ML11105A185

2010 Prairie Island Nuclear Plant Initial License Examination Outline Submission Rev 0

ML11105A185
Person / Time
Site:	Prairie Island
Issue date:	03/26/2010
From:	Chuck Zoia Operations Branch III
To:	Northern States Power Co, Xcel Energy
References
Download: ML11105A185 (42)

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• .. _ ..... _-. 2010 PRAIRIE ISLAND NUCLEAR GENERATING PLANT INITIAL EXAMINATION OUTLINE SUBMITTAL ENCLOSURE WITHHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH NUREG-1021 UNTIL AFTER THE EXAMINATION IS COMPLETE.

tl Xcel Energy* DEC 072009 Regional Administrator, Region III U S Nuclear Regulatory Commission 2443 Warrenvitle Road, Suite 210 Lisle, Illinois 60532-4352 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPA-42 and OPR-60 L-PI-09*126 NUREG-1021 PTatrie Island. Nuclear Generatfng Plant (PINGP} Initial Operator Licensing Examination Qutlines .. .

Reference:

1. Nuclear Regulatory Commission (NRC) letter to Mr. Mark A. Schimmel, "Prairie Island Nuclear Generating Plant, Units 1 and 2, Confirmarion of Initial License Examination," dated November 5,2009, Accession Number Ml093170483.

In response to Reference .1, Northern States Power Company, a Minnesota Corporation (N8PM), submits the integrated examination outlines for the initial operator licensing examinations to be administered at PINGP the weeks of March 15 and 22, 2010. This information is provided in accordance with guideline ES-201 of NUREG-1021 , "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement

1. NUREG-1021 physical security requirements state that the enclosed examination materials shall be withheld from public disclosure untit after the examination is complete.

1717 Wakonade Drive East

• Welch. Minnesota 55089-9642 Telephone:

651.388.1121 Regional Administrator, Region 111 Page 2 Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Units 1 and 2 Northern States Power Company -Minnesota Enclosure cc: Charles Zoia, US NRC Region III, with enclosure Hironori Peterson, US NRC Region Ill, without enclosure ENCLOSURE WITHHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WJTH NUREG*1021 UNTIL AFTER THE EXAMINATION IS COMPLETE. ENCLOSURE 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Initial Operator Licensing Examination Outlines Form Title or Description Number of Number Pages r""' Examlnation Outline Quality Checklist 1 ES-201-3 Security Agreement 4 ES-301-1 Topics Outline --Reactor Operator (RO) 2 ES-301-1 Administrative Topics Outline -Senior Reactor Operator 2 (SRO) ES-301-2 Control Room/In-Plant Systems Outline -RO 2 ES-301-2 Control Room/In-Plant Systems Outline -SRO-U 2 .. ,--.. ---ES-301-2 Control Room/In-Plant Systems Outline -SRO-I 2 ES-301-5 Transient and Event Check1ists 3 , .. ES-D*1 Scenario Outline 10 r'-'-"" .. -ES-401-2 PWR Examination Outline (RO) 7 .,' ** " __ *n" __ o,.*_" _. .... _.

• • .

_, *. ,_ ""' *.. " .... ,",. ,_. ___ ._ " ** ... *. ,_" ." .,--... ... ... "" .... -ES401-2 PWR Exanlination Outline (SRO) 5 ,_,., _"' *.* ... " ** "'_, .... _.,,_ ... ,"'_ ,'" '. __ ,_ " _. .... ES-401-3 Generic Knowledge and Abilities Outline (Tier 3) (RO) 1 .... , .. , ''. .. E8*401-3 Generic Knowledge and Abilities Outline (Tier 3) (SRO) i .. --ES-401-4 Record of Bejected KI As 1 f--... ,* .. , ..... ,.

• • _ ** '." _ ,_",.",,",. .. '" ....... '. n ******* ....

i NiA 2010 lL T Exam Random Selection Methodology 2 r, ** ,., ** ,. Examination Outline Quality Checkl i st Facility: Prair ie I sland Date of Examinat i on: 3/15/2010 Item 1. W A I T T E N 2. S I M U L A T o A 3. W 1 T 4. G E N E A A L J Task Des cription a. Verify th at the outl in ers) fit(s) the appropriate model, i n accordance with ES-401. b. A ssess whether the outline was systemat ically and r andomly prepared in accordan c e with Section 0.1 o f ES-4 0 1 and whether all KIA categories are a ppropriately sampled. v c. As sess wh e ther the out line over-emphasizes any systems, evolutions , or generic t op i cs. ./ d. A ssess whether th e justifications for deselected or rej ec ted KIA statements are appropr i ate. ./ a. Using Form ES-301-5, verify that the proposed scenario sets cover the required numbe r of normal evolutions, i nstrument and component failures , te chnic a l speci fica t ions , and major transients. b. As sess wheth e r there are enough scenario se t s (and spares) to tes t t he projected number and mix of applicants in accordance with the expected crew co mposition a n d rotat ion schedule without compromising exam integrily , and e nsure that each applicant can be tested using at least one new or sig nif icantly modified scenario. that no scena ri os are duplicated from the applicants ' audit testis), and that scenarios will no t be r epeated on subsequent days. c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative c rit e r ia s pec i f ied on Form ES-301*4 and described in Append i x D. a. Verify that the systems walk-through outline meets the crite ria specified on Form ES-301-2: (1) the oulline(s) contain(s) the req u i red number of con t rol room and in-p lan t tasks distributed among the safety fu n ctions as specified on the f o rm (2) task repetition from th e last two NAC examina t ions is wi t h i n the limits specified on the f o rm (3) no tasks are duplicated from Ihe applicants' audit t es t(s) (4) t he number of n e w 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 cri ter ia on the f o rm. b. Verify that the administrative outline me e ts 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 sig nificantly mod i fied (3) no more than one task is rep ea ted from the last two NAC l icensing examinations

c. Determine if there are enough differen t outlines to tes t the p r ojected number a nd mix of applicants and ensure that no items are duplicated on subsequen l days. a. Assess whether plant-speCif ic priorities (incl ud ing PAA and IPE i ns ig hts) are covered in t he app r opr i a t e exam sections.

b. Assess whether the 10 CFA 55.41/43 and 55.45 sampling is app r opriate. c. Ensure that KIA importance ratings (ex cep t for plan t-s p eci fic priorities) are at l eas t 2.5. d. Check for duplication and overlap among exam sec t ions. e. Check th e entire exam for balance of coverage. f. Assess whether t he exam fits t he appropriate j ob level (AO or SAO). a Note: It Independent NRC r e viewer i nilial items in Co lymn " co.; chief examiner concurre n ce mqu i rt;ld. Not app fica bl efof NRC-prepared examinationoutlinEls NUREG 1 021 Revision 9 Supplement 1 Initia ls b' c it

........ _ ... _-_ .*.. _----------------------- ES*301 Administrative Topics Outline Facility: Prairie Island Examination LeveL RO X Administrative Topic (see Note) Conduct of Conduct of Operations Equipment Control Control EmolfJency Procedures/Plarl SRO 0 Type Code' P,D, H [J, N,R N,R Date of Exmmnation: Marctl Operating T*clst Number: Describo activity to bo performoej Admin 43, Determine the time to boil durin9 reduced inventory (2.1;:5 r******* ..*..... Admin 48, ReS/Stearn Generator temperature verification (2,1,20 4,6/4.6) Admin 61, Approve isolation for 'A" CC Pump (2.2.13 41/4.3) Admin 62, Verification of RWP limits (23.7 3,5/3,6) N/A All iterns (5 total) are required for SROs, RO applicants fHquire only 4 items unless they are retaking only the administrative topics, when all 5 are required,

• Type Codes & Cr iteri,,)' (C)ontrol room, (S)imulator, or Ciass(R)oorn (O)irect from bank (::C; 3 for ROs; :,4 fOI Sf::(Os & F;:O (N)ew Of (M)Odified from bank (?: 1) (PJrevlous 2 exams (:;, 1; ran(jom!y

,,,,,,,,,,*,<

1\.1, I)'' C. ,.'" RO Admin JPM Summar}! A 1 a -Bank JPM -This JPrv1 is to determine if the personnel airlock can be open with the given plant conditions.

Trlis JPM was used on the 2007 NRC Exam A 1 b -Bank JPM -This JPM is to determine if plant conditions support starting the first HCP by vmifying RCS and S!G temperature difference, A2 ' New JPM ,,-This is a new JPM to approve the isolation of 'A' CCW pump for maintenance. A3 ' New JP/'vl -This is a new JPM to verify if work can be performed with a given RWP, A4 -Not required Facility Praine Date of t:xornin(ltJon: March 201 () . .. '._'" --.*. -Exmnination Level: f;:O SRO X OperatinG Test Nurnber:

• • >. Administrative Topic Type Describe activity to be performed (see Note) Code' Admin 43, Deterrnine the lime to boB during reducud Conduct of Oporatlons P,O,R inventory (21.25 39/4.2) .... , ...... Admin 48, ReS/Stearn Generator temperature Conduct of Operations O,H verification.

(2.1.20 4.6/4.6) ._--Admin 61, Approve isolation for "A" CC Pump 111 ICIIl Control N,R (2.2.13 4.1/4.3) Admin 62, Verification of RWP limits Control N,R (2.3.7 35/3.6) Admin 4'1, Perform Interim EmerfJEHlcy Director Actions Emergency Procedures/Plan N,R (2.4 .41 4.£5.) NOTE. All items (5 total) are required for SROs. RO applicants require only 4 Items unless they are retakinp oniy the adm!nlstratlve topics, wilEln ali 5 are required.

• Type Codes & (C)ontrol room. (S)irnulator, or Class(R)oom (0 )irf'ct from bank (:5 3 for ROs. s 4 for SROs & RO (N)ew or (M)odif!ed from bank 1 2 exams (,S 1, randomly

.,_ .. __ ., .. _._. __ '" .. _., ... __ ______________________ ?MII SRO Admin JPM Summary A 1 a -Bank ')PM -Tr)is JPrvl is to determine if the personnel airlock can be open with the given plant conditions. This JPM was used on the 2007 NRC Exarn. A 1 b -Bank JPM --This JP/Vl is to if plant conditions support startinq the first RCP by verifying RCS and S/G temperature difference. A2 .. New JPM -This is a new JPM to approve the isolation of "A' CCW pump for maintenance. A3 -New JPM -This is a new "IPM to verify if work can be performed with a given RWP. A4 -New JPM -This is a new JPM to perform the Interim Emergency Director actions during a plant event ... tJ __ ......... , ..... __________ ..... __ * .. __ *_"'_.'

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__ . __ ._-_ ... _--_._._._ .. _.-._._ .. _---/2. 0 Control Roomlln-Plant Systems Outline Form E S-30 1-2 ! F acili ty: Pr a ir ie Isl and D ate o f Ex am ina tion: Ma rch 201 0 I --.----.---...... ---.-.--... --... ------.--.--I Exam L eve l: RO X SRO-I 0 SRO-U 0 Operating Tes t No.:. _______ . __ !r'0,.,=" o==""===<=,== . "....= (7 for or __ 1 /' Syst e m / JPM Title T ype Cod e' Saf ety Func t ion ---... _-b. EO-31 SF-1 , P er form L: C ontain m ent Isolatio n A, D , S I 2 Actuation Failure If----*--**--*** .. *-**--**** ----. ..-*------** .. *--*1----*--'--c , PS-3, Respond to a Press uri z er Level Channel Failing Low D , S 1 __ 3 ___ -1 1 d, AF-8S , R e stor e AFW F low After AFW Pum p triP on L ow P ressur e D S r---4S . _____ ... _ .... _____ A. _5 = .... Restore .. 2 _. __ S I 6 ___ _ g. NI-4SF-1, N 35 High W i th Fai lu r e Of to A, D , S I 7_ h. CC-6S, Loss of Component Co oling Water N , S . 8 0 , E, (3 fo r RO;; (3 for SRO-I); (3 or 2 fo r SRO-U) Ii. VC-16 , Borate Un i t 1 RCS from Outside t he Control Room ,---"--.. -.. -----.--.---.. ----.---.. --.-----+-... -.... ---........ --.-.+ .. *"--'-"---'-'*"'---11 D , E,P 6 I j. IP-3 , Res pond t o Bypassed In s tru ment In ve rter r --. **---*-*,---+---------+--------.. -.. *-11 I k. AF-18 , Control S/G Water L evel s N , E, L __ 4S f @ All RO and S f'!O*1 co ntro l room (and in-plant) sy stems mu st b e d iffe mnt a n d serv e di ffere n t sa fet y l fu nctions; all 5 SRO-U systems must serve different sa f e t y f unc ti o n s; in-plant systems and functions may over l ap th ose t ested in th e con trol roo m. ..... T';e I / "=.==,= 1------... __ ... -----.. *-----*----.. ---------1 1 (A)!t e rnate pa th I 4-Ci 1 4-6 ! 2*3 (C)ontrol r o o m , (D)irect from b a nk i (E)me rgen cy o r abn or ma l in-p l a nt I (EN)gineered safety f e atur e (L)ow-Power I S h utd o wn (N)ewor (M)odifi e d fro m b ank inclu din g i{i\) (P)rev i o u s 2 ex am s (R)C A (S)i mu lator 2 t!<=1/?1 .. I -/ 2: 1 (contr o l ro o m s y s tem) 2: '1/2:11 2: 1 !> 3 / $ 3 / s 2 (randomly selec t e d) 2:1/2:1/2: 1 il===================*,_===.-=. ==== .. = .. ==,_= ... ,=======.= -" Rev isio n H Su p P leme nt '1 " "" -" ... _-,,----_ .. _. __ ..... _--- ._------_.- RO JPM Summary a -Bank JPM -This ,}PM aligns Charging flow from the RWST during an ATVVS condition b -Bank JPM -This JPM performs Attachment L to cornplE"tH the isolation of containment by manually aligning components that did not automatically isolate. c -Bank JPM -. This JPM has the operator respond to a PZR level ctlannel failing and taking actions lAW the procedure. d Bank JPM -This JPM has trle operator the 12 MDAFW pump after a trip on low discharge pressure. e -Bank JPM -This JPM has the operator restore PRT conditions to normal using the RCDT pump. f .. New JPM -This is a new JPM to supply Bus 15 from Unit 2. 9 -Bank JPM -This JPM has the operator respond to conditions as they occur. N35 will fail during a reactor stariup and the reactor will not automatically trip, but will triP manually. h-New JPM -This is a new JPM to isolale a leak in the CCW system using 1 C14 AOP1 . .. Bank JPM ... This JPM requires the operator borate the RCS using MV-32086 locally. -Bank JPM -This JPM has the operator to respond to a bypassed instrument inverter and restore the inverter to service. k -New JPM -This is a new JPM that has the operator control SG water levels during a plant shutdown from outside the control room. --_._----! I I I I I I I I I I ", Control Roomlln-Plant Systems Outline Prairie lei Dale of Examination: March 2010 .... -" Exarn Level: RO SRQ.-J [] SRO-U X Operating Test No. __ *** " _".w,_" __ M"' __ __ '_ ... .,_.-Control Room SysterTls@ (H for RO); (7 for SRO-I); (2 or 3 for SRO-U. indudino 1 ESF) System / JPM Title Type Safety Function .. "". . ...... " ... " ... """". a N/A EO-31SF*1, Perform f\ttachment L: Containment Isolation A, D, S ') "-Failure N/A N/A N/A ""-_ ... "--EA-19SF, Restore Power to Bus 15 from Un I! 2 A,N, EN,S 6 , N3:5 Failure High With Failure Of Reactor to Trip A , D,S 7 Systerns© (3 for RO); (3 for SRO-J): (3 or 2 for SRO-U) ... _-"" i. VC-16. Borate Unit 1 ReS from Outside the Control Room D. E, R 1 . "._ .. ,""-NIA .. " .. __ .. " .. "". k. AF-18, Control S/G Water Levels N, E L 4S @ All RO and SRO-I control room (and ifl"planl) systems must be different and servo different safety functions; ali El SRO .. U systems must serve different salety funC!lons; Ill-plant systerns and functions may overlap those tested in the control worn. , Type Codns for / / (A )lternate patll 4-6 f 4*6 i 2<:\ (C)ontrol room (D)irect from bank "'9/.$81'£4 (E)mergency or abnormal c 1 10-J ! i:: 1 (EN)gi!lE}ered f i <:1 foorn systf;rn) (L)ow-Power! f /2. 1 /:;;:. '1 (N)ew or (M)odlfied frorn bank inc1udinp *2,2/;:::2/2 "1 (P)revious

2 EtXi;lrnS

"",ICd*tEd,) (R)CA :-:. '1 ;' ! I,! 'l (S)lrnulator 16 ill IIftlldllli III' SRO-U JPM Summary-a -N/A b -Bank JPM --This JPM performs Attachment L to complete Irle isolation of containment by manually aligning components that did not automaticaliy isolate. c -NfA d

• N/A e -NJA f -New JPM-This is a new JPM to supply Bus 15 from Unit 2, 9
• Bank JPM --This JPM has the operator respond to conditions as they occur. N35 will fail during a reactor startup and the reactor will not automatically trip, but will trip manually, h -N/A -Bank JPM -. This JPM requires the operator borate the ReS using MV-32086 locally, j -N/A k -New JPM -This is a new JPM that has the operator control SG water levels a plant shutdown from outside the control morn, NUREG1021, 9

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Prairie Island Date of Examination: March 2010 Exam Level: RO D SRO-I X SRO-U 0 Operating Test No.: Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U. including 1 ESF) System I JPM Title Type Code" Safety Function a. FL-10SF-3. Lineup RWST to charging during ATWS A.P,D.S 1 b. N/A c. PS-3, Respond to a Pressurizer Level Channel Failing Low D,S 3 d. AF-BS. Restore AFW Flow After AFW Pump trip on Low Pressure D,S 4S e. RC-22SF-1, Lower PRT Level A.P.D.S 5 f. EA-19SF. Restore Power to Bus 15 from Unit 2 A. N. EN, S 6 g. NI-4SF-1, N35 Failure High With Failure Of Reactor to Trip A,D,S 7 h. CC-BS. Loss of Component Cooling Water N.S B In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. VC-1B. Borate Unit 1 ReS from Outside the Control Room D,E.R 1 j. IP-3. Respond to Bypassed Instrument Inverter D.E,P 6 k. AF-18, Control S/G Water Levels N,E,L 4S @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room .

• Type Codes Criteria for RO f SRO-I f SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irect from bank s9/::;8/::;4 (E)mergency or abnormal in-plant ;;:1/;;:1/;;:1 (EN)gineered safety feature I ;;:1 (control room system) (L)ow-Power I Shutdown ;;:1/2:1/;::1 (N)ew or (M)odified from bank including 1 (A) ;::2/;::2/;::1 (P)revious 2 exams s 3 I s 3 I s 2 (randomly selected) (R)CA ;::1/2:1/;;:1 (S)imufator NUREG 1021. Revision 9 Supplement 1

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1(.0 SRO*' JPM Summary a -Bank JPflil -This JPt",1 aligns Charging flow from the RWST during an ATWS condition b -N/A c -Bank JPM -This JPM has the operator respond to a PZR leve! channel failing and taking actions lAW the procedure. d . Bank JPM --This JPM has the operator restore th(') 12 MDAFW pump after a trip on low discharge pressure, e -Bank JPM -This JPM has the operator restore PRT conditions to normal using the RCDT pump, f -New JPM -This is a new JPM to supply Bus 15 frorn Unit 2, g -Bank JPM -This JPM has the operator respond to conditions as they occur N35 will fail during a reactor startup and the reactor will not automatically trip, but will trip manually, h -New JPM --This is a new JPM to isolate a leak in the CCW system using 1C'14 AOP1 . . Bank JPM -This JPM requires the operator borate the ReS using MV-32086 locally, -Bank ,)PM--This JPM has the operator to respond to a bypassed instrument inverter and restore the inverter to service, k . New JPM -. This is a new JPM that has the operator control SG water levels during a plant shutdown from outsIde the control room_ i ! 1 I , I I I I II I ES*301 Transient and Event Checklist R.o Form ES*301*5 IF acility: Pralrio Island Date of Exam: March 20'lll Operating Test No.: 1 [ V r**-*-*-** F) E 1 L N I T CREW C POSITION /\ T N Y T P E S A R T 0 C 11 RX NOR lie 3 M!\J T5 '3,4 RX NOr< 12 I/C 13 MAJ 5 iTS 3.4 RX NOR IIC MA.l i i 8 " ,) R P () 1, :3 4 2 i, :3 14 2 1,3 2 CRE\N POSITION f'\ T C , ...... _-_ ..*. .... B 0 P .*..*. ,2, 3,5 4 I Scenarios 3 CREW POSITION S A B r-{ T 0 0 ('" p '4' 3. 4 5 ............. 3,4 5 I 4 T r'li ...... -.. 0 CREW T N POSITION A I M S A B L U R T 0 rv1rJ r--' 0 C P R j U .-............. 5 4 :3 2 :3 2 1 . _ ............. I-.j .........

• !*****_*I*

..... I*** 1 2. 4 3. 4 c* ,) 5 3 3 2 1 j 4 2 2 1 2 2 1 1 4 2 Instructions: 111111111 I

• Check the levol and enter tile operatlrl[J test number and Form ES-t)*l eVHnl numtwrs for oach t)VEmt type, TS are not applicable for RO appilcants, ROs must serve in both the "aHhr-:*con!rols

(/"TC)" and of*plant (BOP), posItions; instant SROs mllst SiC'!Ve in both the SRO and the' l\TC pOSitions. including at least two instrument Of' component (IIC) malfunctions and ono major lmnslflnt, in the .ATC position. If an lnslnnt SRO od(litionall.v serves in tho BOP position. one lie malfunction can bo credited !mvard the two I/C malfunctions required for tho ArC pOSition.

• Roactivity manipulations may bii) condlJctHi under normal or co!)lrolft::r..i ailnonnL,1 GI.me!ilions to Section D.5.d) but must be per Section C2,a of App{<ncfix D. {'I normal evoiutions

ncly be mpiaced With addltionai ins/rurnent or conlpoll(mj nl!:l!fuflGl;OI1S (In a 1 lor*} basis.

• VVhGnever practicnl, t)oth

(]nd cornponent sh'L'juki be included: onl:,l that requirf) 'fmifiabie actions thot provide insiqhl to tho competence

mmt toward the minirnlJm specified for the uppil level in tilerigllt*hamj coiumns. [ Ins. ,,.11 I I I I fl..v ES-301 Transient and Event Checklist Form ES-301-5 Facility

Prairie Island Date of Exam: March 2010 Operating Test No.: 1 A E Scenarios P v P E 1 2 3 4 T M L N 0 I I T CREW CREW CREW CREW T N C POSITION POSITION POSITION POSITION A I A T M S A B S A B S A B S A B L U N Y R T 0 R T 0 R T 0 R T 0 M('} T P 0 C P 0 C P 0 C P 0 C P E R I U R5 RX 1 1 1 NOR 1 1 2 1 IIC 3, 2,3 2,3, 9 4 6. 7 4,6 MAJ 5 4 5 3 2 TS 0 0 RX 1 1 1 NOR 1 1 1 R6 IIC 3,4 2,3, 6 4 4,6 MAJ 5 5 2 2 TS 0 0 R7 RX 1 1 1 NOR 1 1 1 I/C 2.4. 2,4 5 4 6 MAJ 5 5 2 2 TS 0 0 U1 RX 0 0 NOR 1 1 2 1 IIC 2,4 2 2 MAJ 5 5 2 1 TS 3,4 2,3, 5 2 4 Instructions:

• 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 (IIC) malfunctions and one major transient, in the ATC pOSition. If an Instant SRO additionally serves in the BOP poSition, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

• Reactivity manipulations may be conducted under normal or control/ed 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.
• 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. NUREG 1021, Revision 9 Supplement 1

ES-301 Transient and Event Checklist Form ES*301-5 Facility: Prairie Island Date of Exam: March 2010 Operating Test No.: 1 A E Scenarios p v P E 1 2 3 4 T M L N 0 I I T CREW CREW CREW CREW T N C POSITION POSITION POSITION POSITION A I A T M S A B S A B S A B S A B L U N Y R T 0 R T 0 R T 0 R T 0 M(") T P 0 C P 0 C P 0 C P 0 C P E R I U R1 RX 1 1 1 NOR 1 1 1 IIC 2,3 1,2,3, 2,4, 9 4 5 6 MAJ 5 4 5 3 2 TS 0 0 RX 1 1 1 NOR 1 1 1 R2 IIC 3,6, 2,3 5 4 7 MAJ 5 4 2 2 TS 0 0 R3 RX 1 1 1 NOR 1 1 1 IIC 2, 3 1,2,3, 2,4, 9 4 5 6 MAJ 5 4 5 3 2 TS 0 0 R4 RX 1 1 1 NOR 1 1 1 IIC 3,6, 2,3 5 4 7 MAJ 5 4 2 2 TS 0 0 Instructions:

• 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-ot-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (IIG) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

• Reactivity manipulations may be conducted under normal or controlled abnormal conditions (reter 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.
• 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. NUREG 1021, Revision 9 Supplement 1

.O) E8-401 F2WR Examinallon Outline Forrn ES-401*2 Facility: Prairie Island PrintfJd: 2010 RO KIA Category Points Tier Group K1 K2 K3 K4 JK5 J K6 Ai A2 A:3 Ivi G' Total 3 3 3 3 3 3 113 Emergency 1-----L-_ & .::. 1 2 2 1 2 N/A 9 Abnormal Tier PI,mt Totals 4 5 S 4 5 4 27 Evolutions

3 ." ,.) 3 2 2 3 3 2 ,) :3 28 0 0 2, L ,J ... . ,--, -,--, "f'---.. ---2 1 I 0 1() () (] 0 Plant r' Systems Tier 4 3 4 4 3 :3 4 3 :3 3 4 38 0 0 Totals 3. Generic Knowledge And 2 3 4 2 :3 4 ,,-10 Abilities Categories 2 3 2 3 0 0 0 0 Note: Ensure that at least two topics from every applicable KIA category are s;)I1lpled wilrlirJ each tier of the 1'\0 and SRO-ol1ly outlines (i,e .. except fOI one category in Tier :3 of tho SRO*only outline, the "Tier TOla/s' If) (-,acll KiA cateGory shall not be less than two), ;> The point total for each group ilnd tier ill the proposed outlme Inusl matd1 thai sp()cified in the tablco_ The f!flal POIllt total to!' cacti group and tier may deViate by +/-l from that specified in the table 0 ...... . 0 0 0 based on NRC revisions, The firml RO ()X,lfll tlilist total 75 points ami the SRO-only exam nlUst total 25 points. 3, Systems/evolutions within each 910uP am Identified on Ihe associated OUlitne; systems or evolutions that do not apply at the facility sl10uld be doleted and juslified:

operillionally imp(Jftilnt, site-spt"clfic systems/ovolulions that are not inclucied on the outline sliould t18 acldocl RefGr to Section 0 l_b of ES-4()'i for guidance mfl31'(11ng the ellmirkHlon of inapPl'Opriate K'A 8lalemems, 4, Select tOpiCS from as many systems and evolutions as possible; sample evo!j Sj/stell'l Of evolution Ifl tt1H group [lefore selecting <'l second topic for allY system or evolution.

5. AtJsent il plant-specific pnorijy, only Ihose KiAs tJavin9 an Importance rali P 9 (IR) cr 2.[, or high(}1 shall be selected.

U,w the RO Dnd SRO ralings for the RO ,1nd SRO-only pO('lions, lespectiv8lV. (3, SGlect Sf;;O rOI Tiers 1 1md 2 from tile shaded systmns and KiA categones 7." The (C) I</As if"! T!fHS 1 8nd 2 ,t;h;]U St':it:)ctHd frorn 2 of K','A but topiCS be relevant t() tt'l(';: ;:Jppi!cab!e evolutiex) or s\tsLG:n, Hefer to [J, 1 D of for the appllcHble K!i\s. d. ()rr the pagl:'}$., KIA nt;cnoef's, B tJr;r:;t cJ r;GCh Uv:: for the :3pplicatJ!e iicenso ,;':Yv'f.?,l, 8nd thE: POJ(;t totJis (#) fr;r r.tn<1 !hH nfl):Jp and tiel' for cateqorv In the If Tt.i(::1 "'iarllilinJ is

n *:)tt'/(;r

/\2 G k (in /rH:? C):aH":, f.:nlf;t if. iht::* lett SidE; o{ C:OiLH nn A2 fur r;cr 2, Group :'J (N:)te 1 r1c,\E'S no: :)Pp!y) Use f:,(CJ ;.irK.! Sn() *only

51. For TifH select tOpiCS !roni SC{/IO() 2 ut i:'lH

.. 1(.'/\ I."j(l,:;;cn;l\.iCnS, iRs, ano pOint totdis (il} en h,)fHi [3-401 :1 LlfTlit SHe} to that dro linkHG to 10 en:: ,',:} . .(;" -........ ---....... .,,------- iii PWR RO Examination Outline Printed Facility: Prairie Island ES*401 Emergency and Abnormal Plant Evolutions* Tier 1 I Group 1 Form ES-401*2 E/APE # I Name I Safety Function 000007 Reactor Trip* Stabilization* Recovery 11 000008 Pressurizer Vapor Space Accident 13 000011 Large Break LOCA I 3 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System 14 000026 Loss of Component Cooling Water 18 000027 Pressurizer Pressure Control System Malfunction I 3 000029 A TWS I 1 000038 Steam Gen. Tube Rupture I 3 000054 Loss of Main Feedwater I 4 000055 Station Blackout I 6 000058 Loss of DC Power I 6 00062 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air I 8 W/E04 LOCA Outside Containment I 3 W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sink I 4 K1 K2 K3 A1 A2 cG KA Topic x x x x x x x r, \.i EK2.02 -Breakers, relays and .': I,;:; disconnects X fF' *. '<f AA 1.01 -PZR spray block valve and ;;,' PORV block valve x ,'x I EA2.11 -Conditions for throttling or stopping HPI 5' X 2.4.46 -Ability to verify that the alarms are consistent with the plant

• I.,,,,, '. conditions.

f'; ii,,! AK1.01

• Loss of RHRS during all
• modes of operation

". AA 1.07 -Flow rates to the * 'J components and systems that are I' serviced by the CCWS; interactions among the components AK2.03

• Controllers and posit/oners i'X,*':",:" EA2.02 -Reactor Trip Alarm .t* ... ; tt'**', x** I;;' EA 1.44 -Level operating limits for ,in S/Gs X'i AK1.01 -MFW line break .. depressurizes the S/G (similar to a .' steam line break) "" EK1.02 -Natural circulation cooling AA2.01 -That a loss of dc power has occurred; verification that substitute power sources have come on line 'X 2.4.8 -Knowledge of how abnormal . k '4'1 operating procedures are used in ; conjunction with EOP's. >:.

AK3.08 -Actions contained in EOP for . 'iL' loss of instrument air ,. " EK2.2 -Facility's heat removal if . <

• systems. including primary coolant, f*,

emergency coolant. the decay heat J . removal systems. and relations , between the proper operation of these I.';'" systems to the operation of the facility X 2.1.7 -Ability to evaluate plant performance .. t' and make operational judgments based on operating characteristics. reactor behavior. and instrument interpretation. Imp. Point 2.6 4,2 3,9 4.2 3.9 2,9 2.6 4.2 3.4' 4.1 4.1 3,7 3.8 3.7 3.8 4.4 PWR RO Examination Outline Printed Facility: Pr211rie Island ES *401 Emergency and Abnormal Plant Evolutions -Tier 1 ! Group 1 Form ES*401-2 -E/AP E # I Name I Safety Function K1 -.-----------------1 Loss of Emergency Coolant I WfE1 Recire -' /4 -. Uncontrolled Depressul'lzation of WIE12 all Ste am Generators I 4 KIA Category Totals: 3 K2lt' .... A2 _ .. I ), X I : . . '. 3 3 G KATopic Imp. EK3.3 -Manipulation of con trois 3.8 1 required to obtnin desired operating results during abnormal. and emergency situations -il EK3.1 Facility oper. characteristics 3.5 during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating lifmtations and reasons for these operatino .. characteristics "'w_. ___ ___ "_"' .. ___ ________ ------.-----.... -3 Group Point Total: 18 .. ... --...... .... .. PWR RO Examination Outline Printed Facility: Prairie Island ES *401 Emergency and Abnormal Plant Evolutions* Tier 1 I Group 2 Form ES-401*2 E/APE # I Name I Safety Function K1 K2 K3 A1 'FA,2 'i': " G, KATopic Imp. Point " :>' , ',' ";:', : , 3.2 000001 Continuous Rod Withdrawal I 1 X AK3.01 -Manually driving rods into 1 o position that existed before start of '. casualty " 'n 000005 Inoperable/Stuck Control Rod I 1 X AA 1.01 -CRDS 3.6 1 000028 Pressurizer Level Malfunction I 2 X., 2.4.31 -Knowledge of annunciator 4.2 1 2 ., alarms, indications, or response procedures).

,," , ; " 000059 Accidental Liquid RadWaste ReI. I X AK1.01 -Types of radiation, their units 2.7 1 9 , i of intensity and the location of the sources of radiation in a nuclear eY c.' power plant !' " 000076 High Reactor Coolant Activity I 9 X Ie;

; ;,A;: AK3.0S -Corrective actions as a 2.9 1 , "if"; result of high fission-product radioactivity level in the RCS W/E06 Degraded Core Cooling 14 X EA2.2 -Adherence to appropriate 3.S 1 ,; procedures and operation within the .'1,' ' limitations in the facility's license and '"f;;, amendments

"" W/E10 Natural Circ.,With steam void in X , EK2.2* Facility's heat removal 3.6 1 vessel with/without RVLlS ( 4 " ' systems, including primary coolant, emergency coolant, the decay heat , removal systems, and relations

0,t; between the proper operation of these systems to the operation of the facility " W/E13 Steam Generator Over-pressure X !er';l , EK2.1 -Components, and functions of 3.0 1 14 ,; control and safety systems, including i "'l;c" :,%,"' instrumentation, signals, interlocks, failure modes, and automatic and "[ d manual features 'l W/E16 High Containment Radiation 19 X EA2.2

• Adherence to appropriate 3.0 1 procedures and operation within the c limitations in the facility's license and "i: amendments cC KIA Category Totals: 1 2 2 1 1; Group Point Total: 9 PWR RO Examination Outline Printed Facility:

Prairie Island Plant Systems. Tier 2 I Group 1 Form ES-401-2 Imp. Point .6 1 2.8 1 K50? . Helationshlp between SUr.::: and reactlvit) .. --'+-----+----. K3.01 -ReS 3. 1 006 Emergency Core CoolinG K6.02 . Core flood tanks 34 1 (accumulators) 1-----------------+----+---- -.+---1----+---1---+----11---------1---.+,.- .. : . .:..---.*.. ---.-.:.--- ... -.-----.-+---.....-4----- 007 Pressurizer ReliefiQuench X K3.01 . Containment 2.5 Tank r* -----... .. -_+_--:I--_+--+-........j-----------+--- A2.08 -Effects of shutting (auto or otherwise) the isolation valves of the letdown cooler 008 Component Cooling Water x 1 -1 ***--*---*----*--*-------*--+-+--_+--1--+-_+--1--+-4-*-1--+-+*---------_t_----t-----. 010 Pressurizer Pressum Control .'. X 2.4.11* Knowi"df)* of 'lbnoflna! . condition proCBdurns. r---------c-.-- .. -,.""'+-4--f.---l---\--I--1--4--+- .. ......-JI--4---- 010 Pressurizer Pressure Control X K4.o3 -Over pressure ......... control 4.0 1 3.8 1 3.8' 1 012 Protection X K1.05 ESFAS 013 Engineered Safety Fe8!uros Actuation 022 Containment Coolinq x x K2.01 .. ESFAS/safeguards equipment control K1.04 -Chilled Water 3.6' I 29* 1 --.---+----- 026 Containment Spray x A4.05 ' Containment spray reset switches t---------------+--+-+----+-_i_-+--+.-+--.;..I--+-.+--+-.-----c-- .. -.. --026 Containment Spray x A 1.05 c ChemiGal additive tank lever and concHntration 3.5 1 31 1 .. --.---.. 039 Main and Reheat Steam x K4.07 --Reactor isolation A3.06 -Feedwater Isolation 3.4 1 -3.2' 1 059 Main Feedwater X 1------------.--.--+--\--+--- .-.-f--------"-----i---.-!--I------.----------/C-.......::......f-.-.- 3.1' 1 059 Main Feedwater X K4 .16 --Automatic Trips for MFW pumps .. 061 Auxiliary/Emergency X K5.05 . Feed line voiding 27 ., Feedwater and water hammer 3.3 1 Auxiliary/Emergency X 2.4 .18 -Knowledge of lhe " I i specific bases for EOPs. 3.3 1 062 AC Electrical Distribution X .... K2.01* Major system loads I------.---.--- .. --.-... . 063 DC Eleclri,.al Distribution X 1'.201 .. Grounds ,,') r "',,) 1 Distribution 064 Emergency Diesel Cenerator Old Service Water .... 07B Instrument Air A4.03

• Battery discharge rate X :r 1 ,23 --Ability to perform systfHD i:.Hld :'oteprat(\(1 pl,,1nt prOC{:;dt.ircs during alJ rnodes or D18nt operation.

A201 -. Loss 01 SWS K302** Systems having pntwmatic vaiw"s and f:.nnrrol" 3.0' 1 43 1 "' .! , _ ,c*_'_ 3:,) 3-. ., , 3.4 1 .,.. Facility: Prairie Island ES 401 . SyslEvol # I Name K1 -,--07e Instrument Air 103 Containment KIA Category Totals: 3 ---.. ""'-PWR RO Examination Outline Plant Systems .. Tier 2 I Group 1 K2 K31 K4 K5 K6 Ai A2 A3 A4 """'--,....-_. i----.' ",-.,,----__ ," X X 2 3 3 2 2 3 3 2 2 G 1--3 Printed (c,O Form ES*401*2 I KA Topic Imp. 1-----------I---;'\3,01 ,. Air pressure 3.1 A 1.01 " Containment 3.7 pressure, temperature, and , J humi(jity Group Point 2 8 I _.". '-__ __ c.,_ .. _ "",. __ '-'_ L..-, ___ , ___ ., ___________ ,, __ . 2 111'1'" PWR RO Examination Outline Printed (Co Facility: Prairie Island ES*401 Plant Systems* Tier 2 I Group 2 Form ES-401*2 t, Sys/Evol # I Name K1 K2 K3 K4 K5 K6 A1 A3 A4 >G; KATopic Imp. Point 001 Control Rod Drive X K4.15 -Operation of 2.7 1 latching controls for groups and individual rods 002 Reactor Coolant X K5.19 -Neutron 2.6 1 embrittiement 015 Nuclear Instrumentation X ,.M K1.03 -CRDS 3.1" 1 027 Containment Iodine Removal X ,), , K2.01 -Fans 3.1* 1 029 Containment Purge X i% 11 K3.01 -Containment parameters 2.9 1 035 Steam Generator X K6.02 -Secondary PORV 3.1 1 045 Main Turbine Generator "} X A3.11 -Generator trip 2.6* 1 055 Condenser Air Removal I X 2.2.44 -Ability to interpret control 4.2 1 r c room indications to verify the status and operation of a system. :"" and understand how operator I' actions and directives affect plant and system conditions. 068 Liquid Radwaste X ,,;., A4.02 -Remote radwaste 3.2" 1 release 086 Fire Protection X A 1.04 -Fire dampers 2.7 1 KIA Category Totals: 1 1 1 1 1 1 1 < 0 1 1 1 Group Point Total: 10 '" ES-401 PWR Examination Outline Form ES-401-2 Facility: Prairie Island Printed: Date Of Exam: March 2010 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 IKSl K6 A1 A2 A3 A4 G* Total A2 G* 1. 1 0 0 0 0 0 0 0 3 3 Emergency 2 0 0 0 0 0 0 0 2 2 & N/A N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 S Evolutions

2. 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 I 2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 Plant Systems Tier 0 0 0 0 0 0 Totals 0 0 0 0 0 0 S 3 3. Generic Knowledge And 1 2 3 4 1 2 3 4 0 Abilities Categories 0 0 0 0 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-onlyoutlines (Le .. 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 +/-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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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 KlAs 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 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. Refer to Section D.1.b of ES-401 for the applicable KJAs. 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 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-onlyexams.

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. Umit SRO selections to KlAs that are linked to 10 CFR 55.43. Total 6 4 10 5 3 8 7 (t 0 PWR SRO Examination Outline Printed Facility: Prairie Island ES *401 Emergency and Abnormal Plant Evolutions* Tier 1 f Group 1 Form ES401-2 -K2[ K3 ---E/APE # / Name I Safety Function K1 A1 A2 G KA Topic Imp, Point I ..... ! f--*_--r--**-l

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11 -._-000009 Small Break LOC,'; i 3 .X EA2.01 .. ,L\ctions to be taken, based 4.8; on f;:CS !empC-lr8ture and pressure, saturated and superheated

-000015/0000 17 Malfunctions / 4 X AA2.02 . Abnorrnalities in Rep air vent flow paths imd/or 011 cooling .. 1---_.- W!E12 Uncontrollnd Dopressurization of X 2.4.4'1

• Knowledge of the enlerge!l1cy 4.6 1 all Steam Generators

/4 action level thresholds and

• classifications, ----. --f--._-000056 Loss of Off-site f)ower; 6 X 2.2.39 . Knowledge of less than or 4.5 1 equal to one hour T. S. action .. statements for systems. _. ---000057 loss of Vital AC Inst. E3us / 6 X 2.4.9 -Knowledge of low 4.2 1 .... power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat rernov;;1/)

... mitigation strategies . ..... ------"-" f--._--000077 Generator Voltage ane! Electric X AA2.09

• Operational status of 4.3 1 Grid Disturbances I 6 emergency diesel generators KIA Category Totals: 0 0 0 0 3 ****3 Group Point Total: 6 .. _-,

PWR SRO Examination Outline Printed Facility: Prairie Island ES .401 Emergency and Abnormal Plant Evolutions* Tier 1 I Group 2 Form ES-401*2 E/APE # I Name I Safety Function K1 K2 K3 A1 A2 i*G KATopic Imp. Point .. . 000024 Emergency Boration /1 l"" \X 2.4.4

• Ability to recognize abnormal 4.7 1 indications for system operating

., parameters that are entry-level ' .. conditions for emergency and ; i abnormal operating procedures. ,Ii 000051 Loss of Condenser Vacuum 14 " I' AA2.02 -Conditions requiring reactor 4.1 1 X and/or turbine trip ',' 000067 Plant Fire On-site / 8 ; ". *X" 2.2.40 -Ability to apply Technical 4.7 1 . Specifications for a system. 000069 Loss of CTMT Integrity 15 >S',. Ii' AA2.02 -Verification of automatic and 4.4 1 ..: manual means of restoring integrity KIA Category Totals: 0 0 0 0 ""2* i¥.2+ Group Point Total: 4

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

PWR SRO Examination Outline Printed Facility: Prairie Island ES*401 Plant Systems* Tier 2 I Group 1 Form ES-401-2 Sys/Evol # I Name K1 K2 K3 K4 K5 K6 A1 A!). A3 A4 G. KATopic Imp. Point 003 Reactor Coolant Pump X 2.4.1 -Knowledge of EOP 4.8 1 entry conditions/1m. actions 007 Pressurizer Relief/Quench X A2.06 -Bubble formation in 2.8 1 Tank PZR 008 Component Cooling Water Ii ,("< X 2.1.20 -Ability to interpret 4.6 1 and execute procedure (" steps. 062 AC Electrical Distribution A2.16 -Degraded system 2.9 1 .".i voltages 103 Containment o'X fi A2.01 -Integrated leak rate 2.6" 1 . j test KIA Category Totals: 0 0 0 0 0 0 0 03 0 0 '2 Group Point 5 I* PWR SRO Examination Outline Printed (...0 Facility: Prairie Island ES -401 Plant Systems -Tier 2 I Group 2 Form ES-401*2 Sys/Evol # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp_ Point 028 Hydrogen Recombiner and .x A2.01 -Hydrogen 3.6* 1 Purge Control " ,:. recombiner power setting. " determined by using plant data book 071 Waste Gas Disposal 'l \ A2.0S -Meteorological 2.S* 1 changes 075 Circulating Water X 2.1.27 -Knowledge of 4,0 1 system purpose and/or '; function. > > KIA Category Totals: 0 0 0 0 0 0 0 21' 0 0 Group Point 3 Generic Knowledge and Abilities Outline (Tier 3) PWR RO Examination Outline Printed: Facilioc Prairie Island Form ES-401-3 KA Topic ,......--I I Conduct of Operations 2.1.29 Know le dge of how to conduct system lineups , 4.1 1 such as val v es , breakers , switch e s, etc. 2.1.4 1 Know le dge of tile refueling p roc ess. 2.8 1 Category Total: 2 --trol 2.2.6 Knowledge of the proCE,SS for making changes 3.0 1 t o procedures. 2.2.20 Knowledg e of the proces s fo r m anaging 2.6 1 troubleshooting activities. ----2 2.36 Ability to ana l yz e the e ffe c t of maintenance ? " ". I 1 activities , s uch as degraded power sources, on til e status o f limiting co ndit io n s f or operations. --'----.-.-Category Total: 3 -Radiation Control 2.3.11 Ability to co ntr o l radiation releases. 3.8 1 2.3.1 4 Knowledge of radiati on or con tamination 3.4 1 hazards th a t may ar is e during normal, abnormal , or e mergency co nditions or activities Category Total: 2 --Emergency Procedures/Plan 2.4.2 Knowledge of system se t pOints, inte rl ocks and 4.5 1 automatic actions assoCiated with EOP entry conditions. 2.4.6 Knowledge of EOP mitigation stra t egies. 3.7 1 2.4.42 Knowledge of emergency respon se f acilities. 2.6 1 Category Total; 3 --Generic Total: 10 Generic Knowledge and Abilities Outline (Tier 3) PWR SRO Examination Outline Printed: Facility: Prairie Island Form ES-401*3 Generic Cateaorv KA KAToDic l.!:!:J.Q. Points Conduct of Operations 2.1.5 Ability to use procedures related to shift 3.9 1 staffing, such as minimum crew complement, overtime limitations, etc. 2.1.14 Know/edge of criteria or conditions that require 3.1 1 plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. Category Total: 2 Equipment Control 2.2.18 Knowledge of the process for managing 3.9 1 maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc. 2.2.35 Ability to determine Technical Specification 4.5 1 Mode of Operation. Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.7 1 normal or emergency conditions. Category Total: 1 Emergency Procedures/Plan 2.4.11 Knowledge of abnormal condition procedures. 4.2 1 2.4.50 Ability to verify system alarm setpoints and 4.0 1 operate controls identified in the alarm response manual. Category Total: 2 Generic Total: 7

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o Scenario Outline Scenario No.: Up-fest No' Examiners, Operators: Event Malf. Event Event No. N/A increaSfl Power to 60% Place Second Main Feed purnp in service. RX226 Turbine 1 st Stage Pressure (PT -485) Fails High. SI Pumps fBil to auto starl. NUf:;EG 1021, HovisiOn f) ..................*.....*.* _ ......... _---------------------

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Scenario 1 Summary The crew assumes H18 duty at 50(% power with xenon increasing, equipment OOS. The crelN is directed to increase power to DUring the power rise a st:?cond maill feedwater pump will bt.::! started After the crew has completed the power increase, 11 Charging Pump Trips. The RO will stabilize seal injection flows and/or start 13 charoing pump. The crew responds lAW C4l and 1C12.1 After the plant is stabilized, Turt)ine First Stage Pressure channel (PT-485) fails high. The RO will take rod control to manual and stabilize charging.

The BOP will address the instrum('.mt failure anc! swap steam clumps to Pressure Mode. The SRO will detEmnine TS. requirements After the plant is stabilized, a 20 gpm RCS leak develops. The SRO will detfHmine T.S, requirements. The crew responds lAW 1 C4 AOP 1. After tht-) crew identifies thC! T.S requirements for the RCS leaK, a Sma!1 Break LOCA occurs. The crew will trip the reactor arId enter 1 E-O. Upon the trip, BOP will recognize the turbine fails to auto trip and both SI pumps fail to auto start and perform manual actions to remedy these failures. The crew wiH transiHon to 1 E*1 and the scenario will continue until safeguards pumps are stopped In 1 F R -P.1 or the first SI pump is stopped in 1 ES-1.1. Critical Tasks: E-O --H: Manually start at least one safety Injection pump before transition out of E**O. E-O --TCOA4: Control AFW flow within 38 minutes following a Reactor Trip (SWI 0-35 identified Time Critical Operator Action). E-O --0: Trip turbine before leaving E-O. E-1--C. Trip all Reactor Coolant Pumps so that a severe challenge to Core Cooling does not occur when forced circulation in the ReS stops (Small Break LOCA) NUF{EG 10:2 1. n o Scenario Outline Facility: Prairie Examiners" Operators: Initial Conditions: Turnover: Event Malf. Event Type"' Event No. FW13A R (RO) 11 Main Feedwater Pump Trip. Power Range Ni Fails High NUREG 1021, Revision 9 I Scenario 2 Summary The crew assumes the duty at 71 % power and stable. 11 CC pump is OOS. After the crew takes the duty, 11 MFW pump will trip. The RO will reduce power to -50% using lAW 1 C1.4 AOP1. BOP will address the ARP for the failure and manipulate control room switches as necessary to facilitate trouble shooting and ensure proper system response. After the crew has completed the power reduction, N44 Power Range NI Fails High. The BOP will address the failure and remove the affected channel from service lAW C47 and 1 C51. The RO will place rod control to manual and restore Tave to Tref. The SRO will determine T.S. requirements After the NI failure is addressed, Instrument Bus 113 loses power. The loss of Bus 113 compounded with N44 being OOS causes an automatic reactor trip. The crew will respond lAW 1 E-O and transition to 1 ES-0.1. The 88 will direct performance of 1 C20.8 AOP1 to restore power to Instrument Bus 113 in conjunction with 1 E8-0.1. After power is restored to Instrument Bus 113, 11 S/G Main Steam line break in containment. The crew will transition back to 1 E-O. The BOP will recognize the failure of 11/12 MSIV's to auto close and manually perform the action using 1 E-O Att. L. The crew will then transition to 1 E-2 to isolate the faulted SG and transition to 1 E-1. The scenario will be terminated when the crew transitions to 1 FR-P.1 or upon termination of 81 pumps in 1 ES-0.2. Critical Tasks: E-O --P: Manually close MSIVs before transition out of E-O. E-O -TCOA4: Control AFW flow within 38 minutes following a Reactor Trip. (8WI 0-35 identified Time Critical Operator Action). E-2 --A: Isolate the faulted STEAM GENERATOR before transition out of E-2. NUREG 1021, Revision 9 Supplement 1 K.o Appendix 0 Scenario Outline Form ES*D*1 Facility: _Prairie Island Scenario No.: 3 Op-Test No.: _ 1 Examiners: Operators: Initial Conditions: Power is 1x10.s amgs and stable Turnover: 13 Charging PumQ is OOS Event Malf. No. Event Type* Event No. Description 1 N/A R (RO) Increase Power to POAH. N (SRO. BOP) 12 Condensate pump will be started to replace 11 for Filter Demin Support. 2 IA03B C (BOP) 122 Air Compressor trips 123 fails to auto start. 3 DI-462420FF C (RO) PZR Heater B/U Group 1 B Breaker Trip. TS (SRO) 4 RX202 I (RO) PZR pressure channel (PT -431) fails High. TS (SRO) 5 SG02B M (All) 12 S/G Tube Rupturelon trip). 6 RP12 C (BOP) SI signal CL System Fails. . (N)ormal, (R)eactivity, (I}nstrument (C}omponent, (MJaJor NUREG 1021, Revision 9 Supplement 1 an, Scenario 3 Summary The crew assumes the duty wHh power at i x1 arnps and stable. 13 Charging Pump is OOS. The crew is directed to increase power to the POAH. During the power rise the BOP will start 12 Condensate pump and stop 11 Condensate pump. After the crew has completed the power increase, 1 Air Compressor trips with the 123 AIC failed to auto start The BOP will that 123 Air Compressor does not autornaUcally start and will manually start 123 Air Compressor. The crew responds lAW C47 and C34 AOp*l After the plant is stabilized, PZR Heater BtU Group 1 B Breaker will trip. The RO wi/i co-ordinate with the BOP to align the heater group to the alternate power supply and restore the heaters to operation lAW 1 C20.6. The SRO will determine T.S. requirements After the plant :s stabilized, the controlling pressurizer pressure channel 1 P-431 fails Higll The RO will respond to stabilize ReS pressure. The RO and BOP wiH coordinate to swap the controlling pressurizer cflannel to another channel lAW C47 and 1 C51.3. The SRO wi/! determine TS. requirements. After the plant is stabiliz.ed. 12 SfG will suffer a Tube Rupture TIle crew will trip the reactor and enter 1 E-O. The BOP will recognize thH CL systerns fails to respond to the SI signal and will manually align the system lAW 1 E-O At! L. The crew wiH transition to 1 E*3. The scenario will be terminated upon securing SI pumps in 1 E-:3. Critical Tasks: E-O --TCOA4: Control AFW flow within 38 minutes following a Reactor Trip. (SWI 0-35 identified Time Critical Operator Action). E-3 --A Isolate feedwater flow into and steam flow from the ruptured Stearn Generator before a transition to ECA-3 1 occurs. E-3 B: Establish/maintain an RCS temperature so that transition from E-3 does not occur because of the inability to maintain required subcooling or sudl that an extreme or severe challenge to the Subcriticality< and/or the Integrity CSF occurs, [-3 --C: Depressurize RCS to rneet SI termination criteria prior to overfilling U"\e ruptured Steam Generator. -D: Terminate 81 prior to overfillinG the ruptured Steam Generator NUHEG '1021, HeViSion 9 III Facility Prairie __ .. __ ...... " ............ _... Scenario No .. Op-Test No.' EX.arruner*s: Initial Conditions: 3 4 Malf. No. NI/\ RX216 RX05C TC12, RP07/\ RP07B. 01-464478, OQ()b Power and Event M (All) NUREG '!O21, 9 Supplemef1t1 Operators: Event Reduce Power to 90'10 for 12 Heater Drain Pump brush 95% the BOP I"ernove 12 Heater DrEJin Pump from service. Loss of SaterJuan!s Bus 16. 12 S/G Pressure Instrument PT*478 Fails High. causing 12 S/G PORV to open. Tavg Instrument Faiis High. Turbine Trip with ATWS. I I I I j R..o Scenario 4 Summary The crew assumes the duty at 100% power and stable. 11 MDAFW pump and 13 Heater Drain pump are OOS. The crew will Reduce Power to 90% to remove 12 Heater Drain pump from service for brush inspections. After the power reduction, Loss of Safeguards Bus 16 occurs. D2 DIG starts and does not auto load. The RO will stabilize RCP seal injection flows. The BOP will restore power to Bus 16 by restoring power from CT-11 lAW 1C20.5 AOP2. The SRO will determine T.S. requirements. After Bus 16 is restored, 12 S/G Pressure instrument PT-478 Fails high causing 12 S/G PORV to open. The BOP will recognize the failure and manually close 12 S/G PORV. The SRO will determine T.S. requirements After the plant is stabilized, RCS Loop Thot RTD fails high causing Tavg and Delta T channels to indicate high. The RO will take manual control of charging and rod control. The BOP will coordinate with the RO to take the appropriate channel to 'defeat'. The SRO will determine T.S. requirements After the plant is stabilized, a spurious turbine trip signal occurs. The turbine will trip but the reactor does not. The Crew will enter 1 E-O and transition immediately to 1 FR-S.1. The RO will recognize the A TWS and attempt to manually trip the Reactor, but will be unsuccessful. Rods will be inserted and a boration commenced lAW 1 FR-S.1. The BOP will recognize the 11 TDAFW pump failed to automatically start and will manually start the pump. The scenario will be terminated upon successful tripping of the Reactor per 1 FR-S.1 Critical Tasks: E-O -TCOA4: Control AFW flow within 38 minutes following a Reactor Trip. (SWI 0-35 identified Time Critical Operator Action). FR-S.1 -C: Insert negative reactivity into the core by inserting rods or establishing emergency boration flow to the RCS during the performance of FR-S.1 . NUREG 1021, Revision 9 Supplement 1 ... Appendix 0 Scenario Outline F orm E S-O-1 -_._---_._. ._._-----II F "'t P -. 'I ._. !I aC 1 1 y: __ ra l ne I S a nd !i r Examiners: =-=-====-==:.:_. __ Scenari o No.: Op-Test No.: SB Operators:

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_._--i l II i I I I n i ti al Co n d i tions: __ 71% Powe r and stablc. ____ _ --------_._--: I ... -----.-.. ----.--.---I Turn ove r: --.1LtylDAF;W P1Jmp j s OQS, . . __ . _. __ . _______ . _____ . __ . ___ _ II __ .. __ Breaker i:::..5--"'0'-" 0'--" S'--___________ _ I' .. _ .. _--+------+-_. __ ._.--------_ ... _--_._ .. __ ... __ ... _----._----------_._-i....: 2=---. __ f---'-R_:.:::: D--=.O::;..90::..:9::....-.-+-...:::::..

C (R01_--+_R.....;o...:;..d_F_-6;;....R'-P'-I_F...;;.ac.;. il.s;;.;... ------------.--.--.----.---H 3 TC07B, TC07e R (RO) I Tw o Turbine Interce pt Valve s fail closed. C (S RO) I *------r-------+-------+-------------------------------41 -+/--______ SJ_ROL I so lat io n V alv e fails _______ . ________ _ ------t-----------+-----------*f-----------------.. *--------.. *--------------------*-------*-----------;1 5 Rp03F ___ _ yYithdraw a l ___________________ _ -----+--_._ .. -6 RC 07A . __ 1 M (A l l) i LBLOCA. -*-------------------;1 .. NU R EG 1021 , 9 Supplement 1 ---------_.--........ _. Scenario SB Summary The crew assumes the duty at 71 power and stable. 12 MDAFW pump and Breaker 16-10 are OOS. After the crew assumes the duty. PZH PORV PCV-431 C starts leaking by. The RO will recognize the failure and coordinate with the BOP to close the associated block Vel:ve lAW C47 and 1 C4 AOP1. The SRO will delerrnine T.S. requirements. After the plant is stabilized, Rod F*6 RP! fails to zero. The RO will n:.,cognize the failure and coordinate with the BOP to respond lAW C4-r and 1 C5 AOP4 & AOP5. The SRO will deterrnm.e T.S. requirements. After the plant is stabilized, two Turbine Intercept valves fail closed. The BOP will recognize the failure and respond per C4? anej 1 C23 AOP2 to determine a rapid downpower is reqwmd. The RO will reduce power below 50%) lAW 1 C1.4 AOP1. After the plant is stabilized, a letdown line isolation valve fails closed, The will recognize the failure and coordinate with the BOP to place excess letdown in service lAW 1C*12.1 AOP3. After the plant IS stabilized, a continuous uncontrolled rod wiUldrawal occurs. The RO will recognize the failure and place Rod control in manual. Rods will continue to wIthdraw and the crew will respond lAW 1 C5 AOP1 and trips reactor and enters 'I E-O, After the crew trips the reactor, a large break LOCA occurs, The crew wilt continue in 1 E-O and transition to E .. 1, The BOP will recognize automatic containment isolation signal fails to actuate and the Lead operator will ensure all containment isolation valves are closed lAW E-O AlL L The crew will transition to 1 ES-1.2. The scenario will be terminated when one safeguards train has been restarted on recire sump B. Critical Tasks: E-O --0: Manually actuate Containrnent Isolation or close containment isolation valves such that at least one valve is closed on each penetration before the end of the scenario. [-0 -. TCOA4: Control AFW flow within 38 minutes following a r.:ceactor Trip. (SWI 0-35 identified Time Critical Operator Action). 1021, Revision H .., ...... jn ............

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