knowledge of the interrelations 295026 S upp ression P ool H ig h X between SUPPRESSION POOL HIGH 3.9 Water Temp. /5 WA T ER TEMPERATURE and the following: S u ppression pool cooling EK2.04 -Knowledge of the interrelations between HIGH CONTAINMENT 295 0 27 Hi g h Co nt a in ment X TEMPERATURE (MARK III 2.6 Tempe r a ture / 5 CONTAINMENT ONLY) and the follow i ng: SPDS/ERIS/CRIDS/GDS: Mark-III AK3.01 -Knowledge of the reasons for 295005 M ain Turb i n e Ge n era t or X the following re s ponses as they apply to 3.8 T rip / 3 MAIN TURBINE GENERATOR TRIP: Reactor SCRAM AK3.06 -Knowledge of the reasons for 295003 P artia l o r Comp l ete Loss of X the following responses as they apply to 3.7 AC/6 PARTIAL OR COMPLETE LOSS OF A.C. POWER: Containment i solation AK3.01 -Knowledge of the reasons for 295006 SC R A M / I X the following respon s es as they apply to 3.8 SCRAM: Reactor water level response AA 1.02 -Ability to operate and/or monitor 700000 Ge n e r ato r Vo l tage and the follow i ng as they apply to E l ectr i c G ri d Dist u rba n ces X GENERATOR VOLTAGE AND 3.8 ELECTRIC GRID DISTURBANCES

Turbine/generator controls. AA 1.04 -Ability to operate and/or monitor 29500 I P artial or Complete Loss of the following as they a pply to PARTIAL Forced Co re F l ow Ci r c ul atio n / I & X OR COMPLETE LOSS OF FORCED 2.6 4 CORE FLOW C I RCULATION: Rod contro l and informat i on system: BWR-5&6 AA 1.02 -Ability to operate and/or monitor 2950 1 9 P art i a l o r Tota l Loss of the follow i ng as they app i" y to PARTIAL I ns!. Air /8 X OR COMPLETE LOSS OF 3.3 INSTRUMENT AIR: Instrument air system valves: Plant-Specific EA2.03 -Ability to d e term i ne and/or 295 0 38 Hi g h O ff-s it e R e l ease R a t e X interpret the following as they apply to 3.5 /9 HIGH OFF-SITE RELEASE RATE: Radiation levels 2950 1 8 P artial or To t a l Loss of X AA2.01 -Ability to determine and/or 3.3 CC W/8 interpret the follow i nll as they apply to

• *

• ES-401 2 09-01 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolut i ons -Tier 1 Group 1 EAPE # / Name Safety Function KIA Top i c(s) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Component temperatu r es EA2.04 -Ability to determine and/or 2 9 5037 SC RAM Co n di ti o n s interpret the following as they apply to P rese n t a n d R eac t or Power Above X SCRAM CONDITION PRESENT AND 4.0 REACTOR POWER ABOVE APRM AP R M Dow n sca le o r Unknow n I I DOWNSCALE OR UNKNOWN: Suppress i on pool temperature 2.2.25 -Eq u ipment Control: Knowledge 29502 1 Loss o f S h ut d ow n Coo lin g X of ba s es in technical s pecifications for 3.2 14 limiting conditions for operations and safety li m i ts. 2950 1 6 Co ntr ol R oom 2.4.11 -Emergen c y Procedures

/ Plan: Aban d o n me n t 1 7 X Knowledge of a bnormal condition 4.0 prcedures. 2.2.42 -Equipment Control:: Ability to 295025 Hi gh R eac t or P r ess ur e 1 3 X recognize system parameters that are 3.9 entry-lev e l cond i tions for Technical Specifications. EK3.01 -Knowledge of the reasons for 295028 Hi gh D rywe ll T e m pe r ature X th e f ollowing r e s ponses as they apply to 3.6 15 HIGH DRYWELL TEMPERATUR E: Emergency depressur i zation 2.2.39 -Equipment Control: Knowledge 29503 1 R eac t or Low W a t e r Leve ll X of less than one hour technical 3.9 2 spec i fica t ion action s tatement s for systems. KI A Catego r y T ota l s: 3 3 4 3 3 4 Group Poi nt Tota l: I 20

• *

• ES-401 3 09-01 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1 Group 2 EAPE # / Name Safety Function KIA Topic(s) EK 1.0 I -Knowledge of the operational 295036 Secondary Containment implications of the following co n cepts as High Sump/Area Water Level / 5 X they apply to SECONDARY

2.9 CONTAINMENT

HIGH SUMP/AREA WATER LEVEL: Radiation releases EK2.06 -Knowledge of the interr e lations 295032 High Secondary between HIGH SECONDARY X CONTAINMENT AREA TEMPERATURE 3.3 Co ntainm ent Area Temperature / 5 and t he following:

Area temperature monitoring system E K 3.0 I -Knowledge of the reasons for the 295029 High Suppression Pool X following responses as they app l y to HIGH 3.5 Water Level / 5 SUPPRESSION POOL WATER LEVEL: Emergency depressurization AAI.OI -Ability to operate and/or monitor 295022 Loss of CRD Pump s / I X the following as they apply to LOSS OF 3.1 CRD PUMPS: CRD hydraulic system AA2.01 -Ability to determine and/or 295008 High Reactor Water Level X interpret the following as they apply to HIGH 3.9 12 REACTOR WATER LEVEL: Reactor water level 500000 High CTMT Hydrogen X 2.4.6 -Emergency Procedures I Plan: 3.7 Conc.15 Knowledge of EOP mitigation strategies.

295020 In advertent Cont. Isolation 2.4.11 -Eme rg e n cy Procedures I Plan: 15 & 7 X Knowledge of abnormal condition 4.0 procedures.

KIA Category Totals: 1 1 1 1 1 2 Group Point Total: I 7 ES-401

• System # / Name K K 1 2 209002 H PCS X 2 1 2000 RP S X 400000 Co mp one n t Coo l i n g X W ater 2 1 SOO S A PR M I LPR M X 2 1 SOO4 So u rce R a n ge Mo n i t o r

• 262002 U P S (ACfDC) 26200 I AC E l ec tri ca l D i st r i bu tio n 218000 AD S 263000 D C E l ec tri ca l D i strib u tio n 264000 E D Gs 239002 S R Vs

• 4 Form ES-401-1 09-01 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A A A G 3 4 5 6 1 2 3 4 K 1.05 -Know l edge of the p h ysica l connectio n s and/or cause-effect r elations h i p s be t wee n HI G H PRESSURE CORE S PR AY SYSTE M (H PCS) and th e fo ll owing: Standby liquid co n tro l system: P la n t-Specific K 1 .13 -Knowledge of the phys i cal connect i ons and/or c au s e-effect relationships between REACTOR PROTECTION SYSTEM and the following: Conta i nment pressure K2.01 -Knowledge of e lectrical power suppli es to the following: CCW pumps K 2.02 -Knowledge of e le c tr i cal powe r supplie s to the following: APRM channels K3.03 -Knowledge of the effect tha t a loss or malfunction of the X SOURCE RANGE MONITOR (SRM) SYSTEM will have on follow i ng: Rod control and information s ystem: Plant-Spec i fic K3.1 7 -Knowledge of th e effect tha t a loss or malfunction of the X UN I NTERRUPTABLE POWER SUPPLY (A.C.l D.C.) w i ll have on following:

Proce s s mon i toring: Plant-Speci fi c K4.01 -Know l edge of A.C. ELECTRICAL D I STRIBUTION X des i gn feature(s) and/or interlocks which provide for the following: Bus lockouts K4.01 -Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM X design feature(s) and/or interlocks which provide for the following: Prevent inadvertent in i tiatior of ADS logic KS.01 -Knowledge of th e operat i onal imp l icat i ons of the X follow i ng concepts as they apply to D.C. ELECTRICAL DISTRIBUTION

Hydrogen generation during battery charging. KS.06 -Knowledge of the ope r ational implications of the X following concepts as they apply to EMERGENCY GEN E RATORS (DIESEUJET)

Load sequencing K6.03 -Knowledge of the effect that a l os s or malfunct i on of t he X following will have on the RELIEF/SAFETY VALVES: A.C. power: Plant-Specif i c Imp. Q# 2.8 3.5 2.9 2.6 3.3 2.9 3.0 3.7 2.6 3.4 2.7 ES-401

• System # / Name K K 1 2 2 6 1 000SG T S 2 11 000 SLC 20 5 000 S hu tdow n Coo l i n g 2 17 000 R C I C

• 203000 RH Rl LP C I: In jec t io n M ode 2 1 5OO3 IRM 259002 R eac t or W ate r Level Co nt ro l 300000 In s trum e nt A ir 20900 1 LP CS 223002 PC ISlNu c l ear Steam S uppl y S hut off

• 4 Form ES-401-1 09-01 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A A A G 3 4 5 6 1 2 3 4 K6.09 -Knowledge of th e effect tha t a loss or malfunct i on of the X following will have on the STANDBY GAS TREATMENT SYST E M: Primary containment h i g h pressure: Plant-Specific A 1.10 -Abil i ty to predict and/or monitor chan g es in paramete r s X assoc i at ed w i th operating the STANDBY LIQUID CONTROL SYSTEM controls including: Lights and alarms A 1.01 -Ability to predict and/or monito r changes i n parameters associated with operat i ng the X SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including: Heat exchanaer coolina flow A2.02 -Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and ) (b) based on those prediction s , use pro c edures to correct , control , or mitiga t e the consequences of tho s e abnormal condit i ons or operations

Turbine trios A2.16 -Ability to (a) predict the impacts of the follow i ng on the RHA/LPCI: INJECTION MODE (PLANT SPECIFIC)

and (b) ) based on those predic t ions , use procedures to correct , control , or mit i gate the consequences of t hose abnormal cond i tions or operations

Loss of coolant acc i dent A3.01 -Ab i lity to monitor automatic operations of the INTERMEDIATE X RANGE MONITOR (IRM) SYSTEM including: Meters and recorde r s A3.10 -Ability to monitor automat i c operations of the REACTOR X WATER LEVEL CONTROL SYSTEM including: TDRFP lockup: TDRFP A4.01 -Ability to manually operate X and/or mon i tor in the control room: Pre s sure ga u ges A4.03 -Ability to manually operate X and/or monitor in the control room: Injection valves 2.4.49 -Emergency Procedures

/ Plan: Ability to perfo r m without ) refe r ence to proced ur es those actions that require immediate operat i on of system components and c ontrols. Imp. Q# 3.1 3.7 3.3 3.8 4.4 3.3 3.1 2.6 3.7 4.6 ES-401

• System # / Name K K 1 2 2 1 2000 RPS 26 1000 SGTS 2 11000SLC 263000 DC E l ect ri ca l Di st ributi o n

• 2 1 8000 A D S X KIA Ca t eg ory Tot a l s: 3 2

• 4 Form ES-40 1-1 09-01 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A A A G 3 4 5 6 1 2 3 4 2.2.36 -Equipment Control: Ability to analyze the effect of ) maintenance activities , such as degraded power sources , on the status of limiting conditions for operations. 2.1.31 -Conduct of Operat i ons: Ability to locate control room ) switches , controls , and indications , and to determine that they correctly reflect the desired plant lineup. K5.06 -Knowledge of the operational impl i cations of the X following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM: Tank level measurement A 1.01 -Ability to predict and/or monitor changes in parameters X associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including: Battery charging/discharging rate K1.06 -Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Safety/rel i ef valves 2 2 3 2 3 r 2 2 Gr o up P o int T o tal: < Imp. Q# 3.1 4.6 3.0 2.5 3.9 I 26 ES-401

• System # / Name K K 1 2 20200 1 Recirculation X 20 1001 CRD Hydraulic X 290002 Reactor Vessellntemals 29000 I Secondary CTMT

• 290003 Contro l Room HV AC 286000 Fire Protection 20 100 5 RCIS 204000 RWCU 272000 R adia tion Monitoring 233000 Fuel Pool Cooling/Clean up

• 22300 1 Primary CTMT and Aux. 5 Form ES-40 1-1 09-01 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 2 K K K K A A A A G 3 4 5 6 1 2 3 4 KI.23 -Knowledge of the physical connections and/or cause-effect relationships between RECIRCULATION SYSTEM and the following: Average power range monitor flow converters:

Plant-Specific K2.02 -Knowledge of e l ectrical power supplies to the following:

Scram valve solenoids K3.07 -Knowledge of the effect that a loss or malfunction of the X REACTOR VESSEL INTERNALS will have on following: Nuclear boiler instrumentation K4.01 -Knowledge of SECONDARY CONTAINMENT design feature(s) and/or interlocks X which provide for the following:

Personnel access without breaching secondary containment:

Plant-System K5.03 -Knowledge of the operational implications of the X following concepts as they apply to CONTROL ROOM HVAC Temperature control K6.05 -Knowledge of the effect that a loss or malfunction of the X following will have on the FIRE PROTECTION SYSTEM Screen wash system: Plant-Specific A 1.01 -Ability to predict and/or monitor changes in parameters associated with operating the X ROD CONTROL AND INFORMATION SYSTEM (RCIS) controls including:

First stage shell pressure/turbine load: BWR-6 A2.06 -Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM; and (b) based on those ) predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations

A.C. failure A3.09 -Ability to monitor automatic operations of the X RADIATION MONITORING SYSTEM including: Containment isolation indications A4.04 -Ability to manually operate X and/or monitor in the control room: Pool level 2.4.20 -Emergency Procedures

/ X Plan: Knowledge of operational implications of EOP warnings, cautions, and notes. Imp. Q# 3.4 3.6 3.1 3.5 2.6 2.6 3.2 2.5 3.6 2.9 3.8 ES-401

• Sys t em # / Name K K 1 2 22300 1 P rim ary CTMT and A u x.. KI A Category To t a l s: 1 1 *

• 5 Form ES-40 1-1 09-01 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 2 K K K K A A A A G 3 4 5 6 1 2 3 4 2.4.1 -Emergency Procedures

/ X Pl a n: Kn o wledge of EOP entry cond i t i on s and immediate action steps. 1 1 1 1 1 1 1 1 2 Gro up P o int T ota l: Imp. Q# 4.6 I 1 2 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

• Facility:

09-01 NRC Exam Date: Category KIA # RO SRO-Only Topic IR Q# IR Q# 1. Knowledge of procedures and limitations Conduct 2.1.36 involved in core alterations.

3.0 of Operations 2.1.25 Ability to interpret reference materials, such 3.9 as graphs, curves, tables , etc. Subtotal 2

• 2.2.12 Knowledge of surveillance procedures.

3.7 2. Knowledge of limiting conditions for Equipment 2.2.22 operations and safety limits. 4.0 Control Ability to interpret control room indications to 2.2.44 verify the status and operation of a system , 4.2 and understand how operator actions and directives effect plant and system conditions.

Subtotal 3 2.3.4 Knowledge of radiation exposure limits under 3.2 3. normal or emergency conditions.

Radiation 2.3.11 Ability to control radiation releases.

3.8 Control

Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 responsibilities, access to locked high-radiation areas, aligning filters, etc. Subtotal 3 4. Emergency Procedures

/

• Plan ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

• 2.4.14 Knowledge of general guidelines for EOP 3.8 usage. Knowledge of low power / shutdown 2.4.9 implications in accident (e.g., loss of coolant 3.8 accident or loss of residual heat removal) mitigation strategies.

Subtotal 2 Tier 3 Point Total 10 *

• Appendix D Scenario Outline Form ES-D-l

• Facility:

Clinton Power Station Scenario No.: One Operating Test No.: 2010301 Examiners:

Carl Moore Operators:

Dell McNeil Initial Conditions:

Reactor power is 88% Turnover: 1. Cross tie H-I busses with I supplying.

Event Malf. No. Event Event No. Type* Description I None BOP-N Cross tie H-I busses with I supplying 2 Override ATC-IIC Clogged filter CB pump 3 None ATC-R Lower reactor power with flow 4 Override ATC-C HCU failure pressure at zero requiring control rod to be driven into 00 5 Override BOP-C Turbine L.O. temperature controller 6 All -A02_01 -BOP-C Loss of seal water to A Circulating water pump 7_TVM 7 ALL-M RCIC unisolable steam line leak 2 areas 8 ALL-C BID 2 SRV's fail to open.

• 9 *(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

• Page I of 2

• *

• Appendix D Scenario Outline Form ES-D-I Scenario No.: One Operating Test No.: 2010301 Narrative Summary Event # Description

1. Cross tie R-I busses with I supplying

2. Clogged filter CB pump applicant is required to secure the Condensate Booster Pump and start a standby pump. 3. Lower reactor power with flow required per the turnover sheet. 4. RCU failure pressure at zero requiring control rod to be driven into 00 call in from the field operator says there is a leak on the F-111 valve and the RCU.cannot be pressurized until repairs are complete requiring the control rod to be driven in to position 00 5. Turbine L.a. temperature controller fails causing main turbine lube oil temperature to rise requiring the operator to take manual control of main turbine lube oil temperature.

6. Loss of seal water to A Circulating water pump requiring it to be removed from service 7. RCIC un-isolable steam line leak 2 areas requiring a manual initiation of ADS 8. Upon the initiation of ADS 2 SRV's fail to open which requires manual operation to open two more relief valves to complete the blow down EOPS 1,6,3 Critical tasks:

• Blow down when two areas above max safe

• Verify seven relief valves open upon initiation of ADS Page 20f2 Appendix D Scenario Outline Form ES-D-l

• Facility:

Clinton Power Station Scenario No.: Two Operating Test No.: 2010301 Examiners:

Carl Moore Operators: Dell McNeil Initial Conditions:

Reactor power is 50% Turnover: I. MDRFP locked out for maintenance

2. Shift TBCCW pumps for maintenance Event Malf. No. Event Event No. Type* Description 1 None BOP-N Swap TBCCW pumps 2 None ATC-R Raise reactor power with rods 3 BOP-C CCW pump trip YP_XMFfB -39lX 4 Override ATC-C 'B' RWCU pump seal plate temperature high 5 ED_EK20_TR BOP-C ERA T Static V AR Compensator trip UE

• 6 YPRRI5AA ATC-I FWLC level sensor failure 7 ALL-M Loss of stator water cooling causing Generator runback 8 XP_MMFFf_ ALL-M ATWS All Scram functions fail. B4963 XMFfB5002 9 YP_XMFfB -ALL-M CRD Pump trip A or (B) on the scram 4852(3) *(N)ormal, (R)eactivity, (I)nstrument, (C)omponent , (M)aJor

• Page 1 of 2

• *

• Appendix D Scenario Outline Form ES-D-l Scenario No.: Two Operating Test No.: 2010301 Narrative Summary Event # Description Narrative Summary Event # Description

l. Swap TBCCW pumps 2. Raise reactor power with rods lAW with the REMA 3. CCW pump trip. The 'B' operator will have to start the standby CCW pump in accordance with the ARP. 4. RWCU pump B develops a seal leak requiring its removal from service. 5. ERAT Static V AR Compensator trips. The 'B' RO places control switch to off and remove from service and perform 9082.01 in accordance with the ARP. 6. Feed water level instrument fails high causing the applicant to transfer FWLC to the operating channel. 7. Loss of stator water cooling generator runback manual scram required 8. A TWS all scram functions fail 9. On initiation of the scram the operating CRD pump will trip which will not allow the control rods to be driven in until CRD is restored.

EOPS 1,lA Critical tasks:

• Perform a manual scram at the confirmation of the main generator runback

• Restore CRD to drive control rods to shut down the reactor

• Lower reactor water level to control reactor power by terminating and preventing injection

• Inject SLC Page 2 of2 Appendix D Scenario Outline Form ES-D-l

• Facility:

Clinton Power Station Scenario No.: Spare Operating Test No.: 2010301 Examiners:

Carl Moore Operators: Dell McNeil Initial Conditions:

Reactor power is 50% Turnover:

I. Swap EHC pumps Event Malf. No. Event Event No. Type* Description I None BOP-N Shift EHC pumps 2 None ATC-R Raise reactor power with rods 3 ATC-C While with drawing control rod coupling failure (will recouple) 4 BOP-C SRV open (closes upon removal of fuses) 5 YP_XMFTB -BOP-C Spurious HPCS initiation 4102 6 Override ATC-C 'A' TDRFP trouble alarm 7 IT-14 ALL-M Instrument line break 8 IT-IS ALL-C Loss of all indication requiring RPV flooding EOP 2. * *(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

• Page 1 of 2

• *

• Appendix D Scenario Outline Form ES-D-l Scenario No.: Spare Operating Test No.: 2010301 Narrative Summary Event # Description

1. Shift EHC pumps per 3105.02 Main EHC hydraulic power unit. 2. Raise reactor power with rods per the REMA. 3. When with drawing control rod the coupling will fail requiring the operator to couple the control rod. 4. SRV will fail open and the SRV will close upon removal of the "B" control power fuses. 5. HPCS will initiate causing reactor power to lower. The "B" operator will have to secure HPCS. 6. 'A' TDRFP experiences a trouble alarm on a thrust bearing wear condition requiring tripping of the 'A' TDRFP. This will require verification that the running 'B' TDRFP is adequately maintaining level. A RR FCV runback will require entry to CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control to verify no core instabilities along with entry into CPS 4002.01, Abnormal RPV LevellLoss of Feedwater At Power. 7. Instrument line break in the drywell causing drywell pressure to rise requiring a manual scram 8. 4 minutes after the instrument line break there will be a loss of all RPV level instrumentation and RPV will have to be flooded to the Main Steam Lines. EOPS 1,1A Critical tasks:

• Secure HPCS

• Manual Scram

• Flood vessel to the main steam lines Page 2 of2