Text

Examination Outline Submittal for the Prairie Island Initial Examination - August 2005
	ML052900478
Person / Time
Site:	Prairie Island
Issue date:	04/01/2005
From:	Solymossy J; Nuclear Management Co
To:	; Region 3 Administrator
Shared Package
ML052720166	List: L-PI-05-078, Facility Post-Examination Comments for the Prairie Island Initial Examination - August 2005; ML052900478; ML052900501; ML052910092; ML052910118;
References
	50-282/05-301, 50-306/05-301
	Download: ML052900478 (31)
	v • d • e

EXAMINATION OUTLINE SUBMITTAL FOR THE PRAIRIE ISLAND INITIAL EXAMINATION - AUGUST 2005

PRAIRIE ISLAND Outline Submittal Contains the following:

Station Cover Letter transmitting the outline ES-201-2 ES-301-1 ES-301-2 ES-301-5 ES-401-2 ES-401-2 ES-401-3 D-1 Examination Outline Quality Checklist Administrative Topics Outline (RO) (SRO)

Control Room and Facility Walk-Through Test Outline (RO)

(SRO-I) (SRO-U)

Transient and Event Checklist (3 Checklists)

PWR RO Examination Outline PWR SRO Examination Outline Generic Knowledge and Abilities Outline (RO) (SRO)

Dynamic Simulator Scenario Outline for 5 scenarios There were no NRC comments on the Outline Submittal

APR 0 1 2009 L-PI-05-024 NU REG-I 021 Regional Administrator U S Nuclear Regulatory Commission Region 111 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 Prairie Island Nuclear Generating Plant Dockets 50-282 and 50-306 License Nos. DPR-42 and DPRBO Examination Material for Prairie Island Initial License Examination. Weeks of Auqust 8 and Ausust 15,2005 Enclosed are the integrated examination outlines for the initial license examination to be administered at our facility the weeks of August 8 and August 15, 2005. This information is being provided in accordance with guideline ES-201 of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9.

NUREG-I 021 physical security requirements state that the enclosed examination materials shall be withheld from public disclosure until after the examination is complete.

Please direct any questions or comments regarding this material to Bill Markham at 651-388-1 165, ext. 5277.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

lear Generating Plant cc:

Dell McNeil (NRC Chief Examiner) w/attachments 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ES-201 Examination Outline Quality Checklist Form ES-201-2 Item

1.

W R

I T

T E

N

2.

S I

M U

L A

T 0

R

3.

W I

T

4.

G E

N E

R A

L -

Date of Examination I

Task Description a

a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401

~

b. Assess whelher the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KIA categories are appropriately Sampled.

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

d Assess whether Ihe justifications for deselected or rejected WA statemenls are appropriate. A a

Using Form ES-301.5. verify that the proposed Scenario Sels Cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.

b. Assess whether there are enough scenario sets (and spares) lo tesl the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule withoul compromising exam integrity, and ensure that each applicant can be tested using at least one new or significanlly modified scenario. that no scenarios are duplicated from the applicants audit lest(s), and that scenarios will not be repeated on subsequent days.

To the extent possible, assess whelher the oulline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-3014 and described in Appendix D.

v t

c

~~

~

a b w l, mal rne sbslems nalh-lnrmgh ourl ne meets tne criteria specfiea on Fcrm ES-301-2 I 1, tnt 0.llmq51 conla 01s. Ine rcqLlie0 nunoer of control room ana on-plant lash?.

a strio~tco among Ine salel, functons as specifieo on the form (2

lass repelil on lrom Ine,as1 WO NRC exammations s wlhm tne I m Is speclfieo on the lorn

,3.

no lash5 are aLp catba from tne applicants am1 lestls)

,41 me n m c e of w w or mouilca tasks meets or excess me rn nimms speofied on lhe form 151 Ine nrmDel 01 atcrnale pain iowpower emergency. ana RCA tascs meet tne crleria on the form berily that tne aom nostrat.e o.tline meels the crilena specifiea on Form ES-301-1

( I, me lash5 are d~StriOLtea among the Iop#cs as spec,fied on the lorm (21 at east one rash IS neb or s gnf,cantly moafiea (3, no more than one la% s repeatea from the last two hRC licensing examlnat.0ns Delcrm ne I there are enmgn 0 fferent orllineS lo tesl Ine pr0,eCIea nLmDer and m x 01 app #cants and ensure that no lems are duplicatec on sc.bSeqrent days Assess nhether plan1.spec.f c pr orit es (mdud.ng PRA and PE Ins!gnlsJ are Cokerea n tne appropr ate exam sed ons Assess +nether the 10 CFR 55 41.43 and 55.45 %ampling 1s appropnale Ensure rhal I( A Imporlance ratings (excepl for plant-speclfic prmt es) are at least 2 5 Checs lor d.pl.calmn m u overlap among exam sec11ons W

ff o

c a

D c

0 jl J#,

v

e. Check the entire exam for balance of coverage.

1.

Assess whelher the exam fits the appropriate job level (RO or SRO).

1 %

U Date

a. Author g&&-

b. Facility Reviewer c)

c. NRC Chief Examiner I#)

d. NRC SupeNiSor Note:

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

ES-201, Page 25 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Prairie Island Examination Level (circle one):

Administrative Topic Type (see Note)

Code*

Conduct of Operations RO-A-1 D, P Conduct of Operations RO-A-2 D, S Equipment Control RO-A-3 N, S Radiation Control RO-A-4 D

Emergency Plan NIA Date of Examination: 8/1/05 Operating Test Number: __

Describe activity to be performed ADMIN-10, Determine Maximum RCS Venting Time 2.1.23 (Classroom)

ADMIN-5S, Establish Appropriate High Flux at Shutdown Setpoint 2.1.30 (Simulator)

FH-3S, Perform SFP Fuel Handling Checklist 2.2.26 (Simulator)

ADMIN-8, Conduct an Emergency Radiation Survey 2.3.10 (In-Plant)

~

NIA NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking onlv the administrative touics. when 5 are reauired.

Type Codes & Criteria (C)ontrol room (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (2 1; randomly selected)

(S)imulator ES-301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Examination Level (circle one): RO Facility: Prairie Island Date of Examination: 8/1/05 Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note)

Code*

Conduct of Operations SRO-A-1 D

Conduct of Operations RO-A-2 D, S Equipment Control RO-A-3 N, S ME-1, Respond to a Medical Emergency 2.1.8 (Classroom)

ADMIN-SS, Establish Appropriate High Flux at Shutdown Setpoint 2.1.30 (Simulator)

FH-3S, Perform SFP Fuel Handling Checklist 2.2.26 (Simulator)

Radiation Control ADMIN-37, Authorize Emergency Exposure (Classroom)

SRO-A-2 N

2.3.1 Emergency Plan SRO-A-3 N

ADMIN-39, Issue Updated PAR based on Wind Change 2.4.44 (Classroom)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking onlv the administrative touics. when 5 are reauired.

Type Codes & Criteria (C)ontrol room (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (I 1; randomly selected)

(S)imulator ES-301, Page 22 of 27

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 System I JPM Title Type Code*

Facility: Prairie Island Exam Level (circle o n e j B S R O ( 1 ) / SRO(Uj Date of Examination: 8/1/05 Operating Test No.:

Safety Function

~

a. CVCS / FL-IOSF-3, Line up RWST to Charging During an ATWS RO-S-1 ESFAS I EO-31SF-2, Attachment L, Steam Line Isolation Failure RO-S-2 ECCS / SI-13s. Inadvertent Safety Injection Actuation RO-S-3 Condenser Air Removal / ARS-I, Condenser High Pressure RO-S-4 D, A, S 2

N, L, E, S 3

D, S, P 4b

b.

c.

d.

N. A, S

e.

f.

PRT I RC-22SF-I, Lower PRT Level RO-S-5 AC Electrical Distribution / EA-5s. Transfer Safeguards Power to Offsite Source 5

From Diesel Generator RO-S-6 Reactor Protection I FL-2OSF-2, Ejected Control Rod With RPS Failure RO-S-7 Liquid Rad Waste / WD-IS, Terminate Accidental Radioactive Liquid Release RO-S-8

g.

h.

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow power (N)ew or (M)odified from bank including I(A)

(P)revious 2 exams (RjCA (S)imulator D, S 6

N, L, A, S 7

D, S 9

4-6 14-6 / 2-3 i,

Hydrogen Recombiner / HC-I, Startup Hydrogen Recombiner RO-S-9 AC Electrical Distribution / IP-3, Respond to Bypassed Instrument Inverter RO-S-IO Cooling Water I F5-9. F5 Appendix B, Attachment C, Unit 1 RO Actions RO-S-11

j.

k.

5 9 / 5 8 / 5 4

> I / > 1 / 2 1 2 I / 2 1 / 2 I 2 2 / 2 2 / 2 1 5 3 / 5 3 I 5 2 (randomly selected) 2 I / > l / t I D, R 5

N. E 6

D, P, E 4b ES-301,23 Of 27

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 System / JPM Title Type Code*

Safety Function D. A, S D, A, S

a.

CVCS I FL-IOSF-3, Line up RWST to Charging During an ATWS RO-S-I ESFAS I EO-3 ISF-2, Attachment L, Steam Line lsolation Failure RO-S-2

b.

I 2

N, L. E, S D, S, P

c.

d.

ECCS / SI-13S, Inadvertent Safety Injection Actuation RO-S-3 Condenser Air Removal I ARS-1, Condenser High Pressure RO-S-4

~~~

In-Plant Systems (3 for RO: 3 for SRO-I; 3 or 2 for SRO-U) 3 4b

i.

Hydrogen Recombiner I HC-1, Startup Hydrogen Recombiner RO-S-9

f.

AC Electrical Distribution / EA-5s. Transfer Safeguards Power to Offsite Source From Diesel Generator D, S 6

functions may overlap those tested in the control roi

Type Codes N. L. A, S

g.

Reactor Protection / FL-20SF-2, Ejected Control Rod With RPS Failure RO-S-7

h.

Not Administered to SRO-I (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 7

ES-301,23 Of 27 D. E

k. Aux Feed Water / F5-7, F5 Appendix B, Attachment A, Unit 1 SS Actions SRO-S-I 4b

ES-301 Control Room I In-Plant Systems Outline Form ES-301-2 System / JPM Title Type Code*

Safety Function D, A, S

3.

CVCS / FL-IOSF-3, Line up RWST to Charging During an ATWS RO-S-I

b.

Not Administered to SRO-U I

N, L, E, S ECCS I SI-13S, Inadvertent Safety Injection Actuation RO-S-3

d.

Not Administered to SRO-U E.

Not Administered to SRO-U

h.

Not Administered to SRO-U I

I 3

~~

In-Plant Systems (3 for RO; 3 for SRO-I: 3 or 2 for SRO-U) t Not Administered to SRO-U

g.

N, L, A, S Reactor Protection I FL-20SF-2. Ejected Control Rod With RE'S Failure RO-S-7

~~

i.

Hydrogen Recombiner / HC-1, Startup Hydrogen Recombiner RO-S-9 I

_ < 9 / _ < 8 / _ < 4 2 l l 2 1 / 2 l 2 l l t l / 2 l 2 2 / 2 2 / 2 1

< 3 I < 3 15 2 (randomly selected)

i. Not Administered to SRO-U

k.

D, E Aux Feed Water I F5-7, F5 Appendix B, Attachment A, Unit 1 SS Actions SRO-S-I 4b (Clontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow power (N)ew or (M)odified from bank including I(A)

(P)revious 2 exams (RKA (S)imulator 2 112112 I ES-301,23 Of 27

Transient and Event Checklist Form ES-301-5 ES-301 v

E N

T T

acilltv: -

A P

P L

I C

A N

T 1

2 3

4 CREW POSITION CREW POSITION CREW POSITION CREW POSITION 2005 - fl 2al5;-G A l i L t E I5LAr-h Date of Exam: s'/z/o S Operatinq Test No.: h# I E

l Scenarios 1

C rcle the applicant level and enter lne operalmg lesl number and Form ES.D-1 even1 nc.mDerS for eacn even1 lype TS are no1 applicable for RO applicanls ROs must serve n both me 'al-lhesonlrols (Arc)- ana 'balance.01-plant (BOP)' positions. Instant SROs must do one scenario. including at least two Inslr.men1 or component IIICJ malLnc1,ons ana one major lransienl. n the ATC position Reacliviry manipLlalions may DB conducted maer normal or conlmlled abnorma. cvndil o m (refer 10 Secllon D 5 at DUI most DB signtcanl per Seclion C 2 a of Appendix D ' Reactivity and normal evoILbOns may be replacea *Ilh addiuonal mslmmenl or component maliunclions on a 1-fof.1 basis Whenever pracllcal. DOlh mslnmenl and componenl mahnCliOnS ShoUIo be inclLded only ltws0 thal reQu.ro verdaboe adions lhal Dmwde lnsiqhl IO the applcant's compelence cmnl toward lne mmimm requiremen1 2

3

Transient and Event Checklist Form ES-301-5 ES-301 Date 01 Exam g/3/os.6/4 105 Operatinq Test No L 15-Circle the applicant level and enter the operating test number and Fwm ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must sewe in bath the 'al-lhe-contro1S (ATC)' and 'balancwf-plant (BOP)' positions: Instant SROs must do one scenario, including at least two instrument or component (VC) malfunctions and one major transient. in lhe ATC position.

Reactivity manipulations may be conducted under normal or contmlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a ofApp3ndix D.

Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.

Author:

NRC Reviewer:

ES-301, Page 26 of 27

Transient and Event Checklist Form ES-301-5 ES-301 DateofExam S/3/

0 5 8/+5 Operatinq Test ho 3

rcr,C,t ISL E

l Scenarios v

0 1

E N

T J B S -&

2005-f J0.G D T

N CREW POSITION CREW POSITION CREW POSITION CREW POSITION A

1 2

3 4

T M

1 T

I

1.

Circle 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 applioants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) pasitions: Instant SROs must do one s c e n a ~,

including at least two instrument or component (VC) malfunctions and one major transient. in lhe ATC position.

Reactivity manipulations may be conducted under normal OT contmlled abnormal c o n d i t i (refer to Section 0:5.d) but must be significant per Section C.2.a of Appendix D. + Reactivity and normal evolutions may be replaced wlth additional instrument or component malfunctions w) a I-for-1 basis.

2.

Author:

NRC Reviewer:

ES-301, Page 26 of 27

ES-401 PWR Examination Outline Form ES-401-2 Facility pRAl/ZlE z 5 L A / J g Date of Exam

/, /os Ro Uote:

1.

Ensure that at least two topics fmm every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e.. except for one category in Tier 3 of the SROonly outline. the Tier Totals' in each WA category shall not be less than two).

The point total for each group and tier in the proposed outline must match that specified in the lable.

The Pnal point total for each group and tier may deviate by i1 fmm that specified in the lable based on NRC revisions. m e final RO exam must total 75 points and the SROonly exam must total 25 points.

Systemdevolulbns within each group are idenlkied on h a s d a t e d outline: systems or evuluthns that do not apply at the faciliy should be deleted and justled; operalionally impartanl. site-speciflc systems thal are not included on the outline should be added. Refer to ES-401., for guidance regarding the elimination of inappropriate WA statements.

Select topics fmm 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.

Absent a plant-specific priority, only those WAS having an importance rating (IR) pf 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions. respectively.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

The generic (0) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog. but the topics must be relevant lo the applicable evolutiw or system.

On the following pages. enter the KIA numbers. a brief description of each topic, the topics' impoltance ratings (IRs) fw the applicable license level, and the pdnt totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.

F a Tier 3. select topics fmm Section 2 of the WA catalog. and enter the KIA numben. descriptions. IRs.

and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

2.

3.

4.

5.

6.

7..

8.

9.

I I

I ES-401, Page 21 of 33

PWR RO Examination Outline Printed: 04/01/2005 Facility:

Prairie Island ES - 401 Emergency and Abnormal Plant Evolutions -Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function 1 K1 IK2 G I KA Topic I~mp. I Points EK2.03 - Reactor trip status panel 3.5 I

AK2.01 - Valves 2.7*

1 EA2.24 - RCP temperature setpoints 2.6 1

EK3.05 - Injection into cold leg 4.0*

1 AA1.22 - RCP seal failureimalfunction 4.0 1

000007 Reactor Trip - Stabilization -

Recovery / 1 000008 Pressurizer Vapor Space Accident /

3 000009 Small Break LOCA / 3 00001 1 Large Break LOCA / 3 000015/000017 RCP Malfunctions / 4 I

I 000022 Loss of Rx Coolant Makeup / 2 setpoints and operate controls identified in the alarm response manual.

AKI.01 -Loss ofRHRS during all modes of operation X 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation.

3'0 I '

000038 Steam Gen. Tube Rupture / 3 000054 Loss of Main Feedwater / 4 000055 Station Blackout / 6 X

AK3.03 - Manual control of AFW How 3.8 1

control valves EK1.02 - Natural circulation cooling

4. I I

I I

000056 Loss of Off-site Power / 6 I AA2.42 - Occurrence of a reactor trip I 4.1 I 1

l x l 000058 Loss of DC Power / 6 AK1.01 -Battery charger equipment 2.8 1

AA1.07 - Flow rates to the components 2.9 1

and instrumentation and systems that are serviced by the SWS; interactions among the components 000062 Loss of Nuclear Svc Water / 4 t

lAA1.05 - RPS 1 3.3* I 1

000065 Loss of Instrument Air / 8 WIE04 LOCA Outside Containment / 3 EA1.l - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK2.2 -Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility WIEOS Inadequate Heat Transfer - Loss of

I Secondary Heat Sink / 4 EK3.4 - RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and I

Facility:

Prairie Island Imp.

E/APE # / Name / Safety Function K1 K 2 K 3 AI A2 G

KATopic W/E12 -Steam Line Rupture - Excessive X 2.1.2 -Knowledge of operator 3.0 Heat Transfer 1 4 responsibilities during all modes of plant operation.

PWR RO Examination Outline Points 1

Printed:

WACategory Totals:

3 3

3 4

2 3

04/01/2005 Group Point Total:

18 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 2

PWR RO Examination Outline Printed: 0410 112005 Facility:

Prairie Island ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 ElAPE # / Name / Safety Function KI KZ K3 A1 A2 G

KATopic Imp.

000001 Continuous Rod Withdrawal / 1 000068 Control Room Evac. / 8 I

I l

l 1x1 1AK2.06 - T-ave./ref. deviation meter I 3.0*

AK2.02 - Sensors and detectors AK3.04 - Actions contained in EOP for plant fire on site AA2.01 - S/G level 000028 Pressurizer Level Malfunction / 2 000067 Plant Fire On-site / 9 X

X WIE02 SI Termination / 3 WIE03 LOCA Cooldown - Depress. / 4 WE07 Inad. Core Cooling / 4 WiEOX RCS Overcooling - PTS / 4 WIE 10 Natural Circ. 1 4 X

EK1.l - Components, capacity, and 3.2 function of emergency systems alarms and indications, and use of the response instructions.

X 2.4.31 -Knowledge of annunciators 3.3 X

EA1.l -Components, and functions of 3.6 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features X

EA1.3 -Desired operating results 3.6 during abnomial and emergency situations EKI.1 -Components, capacity, and IUACategory Totals:

2 2

1 2

1 1

Group Point Total:

9

PWR RO Examination Outline Facility:

Prairie Island KA Topic Printed: 0410 1 12005 Form ES-401-2 Imp.

K4.07. Water supplies K1.09 - RCSO 41.12-RHR heatup limits limiting conditions for operations and safety limits.

A3.01.

Components which discharge to the PRT K1.01 - SWS K6.02 - PZR K5.01 - DNB K4. 10.

Safeguards equipnicnt control reset K5.02 - Safety system logic and reliabilitv 2.2.22 - Knowledge of 3.0 3.6 2.9 3.4 2.7*

3.1 3.2 3.3*

3.3 2.9 A1.02. Containment p T e s s u r e correct MOV positioning K3.06 - SDS A3.02.

Isolation of the MRSS K4.02 -Automatic turbinelieactor trip runback 2.2.22 - Knowledge of limiting conditions for operations and safety limits.

K1.09 - PRMS A3.01.Pump starts and 3.6 4.3 2.8*

3.1 3.3 3.4 2.6*

K3.02-EDlG

'oints I

1 -

4. I 1

1 I -

including an understanding of running and incoming voltages A1.01 - Battery capacity as it is affected by discharge rate K6.08 - Fuel oil storage tanks limiting conditions for operations and safety limits.

A4.03 - Check source for operability demonstration 2.2.22 - Knowledge of I

2.5 3.2 3.4 3.1 1

1 1

PWR RO Examination Outline Facility:

Prairie Island KIA Category Totals:

Printed: 04/01/2005 evacuation (inc uding recognition of the alarm) 3 2

3 3

2 2

3 2

3 Group Point Total:

28 2

PWR RO Examination Outline Printed: 04!01/2005 Facility:

Prairie Island

ES-401 PWR Examination Outline Form ES-401-2 RO KIA Category Points K

K K

K A

A A

A G

1 2

3 4

5 6

1 2

3 4

Total Group 18 1

2 Tier Totals NIA NIA -

9

- 27 Facility:

p SRO-Only Points A2 G'

Total t

6

z.

L 4

6 4

10 Tier

1.

Emergency 8 Abnormal Plant Evolutions

2.

Piant Systems

3. Generic Knowledge and Abilities 1

2 3

4 1

2 3

4 7

c (Zit Categories Note:

1.

Ensure bat at least two topics fmm every applicable KIA category are sampled within each tier of the RO and SRO-mly outlines (i.e.. except fw one category in Tier 3 of the SRO-only outline. the Tier Totals' in each WA category shall not be less than two).

The point total far each group and tier in the proposed outline must match that specified in the table.

The final point total for each gmup and tier may deviate by 31 fmm that spenfied in the table based on NRC revisions. The final RO exam must total 75 pints and the SRO+nly exam must total 25 points.

SysternslevolutMls W i n each gmup are identifbd on the associated autline: systems OT evolulions that do not apply at Uw facility should be deleted and justified: opeationally impatant. site-specific systems that are not included w1 the outline should be added. Refer to ES401. Allachment 2. fw guidance regardins the elimination of inappropriate KIA statements.

Select topics from as many systems and evoluliow as possible; sample every system w evoluiion in the group before selecting a second topic far any system w evolution.

Absent a plant-specific priority. only those WAS having an importance raling (IR) of 2.5 or higher shall be selected.

Use h e RO and SRO ratings for the RO and SRO-only portmns. respectively.

Select SRO topics for Tiers 1 and 2 from the shaded Systems and WA categories.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog. but the topics must be relevant to the applicable evolution or system.

On the following pages, enter the WA numbers. a brief description of each topic. the topics' imporlance ratings (IRs) far the applicable license level, and the paint totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO+,nly exams.

Fa Tier 3. select topics from Sectin 2 of the KIA catalog. and enter the WA numbers. descriptions. IRs.

and point totals (#) cm Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

2.

3.

4.

5.

6.

7.'

8.

9.

I I

I ES-401. Page 21 of 33

PWR SRO Examination Outline Printed: 04/01/2005 Facility:

Prairie Island ES - 401 Emergency and Abnormal Plant Evolutions -Tier 1 /Group 1 Form ES-401-2

s 9

7 IO W/E16 High Containment Radiation / 9 IUA Category Totals:

PWR SRO Examination Outline Printed: 04/01/2005 Facility:

Prairie Island ES - 401 Emergency and Abnormal Plant Evolutions -Tier 1 /Group 2 Form ES-401-2 0

0 0

0 E/APE # I Name /Safety Function I K1 IK2 I K3 IAl X

2.4.4 -Ability to recognize abnormal 4.3 I

indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

2 2

Group Point Total:

4 000036 Fuel Handling Accident / 8 000069 Loss of CTMT Integrity / 5 I

I I

I AA2.02 - Occurrence of a fuel handling I

iincident I :-:

1 X 2.1.2 -Knowledge of operator responsibilities during all modes of plant operation.

X 1 IAA2.01 - Loss of containment integrity I 4.3 I I

I

PWR SRO Examination Outline Facility:

Prairie Island G

X X

2 1 KATopic Imp.

A2.19 - High secondary and primary concentrations of chloride, fluoride, sodium and solids 2.1.33 -Ability to recognize 4.0 indications for system operating parameters which are entry-level conditions for technical specifications.

2.2.22 - Knowledge of 4.1 lirnitine conditions for 3.5 Group 1 r2 X

X A3 A4 2

0 0

Printed: 04/01/2005 Form ES-401-2 Point!

1 operations and safety limits.

X 12.4.31 -Knowledge of I 3.4 I 1

annunciators alarms and indications, and use of the response instructions.

A2.01 - Erratic or failed power supply Group Point Total:

17 16 PWR SRO Examination Outline Facility:

Prairie island K C. An1 Plant Systems - Tier 2 / Group 2 Printed: 0410 1 /2O05 Form ES-401-2 rb I

I I

operations and safety hiits. I I

KIACategory Totals:

0 0

0 2

0 0

1 Group Paint Total:

3

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Equipment Control Facility:

Prairie lsland 2.2.1 1 Knowledge of the process for controlling 2.5 I

2.2.34 Knowledge of the process for determining the 2.8 1

Category Total:

2 temporary changes.

internal and external effects on core reactivity.

Generic Cateeory Knowledge of the process for performing a containment purge.

Printed: 04/01/2005 Form ES-401-3 2.5 1

KA KA Tooic

&Poillts Conduct of Operations 2.1.8 2.1.16 2.1.32 Ability to coordinate personnel activitirs outside the control room.

Ability to operate plant phone, paging system.

and two-way radio.

Ability to explain and apply all system IiniIts and nrecautions.

3.4 I

I Category Total:

3 Radiation Control 2.3.9 2.3.1 1 F I

2.7 I

I Ability to control radiation releases.

Category Total:

2 1

Eniergency ProceduresIPlan I

2.4.5 t 2.4.20 2.4.21 c Knowledge of the organization of the operating procedures network for uoimal, abnormal, and emergency evolutions.

Knowledge of operational implications of EOP warnings, cautions, and notes.

Knowledge of fire in the plant procedure.

1 I

I I

I Category Total:

3 Generic Total:

10

i9 Conduct of Operations 1 3 r /

2.1.10 Knowledge of conditions and limitations in the 3.9 1

Category Total:

1 facility license.

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Equipment Control Faeilit).: Prairie Island Generic Category KA KA Topic 2.2.8 Knowledge of the process for determining if the 3.3 1

proposed change, test, or experiment involves an unreviewed safety question.

2.2.3 1 Knowledge of procedures and limitations 2.9*

1 Category Total:

2 involved in initial core loading.

Printed: 04/01/2005 Form ES-401-3

& P o i n t s 2.3.8 2.3.10 Knowledge of the process for performing a 3.2 I

Ability to perform procedures to reduce excessive 3.3 I

planned gaseous radioactive release.

levels of radiation and guard against personnel exposure.

Emergency ProcedureslPlan Radiation Control 2.4.1 Knowledge of EOP entry conditions and 4.6 I

2.4.32 Knowledge of operator response to loss of all 3.5 1

Category Total:

2 immediate action steps.

annunciators.

Appendix D Scenario Outline Form ES-D-1 Event Malf.

No.

Facility: Prairie Island Scenario No.: 2005-A Op-Test No.: 1 Examiners:

Operators:

1. a

2. b

3. c Initial Conditions: 100% Power, MOC, No Equipment 00s Event Type*

Turnover: Normal 1

RD0916 I

2 1 TC03 I

C 3

I CLOIA I

C 3

1 CL03 I

C CL02B DI-46038C Close 5 I MSOIB I

M FW34B S105AlB Event Description Failed RPI Rod G7 (AOP)

Turbine Control Valve Cycling (AOP) (Reactivity for RO) 11 Cooling Water Pump Trip 121 Cooling Water Pump Fails to Autostart 12 Cooling Water Pump Fails to Autostart 22 Cooling Water Pump Fails to Autostart

~

Isolation of CL to Unit 1 Turbine Building 12 SG Steamline Break in Containment (Inserts on Rx Trip) 12 AFWP Auto Start Failure Both SI Pumps Fail to Autostart MSIVs Fail to Auto Close

(N)ormal.

(R)eactivity, (1)nstrument. (C)omponent, (M)ajor NUREG-1021, Revision 9 38 of 39

Appendix D Scenario Outline Form ES-D-1 9

Facility: Prairie Island Scenario No.: 2005-8 Op-Test No.: 2, 3 FW32 M

Examiners:

Initial Conditions: 100% Power, MOC (Standard IC 'A')

Operators:

1. a

2. b

3. c Turnover: 11 AFWP and Breaker 16-10 00s Start 13 Chg Pump and stop 12 Chg Pump in preparation for isolation of 12 Chg Event I Malf.

1 Event No. I No.

I Type*

1 I N/A I

N RX206 4

1 47012-0203 1

C 5

I RC03B I

M 6 I TC06 I

C TCOIA TC14C FW27B ED026 Event DescriDtion Swap from 11-12 Chg to 11-13 Chg in service PRZR Level controlling channel fails HIGH IO-Bank Oil Leakage reported, requiring transfer of one safeguards 4160V bus to alternate source in anticipation of loss (AOP)

High Vibration on 12 RCP (AOP) (Power reduction required) 12 RCP Shaft Shear Turbine Auto Trip Failure (Note: Events 5-8 required to reduce SG inventory enough to cause loss of heat sink post trip)

MSlV Auto Closure Failure Turbine Left Stop Valve Closure Failure Turbine CV-3 Fails As Is FCV 476 (12 Main Feed Reg) Fails Closed on Trip Bus 12 Auto Transfer Failure MD AFW Pump Trip on Start-Loss of Heat Sink

(N)ormal, (R)eactivity, (1)nstrument.

(C)omponent, (M)ajor NUREG-1021, Revision 9 3a of 39

ADoendix D Scenario Outline Form ES-D-1 Facility: Prairie Island Scenario No.: 2005-D Op-Test No.: 3 Examiners:

Operators:

1. a

2. b

3. c Initial Conditions: 100% Power, MOC Turnover: D1 00s Event No.

1 2

3 4 -

4 4 -

5 -

Malf.

Event No.

I Type*

FW30 I

1 VC08 I

C RC22A r+-

EDO9F DI-46943C Event Description Controlling HDT Level Xmtr fails LOW (Reactivity)

Letdown HX Tube Rupture (leakage into CC) (AOP)

Pzr PORV Leakage (unisolable)

~~~

~

Loss All Offsite AC (Extended Loss)

Bus 16 Lockout (with D1 failure causes loss all AC)

~

~~

Bkr 25-16 failure to close (prevents power restoration on cross-tie)

RCP Seal Failures on Extended Power Loss

(N)ormal, (R)eactivity, (1)nstrument. (C)omponent, (M)ajor NUREG-1021, Revision 9 3a of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Prairie Island Scenario No.: 2005-F Op-Test No.: 2. 3 Examiners:

Operators:

1. a

2. b

3. c Initial Conditions: 2% Power Prior to Turbine Roll in I C 1 2 Startup Turnover: No Equipment OOS, Raise power to 6% per I C 1 2 Event No.

1 2

3 4 -

5 6

6 6

TvDe*

NIA I

R Off D1-462960 I A 0 4 1 132 0 CHI21 8 RClO I

C RCIO I

M CHOIEIF 1

I RHOIA I

C RH02B 1

C LO-4621 1 G OFF 1

Event Descriotion Raise power to 6% per I C 1 2 Regen HX Charging Line Outlet FCV fails CLOSED (AOP)

Steam Header Pressure fails LOW Fire in the Aux Building (requires hot short actions for CC. AFW)

Pressurizer Surge Line Leakage 11 gpm (AOP)

Large Break LOCA-Surge Line Shear Ctmt Press Xmtrs fail as-is, preventing auto Containment Spray 11 RHR Pump Lockout on Start 12 RHR Pump Fails to Start in Auto Breaker trip for Sump B to 12 RHR-Prevents Train B sump recirculation

(N)ormal, (R)eactivity, (1)nstrument. (C)omponent, (M)ajor NUREG-1021, Revision 9 3a of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Prairie Island Scenario No.: 2005-G Op-Test No.: 1 Examiners:

Operators:

1. a

2. b

3. c Initial Conditions: IC-26 Critical following App CIB startup, 10-8A, critical data taken Turnover: No equipment 00s Event Malf.

Event 2

I FW32 I

C 3

1 VC21A I

C 4

1 SGOIA I

C 5

I ED14 I

M EDO9E Dl-46523 I

M 7 I SG02A Event Description Raise reactor power to.5-2% per I C 1 2 Unit Startup.

12 AFWP Lockout 11 RCP Thermal Barrier Heat Exchanger leakage (AOP)

Steam Generator Tube Leak (AOP)

Loss of Offsite Power (Rx Trip)

Bus 15 Lockout

~

~~

22 Diesel Cooling Water Pump start failure 11 SG Steam Generator Tube Rupture (SI) (Causes Loop A CL isolation and loss of pressure)

(N)ormal, (R)eactivity, (1)nstrument. (C)omponent. (M)ajor NUREG-1021, Revision 9 38 of 39

ML052900478

Text

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