EXAMINATION OUTLINE SUBMITTAL AND

NRC COMMENTS FOR THE BRAIDWOOD INITIAL

EXAMINATION - DECEMBER 2007

July 31,2007 BW070057

U. S. Nuclear Regulatory Commission Region Ill 2443 Warrenville Road Suite 210 Lisle, IL 60532-4351

Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Enclosed are the examination outlines, supporting the Initial License Examination scheduled for the weeks of December 3,2007 through December 14,2007 at Braidwood Station.

This submittal includes all appropriate Examination Standard forms and outlines in accordance with NUREG-1 021, "Operator Licensing Examination Standards," Revision 9.

In accordance with NUREG 1021, Revision 9, 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 concerning this letter, please contact David Gullott, Regulatory Assurance Manager, at (81 5) 41 7-2800. For questions concerning examination materials, please contact Darren Stiles at (815) 458-7829.

Submittal of Initial Operator Licensing Examination Outline

Respectfully,

rom coutu Site Vice President Braidwood Station

Enclosures: (Hand delivered to Nick Valos, Chief Examiner, NRC Region Ill)

Examination Security Agreements (Form ES-201-3) Administrative Topics Outlines (Form ES-301-1) Control Room/ln-Plant Systems Outlines (Form ES-301-2) PWR Examination Outline (Forms ES-401-2) Generic Knowledge and Abilities Outline (Tier 3) (Form ES-401-3) Scenario Outlines (Form ES-D-1)(3 sets) Record of Rejected WAS (Form ES-401-4) Completed Checklists:

Examination Outline Quality Checklist (Form ES-201-2) Transient and Event Checklist (Form ES-301-5)

ecc: Director, Licensing and Legal Affairs Manager, Licensing - Braidwood, Byron and LaSalle County Stations Braidwood Nuclear Licensing Administrator Regulatory Assurance Manager - Braidwood Station Exelon Document Control Desk Licensing Human Resources - Braidwood Station Training Manager - Braidwood Station

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

-acility: Braidwood Date of Examination: 12/03/2007

Initials tem Task Description

1. W R I T

E N

a.

b.

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

Assess whether Ihe outline was systematically and randomly prepared in accordance with

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, insbument and component failures, technical specificafions,

Section D.1 of ES-401 and whether all KIA categories are appropriately sampled. 9 %w

T $9 9 4 6 0 * iJ aw

c.

d.

a. 2.

and major transients.

Assesswhether there are enouah scenario sets (and snares) to test the oroiected number

S !~ b. -

- % 9 @ d

M U

A T

ana mix of applicants n accordance wm lne expectw crew compos bon'and rotaton Schedule wtho~t comprom sing exam integr ty. and e n w e that each app wnl can be rested dsing a1 least one new or signilcantly mod.fed scenano that no Scenar os are o,p caled from the app. wns a d d tesl(s). and scenarios wll no1 be repealed on suosequent aae.

To the extent possibe. assesswmetner lne odtline(s) canform(s) mth the qcalitative ana qLan1 tative cr leria specifiea on Form ES-301-4 and aescr oea in Appendu D

Verify lnal !he syslems walk-lhro-gn out ne meets the crilena spectfiW on Form ES-301.2 (1) tne o ~ l ne(si conL%n(s) the rewired number of control room and i-+p anttas6s

disb o~ lw among me safery fbncbons as specif ea on tne b m 12) task repelibon from [ne ast IWO NRC exam nations IS wmin Me Iim 1s speufea on Ihe form (3) no tasns are duplicated from tne appl iwnk audit lesqs) (4) tne nLmber of new or moaXea tasks meets or exceeds the monimms specifec on n e form (5) tne nmoer of a ternate path. ow-power emergency and RCA tasks meet lne criler a

on lne form Verify mal lne aarnin snative outline meets the d b w a speafied on Form ES-301-1 (1 ) lne tascs are diSbibLled among the lopics as specified on me form (21 at least one las6 is new or s gn Acandy moa 6ed

I

E f i o c

a

9 W I T

0

(3) no more than one tas6 4s repealed froin (he last two hRC censing examinabons Determine 11 mere are enodgn dilferem o~tlines lo test tne prpected ndmaer an0 mix of appliwnls and ensure that no lems are auplicated on s-bseqdent days

c

a Assess metner p8anl-specihc prlorlws (inadding PRA and IPE nsigha) are covered CJ A _ , 4

a. Aumor b. Facility Reviewer (+) c. NRC Chief Examiner (#)

JOTE: # Independent NRC Reviewer initial items in Column "c"; chief examiner concurrence required.

ES-201, Page 25 of 27

ES-301 Administrative Topics Outline Form ES-301-1

acility: Braidwood

xamination Level: RO SRO 0 Date of Examination: 12/03/2007

Operating Test Number: 20070301

Administrative Topic (See Note)

Conduct of Operations

Conduct of Operations

Equipment Control

Radiation Control

Emergency Plan

Type Code’

D. S

N, S

D. S

N, S

N/A

Describe activity to be performed

R-103 Perform Shutdown Margin Calculation

KIA 2.1.25 ImD Factor 2.8

R-107 Perform Mode 5 Shiftly and Daily Operating Surveillance

K/A 2 1 18 Imp Factor 2.9

R-201 Hang Worker Tawut (1A FW Pump)

KIA 2 2.1 3 lMn Factor 3 0

R-302 Respond to 1PRO3J High Radiation Alarm

WA 2 3.11 Imp Factor 2 7

N/A

OTE: All items (5 total) are required for SROs. RO applicants require 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 (5 3 for ROs; 5 4 for SROs 8. RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (5 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1

-acility: Braidwood

ixamination Level: RO 0 SRO

Date of Examination: 12/03/2007

Operating Test Number: 20070301

Administrative Topic (See Note)

Conduct of Operations

Conduct of Operations

Equipment Control

Radiation Control

Emergency Plan

Type Code'

N. S

D. S

N, S

N, S

Describe activity to be performed

R-103 Perform Shutdown Margin Calculation

WA 2.1 2 5 ImD Factor 3.1

R-107 Perform Mode 5 Shiftly and Daily Operating Surveillance

WA2.1.18 ImpFactor30

S-201 Initiate a 1 WA 2 2 23

( I A SI Pump)

In+@ Factor 3 8

R-302 Respond to 1PRO3J High Radiation Alarm

KIA 2.3.11 Imp Factor 3 3

S-400 Prepare and Approve Nuclear Accident Reporting System Form.

WA 2.4.40 Imp Factor 4.0

VOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

* Type Codes 8, Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs 8, RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (5 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

i. IP-100 Rod Drive MG Startup and Paralleling with Auto Synchronization

j. IP-400s Local Start of 1 B AF Pump with Failure of Battery Bank

k. IP-704 Align the Fire Hazards Panel

Failure KIA 001000G2.1.23 Imp Factor 3.9

KIA 061000A2.03 Imp Factor 3.1

WA 016000G2.1.30 Imp Factor 3.9

Facility: Braidwood

Exam Level: RO SRO-I 0 SRO-U 0

D, A 1

D, A, E, R 4s

M, E, R 7

Date of Examination: 12/03/2007

Operating Test Number: 20070301

Type Codes

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams

(RPA (S)imulator

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Criteria for RO / SRO-I / SRO-U

4-6 / 4-6 / 2-3

- < 9 / 5 8 1 5 4 - > I / 2 1 /,l - > 1 / 2 1 /,1 - > 2 / 2 2 1 2 1

- > I / 2 1 /,1 - < 3 / - < 3 2 (randomly selected)

ES-301, Page 23 of 27

L

a. SIM-I 10 Perform Emergency Boration for Inadequate Shutdown Margin

b. SIM-222 Align Ventilation Systems for Emergency Operations KIA 004000A4.07 Imp Factor 3.7

KIA 013000A4.01 Imp Factor 4.8 SIM-206 Lower 1B and I C SI Accumulator Level KIA 006000A1 . I 3

c. Imp Factor 3.7

d. N/A

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

D, S, L. A 1

N, S, L, A 2

N, S 3

N/A N/A

Facility: Braidwood

Exam Level: RO 0 SRO-I [XI SRO-U 0 Date of Examination: 12/03/2007

Operating Test Number: 20070301

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including I ESF)

e SIM-501 Drain the PRT

f SIM-610 Perform Low Power Electrical Alignment

g. SIM-800 Swap CC Pumps

K/A 007000A1 01 Imp Factor 3 1

KIA 062000A4 07 Imp Factor 3 1

Safety I I Function

D, s 5

N 3 6

D, S, A 8

h. SIM-901 Perform Waste Gas Release Channel Checks KIA 071000A4.25 Imp Factor 3.2

D, P, S 9

(A)lternate path (C)ontrol room

, (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power / Shutdown

(P)revious 2 exams

(R)CA (S)imulator

1 (N)ew or (M)odified from bank including I(A)

4-6 / 4-6 / 2-3

ES-301, Page 23 of 27

L

u

tS-301 Transient and tvent Checklist korm tS-301-5

raidwood Date of Exam: 12/03/2007 Operating Test Number: 20070301

M I N I M U M(')

4 1 4 1 2

1. Check the a event ty e f g are not ap licable for RO applicants. ROs must serve in boththe "at-the-controls (ATC)" and "bakce-of-plant (B8P)" positions. Instant SROs must do one scenaFio, including at, least two instrument or component (K) malfunctions and one major transient, in the ATC position.

licant level and enter the operating test number and Form ES-D-1 event numbers for each

2 Reactivi manipulations may be conducted under normal or controlled apnormal conditions (refer to

evolutions may be replaced with additional instrument or component mal unctions on a 1-for-1 basis \ Section 8 5 d) but must be significant per Section C 2 a of Appendix D ) Reactivity and normal

3 Whenever practical. both instrbment and component malfunctions should be included. only those that reqdre verifiable actions that provide inaght to the applicant's corn etence count toward the minimum requirements specifiea for the applicants license level in t\e right-hana columns

ES-301, Page 26 of 27

- ES-401 PWR Examination Outline FORM ES-401-2

2 Tne PO nt tola lor eacn gr0-P and t er n !ne P~OPOSW outline mrSl match lhat spec fiea n !ne la0 e Tne I na p m t lola for eacn group ana t er may aemate by f 1 from lnat specifea n the taD e oasea on NRC rev lions The rna RO ekam m-51 tola 75 PO nts ana tne SRO-0% exam mrSl tola 2 5 PO nts

Systems e,oI.ions n tnm eacn group am menhhed on Ine assoc alea out1 ne syslems or ebo _tons lhaloo no1 applf at tne fac, I, sno- a ae ae etea and ,us1 Rea, aperat m a Iy mponant s te-spec fic systems tnat are not ncl.aea on !ne 0.1 ne snou d oe aaaea Refer to ES-401 Anacnment 2 for gAance regard ng !ne e m nat on 01 nappropr ate K A Statements

Se e c t t o ~ cs lrom as many systems ana eVo -1 oris as poss ole samp e every system or ero .I on n the gro-p Delore se ect ng a secona top c lor any system or e.o ution A D S ~ ~ I a p ant-spec f c &w or ty. on I !nose &As h a w g an mponance rat ng IR) of 2 5 or n gner sna oe se ected ,se ine RO ana SUO ral ngs lor the RO ana SRO-an y pon on5 respecl \el l

Se ect SRO top cs lor T k r s 1 ana 2 from !ne snaaea systems and K A wtegor es

The gene, c G ) & AS n T ers 1 ana 2 sna I oe se ectea from Sect on 2 of the K A Catalog bet Ihe top~cs m s t be re e.ant to me app caole eba On me 101 OH ng pages. enter tne & A n-moers a br el aescr pt on 01 each top c me topes imponance ratings RSJ lor the app cao e icense level ana tne PO nt l0la.s (SI lor eacn system ana categon, Enter the gro-p ana t er lola 5

lor eacn category n me taole aoo,e f 1.e nand ng equipment s samp ea .n otner than Categon, A2 or G' on tne SRO-on y exam. enler st on the eft s de of Column A2 for T er 2 G r a 4 2 (Nole ~1 aoes not app Y J Lse 0.p cale pages for RO ana SRO-omy esams

For T er 3 se ect top cs from Sect on 2 of tne K A catalog ana enler me K A n.mOers aescr PI ons IRs. ana PO nt iota s RJ on Form ES-401-3 - m I SRO seiectlons to K A s lnal are mea to 10 CFR 55 43

3

4

5

6 7 '

8

On or syslem

9 - - ES-401, 21 of 33

E/APE # / Name / Safety Function KIA Topic@)

00008 Pressurizer Vapor Space Accident 1 3 Sensors and detectors

00057 Lo55 of Vital AC Inst. Bus 16

00065 LOSS of ln~lrumenl Air I 8

ES-401, 22 of 33

ES-401 3 Form ES-401-2

ES-401 A Form ES-401-2

Abnormal Plant Evolutions - Tier 2/GrouD 1 IRO) jency an

-

KIA Topic(s) I IR

11004 Chemical and Volume Control I 2

I 11005 Residual Heat Removal 1

11006 Emergency Core Cooling I Vaive operatom for accYmYia1ors: Relationship between 2.5; ECCSflowand RCS ~ressure I 1 5 I , 'i! 2

11007 Pressurizer Relief/Quench Tank I I 2.6 1

11008 Component Cooling Water I 1

11010 Pressurizer Pressure Control I Knowledge of operstor re9paSWiMI.p d u m all modes of

ESFAS. BypassMock Oircuih 11012 Reactor Protection 1

L 3. 3 6

3 1

4.4

3 4

2 7

3 4

3 2

2 9

2 8

- - - - - - - -

Meten. annunciators. dials. recorders, and indicating tight

Radiation levels

Canlainmen< pressure. t m ~ e r a t ~ r e and humidity

3 2 2 3 2 Group Point Total' KIA Category Totals: 3

ES-401, Page 24 of 33

ES-401 5 Form ES-401-2

PWR Examination Outline Form ES-401.'

Ib02 Reactor Coolant I 4.2 I 1

14 Rod Position Indication

16 Non-nuclear instrumentation

27 Conla nmenl Iw ne Remova

35 Steam Generator

41 Steam Dumpmurbine Bypass Control

55 Condenser Air Removal

68 Liquid Radwaste

lb72 Area Radiation Monitoring I I I I I I I

._ ES-401, Page 25 of 33

ES-401,22 of 33

ES-401 3 Form ES-401-2

IES-401 PWR Examination Outline Form ES-401-21

00037 Steam Generator Tube Leak I 3

00051 Loss of Condenser Vacuum I 4

v

ES-401, 23 of 33

ES-401, Page 24 of 33

ES-401 5 Form ES-401-2

PWR Examination Outline Form ES-401-

ES-401, Page 25 of 33

ES-401 Generic Knowledae and Abilities Outline flier 3) 3 2 Form ES-4014

Category RO I SRO-Only

IR I a t 1 IR I 6t W A # Topic

2.1 . 24 1. Conduct of Operations 2.1 10

2.1 20

12.2. 13 lKnawledgeof tagging and clearance procedures 1 3 . 6 1 1 I I

Ability 10 obtain and intetprst ~lslton sienrt~al and mechanical drawings. 2.8 1

Knowledge Of COnditionE and limitstiom in the facility license. 3.9 1

Ability lo execute procedure steps. 4.2 1

3 Radiation Control

1

4. 12.4. 29 IKnowledge ofthe emergency plan

(2.4. I I I I I Subtotal

ier 3 Point Total

ES-401, Page 26 of 33

RO

BOP

Initial Conditions: IC-21

Turnover: Unit 1 is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 906 ppm. Online risk is green. I C CDlCB pump is 00s for bearing replacement. The I C CDlCB pumps is expected back in service in four days. Following completion of turnover, the crew is to perform 1BwOS EH-MI, UNIT 1 EH PUMP OPERABILITY MONTHLY SURVEILLANCE. NLOs have been briefed and are standing by at the Unit 1 EH skid.

Event Malf. No. No.

Preload IMF T H l l A 0 IOR ZDll CD05PC PTL IOR ZDIICD05PCB PTL IOR ZDllCB113C CLS

1 None

2

3 IMF THI IB 5

IMF RXOl J 0 30

TRGSET 1

IMF PN1555 (2 70) ON

"(N)ormal, (R)eactivity (1)nstrumeni (C)omponent, (M)ajor Transient

SCENARIO OVERVIEW Unit 1 is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 906 ppm. Online risk is green. I C CDlCB pump is 00s for bearing replacement. The I C CD/CB pumps is - expected back in service in four days. Following completion of turnover, the crew is to perform 1BwOS EH- M1, UNIT 1 EH PUMP OPERABILITY MONTHLY SURVEILLANCE. NLOs have been briefed and are standing by at the Unit 1 EH skid. Heavy rains have been experienced at the Braidwood site over the past few days and are forecast to continue.

After completing shift turnover and relief, the BOP will perform lBwOS EH-MI, UNIT 1 EH PUMP OPERABILITY MONTHLY SURVEILLANCE.

After completing 1BwOS EH-MI, the controlling 1D SG pressure channel will fail low. 1 FW540, Feedwater Regulating Valve, will begin to close and 1D SG level will lower. The BOP will take manual control of I D SG level and stabilize 1D SG level. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment F, will be implemented. The BOP will restore I D SG level control to automatic after 1D SG level is restored to normal and an operable 1D SG steam flow control channel is selected. Technical specifications 3.3.1, conditions A and D and 3.3.4, condition A apply. NOTE: This event is required for RO candidates ONLY. The malfunction may be omitted at lead examiners discretion if INSTANT SRO candidate is filling BOP position and the malfuwtioQ is not needed to meet the INSTANT SRO candidate’s required transients and event total EG 1021 ES-301-5.

After the SG press en to the intermediate position, resulting in by closing 1 RY8000B, PORV block valve. r from 1 RY8000B. 1 RY456 will remain un ditions A and C apply. After the PZR PORV failure is addressed, Loop 4 T d rod motion. The RO crew will place rod control in manual and take acti OPERATION WITH A FAILED INSTRUMENT CHA Spec 3.3.1, conditions A and E apply.

After the Thot RTD failure is addressed, t PUMP TRIP, Attachme k. The RO will borate the RCS as necessary to stabilize

After the I D CDlCB pump trip 450 gpm Steam Generator Tube Rupture will occur on the CTOR TRIP OR SAFETY INJECTION. When SI actuates,

a solenoid failure will ca ntainment. IA to containment will remain for the remainder of the scenario. Following the reactor trip, the 1B SG

SG PORV when required, resulting in an off-site release. The crew will

v

manually isolate the 1B S BwEP-3, STEAM GENERATOR TUBE RUPTURE, based on secondary radiation trends on the 1B SG. After determining RCS pressure control is unavailable, the crew will transition 1 BwCA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.

The scenario is complete when the crew has terminated high head SI in 1BwCA-3.3.

1. Isolate feedwater flow into and steam flow from the ruptured SG prior to completing step 4 of 1 BwEP-3.

2. Cool down to establish RCS subcooling margin, but prevent entry into 1 BwFR-P.1.

3. Terminate high head SI prior to completing step 9 of 1 BwCA-3.3.

Critical Tasks

(ERG Critical Task number - E-3-A) (WA number - 000038EA2.01 importance - 4.1/4.7)

(ERG Critical Task number - E-3-8) (WA number - 000038EA1.36 importance - 4.3/4.5)

(ERG Critical Task number - CA-3.3--A) (WA number - 000038EA1.30 importance - 4.0/3.8) ~

NRC 07-1 Page 2 of 27

Y Firnulation Facility Braidwood Scenario Operating Test No.: 20070301

No.: NRC 07-2

Examiners: Applicant: SRO

RO

BOP

I

nitial Conditions: IC-16

rurnover: Unit 1 is operating at 53% power, stead: state, equilibrium xenon, Boron concentration is 676.0 ppm. Online risk i yellow. 1B RH pump has been 00s for breaker work for the past 10 hours. LCO 3.5.2 has been entered. Expect 1B RH pump back in 48 hours. Following completion of turnover, the crew is to perform lBwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HllLO LEVEL ALARM SURVEILLANCE. Power Team has requested Unit 1 prepare to raise power 200 MW at 0.6 MWlmin due to grid demand

Event I Malf. No. No.

'reload -

IOR ZDllRHOl PB PTL IMF TC03 IMF MSOIA 100 IMF MSOlB 100 IMF MSOlC 100 IMF MSOlD 100 IMF SlOlB

2 None

3 I IMF RX13A 100 10

4 IMF RXlOA 0 30

*(N)ormal, (R)eactivity (1)nstrumeni

Event Event Type* Descriptign

I 1B RH Pump 00s

C-BOP, US

C-BOP Turbine auto trip failure

M-ALL PZR vapor space LOCA

C-RO, US 1B SI pump fails to start

C-ALL 1 B SX pump trip

(C)omponent, (M)ajor Transient

Spiking PR channelheactor trip

SCENARIO OVERVIEW

Unit 1 is operating at 53% power, steady state, equilibrium xenon, Boron concentration is 676.0 ppm. Online risk is yellow. 1B RH pump has been 00s for breaker work for the past 10 hours. LCO 3.5.2 has been entered. Expect 18 RH pump back in 48 hours. Following completion of turnover, the crew is to perform lBwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HVLO LEVEL ALARM SURVEILLANCE. Power Team has requested Unit 1 prepare to raise power 200 MW at 0.6 MW/min due to grid demand.

After completing shift turnover and relief, the crew will perform lBwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HllLO LEVEL ALARM SURVEILLANCE..

After completing 1BwOS FW-M2, Power Team will request Unit raise power 200 MW at 0.6 MW/min due to grid demand. The crew will commence a power ascension at 0.6 mw/min.

After a measurable change in power, PZR level channel 1LT-459 will fail high. 1CV121, charging header flow control valve, will lower charging flow and pressurizer level will lower. The RO will take manual control of PZR level and stabilize PZR level. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment C, will be implemented. The RO will restore PZR level control to automatic after PZR level is restored to normal and an operable PZR level control channel i specifications 3.3.1 conditions A and K apply.

After the ILT-459 failure is addressed, turbine impulse pressure ch rods will begin automatically inserting. After recognizing the instrum stable, the RO will place rod control in manual to stop the inward 60 WITH A FAILED INSTRUMENT CHANNEL, Attachment A, will..@ .. ippkpented. . The crew will defeat the failed instrument and th and P apply.

After the IPT-505 failure is addressed, a loss of inst lBwOA ELEC-2, LOSS OF INSTRUMENT BUS, an cannot be energized from the CVT.

Three minutes after in causing an automatic rea INJECTION. When the reactor trips, the' turbine. The MSlVs will not close. The causing a PZR vapor space 1B SI pump will not start. T components will be man 1 BwEP-1, LOSS OF REA

The scenario is complet

I

5 will fail low. Control

cal specification 3.3.1, conditions A

S 11 1 will occur. The crew will enter - e that instrument bus 11 1 is damaged and

, PR channel N-43 will momentarily spike high, EACTOR TRIP OR SAFETY

will not automatically trip. The crew will manually trip the rapid RCS cooldown will cause a weld break on the PZR

pump. 1A Train ECCS rew will transition to

reactor trips. When SI actuates, the

primary plant conditions.

Critical Tasks

1. Manually trip the main turbine prior to completion of step 2 of 1BwEP-0.

(ERG Critical Task number - E-0-4) (WA number - 045000A4.01 importance - 3.1/2.9)

2. Manually start 1 B SI pump prior to completion step 6 of 1 BwEP-0.

(ERG Critical Task number - E-0--D) (WA number - 013000A4.01 importance - 4.5/4.8)

3. Manually start 1A SX Pump prior to completion of step 12 of 1 BwEP-0.

(ERG Critical Task number - E-0--L) (WA number - 008000A4.01 importance - 2.9/2.9)

NRC 07-2 Page 2 of 25

Simulation Facility Braidwood Scenario Operating Test No.:20070301 No.: NRC 07-3

Examiners: Applicant: SRO

RO

BOP

Initial Conditions: IC-21

Unit 1 is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 820 ppm. Online risk is green. Following completion of turnover, the shift manager requests the BOP to start the OB WS pump in accordance with BwOP WS-

and secure the OC WS pump in accordance with BwOP WS-3. SHUTDOWN OF A NON- ESSENTIAL SERVICE WATER PUMP, for an upcoming clearance order on the OC WS pump. Align the OC WS for standby after it is secured. Operators have been briefed and are standing by at the Lake Screen House to support WS pump s requested Unit 1 prepare to lower power 200 MW at 3.0 MWlmin

1, STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM,

*(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

SCENARIO OVERVIEW

Unit 1 is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 820 ppm. Online risk is green. Following completion of turnover, the shift manager requests the BOP to start the OB WS pump in accordance with BwOP WS-1, STARTUP AND OPERATION OF THE NON- ESSENTIAL SERVICE WATER SYSTEM, and secure the OC WS pump in accordance with BwOP WS-3, SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP, for an upcoming clearance order on the OC WS pump. Align the OC WS for standby after it is secured. Operators have been briefed and are standing by at the Lake Screen House to support WS pump swap. Power Team has requested Unit 1 prepare to lower power 200 MW at 3.0 MWlmin due to grid demand.

After completing shift turnover and relief, the BOP will swap WS pumps in accordance with BwOP WS-1 and BwOP WS-2.

After swapping WS pumps, Power Team will request Unit 1 lower power to 200 MW @ 3 MW/min due to grid demand.

After a measurable change in power, PZR pressure channel 1 PT-455A will fail low. PZR variable and backup heaters will energize and PZR spray valves will close. RCS pressure will rise. The RO will take manual control of PZR pressure and stabilize PZR pressure. lBwOA INST-2, &ERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment B, will be implemented. The RQ ki& restore PZR pressure control to automatic after PZR pressure is restored to normal and an ope[abh,#ZR pressure control channel is selected. Tech na 3.3.2, conditions A and D

After the 1PT-455A failure is addressed, 1A CV pump will tri LOSS OF NORMAL CHA Technical specifications

After the 1A CV pump i manual reactor trip is att 1BwFR-S.1, RESPONS automatic or manual. The RO will initiate emerg 18 AF pump will not start and the 1A A 1BwFR-S.l, the crew will transition to 1

The scenario is complete when the crew

apply. w will implement IBwOA PRI-15.

tore normal charging.

utomatically trip and when a . The crew will implement

rods will not insert in either e reactivity to the core. The d. After completing actions of

L

CTOR TRIP OR SAFETY INJECTION.

tes step 4 of 1 BwEP-0.

Critical Tasks

1. Start 1A AF pump prior tion of step 3 of 1BwFR-S.l

(ERG Critical Task numb

2. Insert negative reactivity into the core by establishing emergency boration flow to the RCS prior to completion of step 4 of 1BwFR-S.I.

(ERG Critical Task number - FR-S.1--C) (WA number - 000029EA1.15 importance - 4.U3.9)

-S.1-B) (WA number -061000A2.04 importance - 3.4/3.8)

~

NRC 07-3 Page 2 of 17

BRAIDWOOD 2007 INITIAL LICENSE EXAM OPERATING OUTLINE COMMENTS

The Importance Factor for WA 2.3.1 1 should be changed from 3.3 to 3.2.

For Event 8, the BOP should not be given credit for a loss of instrument air to containment event.

Source

Admin JPM A (SRO) - Perform Shutdown Margin Calculation

The Importance Factor for KIA 2.3.1 1 was changed from 3.3 to 3.2.

A change was made to not give credit to the BOP for Event 8

Admin JPM C (RO) - Hang Worker Tagout (1A FW Pump)

Admln JPM D (SRO) - Respond to 1PRO3J High Radiatlon Alarm

Scenario NRC 07-1

Comment I Resolution

While an SRO could be expected to perform a Shutdown Margin calculation, it is more job- appropriate (i.e., Content Validity) for the SRO to review and approve completed Shutdown Margin Calculations instead.

Changed JPM to have the SRO candidate review and approve a Shutdown Margin.

1. This JPM should involve more than just hanging 00s cards (e.g., could include incorrect specified sequence of hanging cards and an incorrect position for a component).

2. The Importance Factor for KIA 2.2.13 should be changed from 3.0 to 3.6.

1. Changed JPM to include an incorrect sequence and an incorrect component for the 00s.

2. The Importance Factor for KIA 2.2.13 was changed from 3.0 to 3.6.