ML051240372

Examination Outline Submittal and NRC Comments for the LaSalle Initial Examination - March 2005

ML051240372
Person / Time
Site:	LaSalle
Issue date:	03/07/2005
From:	Ross J Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML050900103	List: ML051240350 ML051240371 ML051240372 ML051240377 ML051240396 ML051240410 ML051240468 ML051240473 ML051240488
References
50-373/05-301, 50-374/05-301 50-373/05-301, 50-374/05-301
Download: ML051240372 (24)

Text

EXAMINATION OUTLINE SUBMITTAL AND NRC COMMENTS FOR THE LASALLE INITIAL EXAMINATION - MARCH 2005

Outline Submittal LaSalle County Station 2005 Initial Examination

Exelan,..

~

txelon Cenerdtioq Company, LLC LaSaIle County Statlor-2601 North 21 Road fMa~~eilles l L 61341-9757 www exeloncorp corn Nuclear November 8, 2004 United States Nuclear Regulatory Commission Attention: Regional Administrator, Region Ill 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 I and NPF-18 NRC Docket Nos. 50-373 and 50-374

Subject:

Submittal of Initial Operator Licensing Examination Outline Enclosed are the examination outlines supporting the Initial License Examination scheduled for the week of March 7, 2005, at LaSalle County Station. This submittal includes all applicable 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 Terrence W. Simpkin at (815) 415-2800. For questions concerning examination materials, please contact John E. Ross at (81 5) 415-2276.

Respectfully, George P. Barnes Site Vice President LaSalle County Station

Enclosures:

(Hand delivered to 6. Palagi, Chief Examiner, NRC Region 111) cc:

NRC Senior Resident Inspector - LaSalle County Station (Without enclosures)

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

b lnitia a

b Item Task Description

1.

L Mv

a. Venfy that the outline(s) fit(s) the appropriate model. in accordance with ES401.

2 S

~~~

~~

b.

Section D.l of ES-401 and whether all K/A categories are appropriately sampled.

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

d. Assess whether the justifications for deselected or rejected WA statements are appropriate.

a. Using Form ES-301-5. verify that the proposed scenario sets cover the required number of normal evolutions. instrument and component failures. technical specifications, Assess whether the outline was systematically and randomly prepared in accordance with v '

and major transients.

w M

U L

A T

0 R

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity. and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualiative Hw and quantitative criteria specified on Form ES-3014 and described in Appendix D.

Hn

~~~~

~~

~~

3.

W I

T

a. Venfy that the systems walk-through outline meets the criteria speafied on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as speufied on the form (2) task repetition from the hst two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test@)

(4) the number of new or modified tasks meets or exceeds the minimunsspechd on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Venfy that the administrative outline meets the Criteria speakd on Form ES-301-1:

(1) the tasks are distributed among the topics as specmed on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the bst two NRC licensing examinations

c. Determine if there are enough different outlines to test the prowed number and mix of applicants and ensure that no items are duplicated on subsequent days.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

c. Ensure that WA importance ratings (except for plant-specific priorities) are at least 2.5.

d. Check for duplication and overlap among exam sections.

4.

E N

E A

e. Check the entire exam for balance of coverage.

L

f.

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

Nn,

a. Author

b. Facility Reviewer r)

I W

1-w-12 do('

c. NRC Chief Examiner (#)

d. NRC Supervisor 2 Note:

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

ES-201, Page 25 of 27

ES-30 1 Administrative Topics Outline F o ~ E S - 3 0 1 - 1 Facility: LaSalle County Station Examination Level: SRO Date of Examination: 03/07/2005 Operating Test Number: 2003-01 Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation control Emergency Plan Type Code*

M P

D N

D Describe activity to be performed Create and Place an Equipment Status Tag (EST) on the Main Steam Line (MSL) Radiation Monitor Recorder 2.1.15 2.313.0 Review A New Case Core Performance Log and Report findings to the Shift Manager (Similar to previous NRC Exam item.)

Review Completed Surveillance and Determine any Action Requirements 2.1.25 2.8/3.1 2.2.12 2.613.0 Given a Radiation Survey Map, Determine Correct Area Posting Requirements 2.3.1 2.213.0 Determine Reportability Requirements per EP-AA-1 14, for a Shutdown Required By Technical Specifications 2.4.30 2.213.6 NOTE:

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

• Type Codes & Criteria:

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

(N)ew or (Mkdified from bank (2 1)

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

(S)imulator ES-30 1, Page 22 of 27

ES-301 Control Room/ln-Plant Svstem Outline Form ES-301-2 Facility: LaSalle Countv Station Examination Level: SRO (see NOTE at bottom of page)

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

Date of Examination: 03/07/2005 Operating Test Number: 2003-01 System / JPM Title I

Safety Code**

Function

a.

Downshift RR Pumps to Slow Speed with One Pump Tripping to Off I A, D, S 1

202001

b.

Initiate RClC for Level Control with Failure of 1 E51-FO46 to Automatically Open A, E, N, S 2

21 7000

c.

Manually Initiate Low-Low-Set (LLS) and then Reset LLS as Directed by I N, S the Unit Supervisor 3

239002

d. Shutdown High Pressure Core Spray (HPCS) After an Automatic Initiation 1 N, L, S with High Drywell Pressure Present I

4 209002

e.

Start Containment Spray with a Failure of the Second Valve to Open I k4, E, L, N, I

5 226001

f.

Perform LOS-DG-M3 (1 6 DG) with a Loss of the SAT I

6 264000

g.

Reset a Half-Scram with a Blown Group Scram Fuse 7

2 12000

h.

Not Applicable 1 NIA I N/A In-Plant Systems * (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i.

In-Plant Actions to Lineup Cycled Condensate (CY) to Low Pressure Coolant Injection (LPCI) for Vessel lniection 1 D, E, L, R

j.

Hydraulically Isolate an Inoperable Control Rod Drive (CRD) Hydraulic Control Unit (HCU) 2 203000 1

201001

k.

Locally Start the OA VE Charcoal Filter N, R 9

290003 All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• • Twe Codes I

Criteria for RO / SRO-I / SRO-U I

4-6 / 4-6 /' 2-3 (A)ltemate 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 (R)CA 21 /21/21 (S)imulator NOTE: SRO-I will perform all 10 JPMs and SRO-U will perform the following five JPMs: d. (ESF), e., f., i.,

59 / 58 114 21 / 21 121 21 / 21 / 21 22 f 22 f 21 1 3 /<3 / 12 (randomly selected) and j.

ES-301, Page 23 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Instructions:

1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event p;

TS are not ap licable for RO applicants. ROs must serve in both the at-the-controls (ATC) and component &C) malfbnctions and one major transient, in the ATC position.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. *Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirement.

balance-of-lant ( L OP) positions; Instant SROs must do one scenario, including at least two instrument or

2.

3.

NOTE: Can use any one o Author:

NRC Reviewer:

/

ES-301, Page 26 of 27

- ES401 BWR Examination Outline FORM ES-401-1

acility Name: LaSalle County Station Date of Exam: March 07, 2005 Jote: 1.

2.

3.

4.

5.

6.

7 :

8.

9.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by *I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions tha do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.

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.

Absent a plant-specific priority, only those WAS 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.

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

The generic (G) WAS 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.

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. Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the WA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

ES-401 2

Form ES-401-1 11ES-401 BWR Examination Outline Form ES-401-Emergency and Abnorn II E/APE # I Name I Safety Function 95001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 0

6 295003 Partial or Complete Loss of AC 16 /

</

0 3

295004 Partial or Total Loss of DC Pwr I6 id v

0 2

295005 Main Turbine Generator Trip I 3

))295006 SCRAM I 1

29501 6 Control Room Abandonment I7 2 0

295018 Partial or Total Loss of CCW I 8.-

J 0

6 295019 Partial or Total Loss of lnst Air I 8 295021 LOSS of Shutdown Cooling 14 \\J I

0 2

295023 Refueling Acc I 8

295024 High Drywell Pressure I 5 fi 95025 High Reactor Pressure I 3 95030 Low Suppression Pool Wtr Lvl I 5 0

8 r -

295031 Reactor Low Water Level I 2 I 1 7,.

1 1

295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 1 7.

00000 Plant Fire On Site I8 (IWA Category Totals:

1 4 1 3 1 4 1 3 I Plant Evolutions - Tier l1Group 1 (RO)

A G

KIA Topias)

IR 2

Natural arculatm 3 5 D C eledncalloads 3 4 I 3 1 R e d w SCRAM Plarn-Spec#~:

I I I IRPS I 3.6 Reactor water level response CMrol rod posrtim 3 8. 4 ?

2 3 4 O'.3 m l d y to expram a d ap;thl system lrnits and pecautms 2

Effeds on cnmponen(lsystem operatmi 3 5 Offgas system 2 8 Feeding and W i n g reactor vessel 3 3 Fuel pool cwlmg and cleanup system 2 9 I 4.2 I

lSuPPRESSED 1

R e a d a walw bwl ndlcalm 3 6 NPSH czuwdaratms for ECCS pumps 3 5 Anernate njectl~n systems Plant-rpecrfc 3 8 4 2 Reactorpower 1

I 2 5 satus mtena which require the notification Fire Classlfmtms by type 2 5 3

3 Group Point Total 1

1 2

ES-401, Page 17 of 33

ES-401 3

Form ES-401-1 BWR Examination Outline F

o

~

ES-401-ES-401, Page 18 of 33

ES-401 4

Form ES-401-1 ES-401. Page 19 of 33

ES-401-1 5

Form ES-401-1 BWR Examination Outline Form ES-401-IIES-401 ES-401, Page 20 of 33

ES-401 2

Form ES-4 BWR Examination Outline Form ES-401-Ememencv and Abnormal Plant Evolutions - Tier l/GrouD 1 ISRO)

K K

EIAPE # I Name / Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 8 4 295003 Partial or Complete Loss 295004 Partial or Total Loss of DC y&,

7/

295005 Main Turbine Generator Trip I 3 I.-

A A

G WA Topic@)

IR 1

2 04, o4 Abtlity to recognize abnormal indicabons for system operating parameters whtch are entry-level condibons for emergency and abnormal operating procedures 4 3 Extent of partial or complete loss of D C power 39 95006 SCRAM I 1 Ib I I I 3 7 Knowledge of bases in technical speaficabons for limiting condibons for operations and safety limb 1

295016 Control Room Abandonment I 7

!@,I 295018 Partial or Total Loss of CCW I 8

295019 Partial or Total Loss of Inst. Air / 8 0

0 I:

T-j I IReactorvessel metal temperature I

3.3 1

295021 Loss of Shutdown Cooling I 4 95023 Refueling Acc I 8

1 Ability to recognize abnormal indications for system operabng parameters which are entry-level condibons for emergency and abnormal operabng procedures 4 3 O4 0

1p95024 High Drywell Pressure I5 0

0 5026 Suppression Pool High Water 95027 High Containment Temperature / 5 95028 High Drywell Temperature I5 5037 SCRAM Condibon Present and Power 95038 High Off-site Release Rate I 9 0

1 0

1 Readorpower 4 2 2

0 3

4 Group Point Total:

WA Category Totals:

0 0

ES-401, Page 17 of 33

ES-401 3

Form ES-401-1 IR 2.9 4

3.4 ES-401 BWR Examination Outline FOIWI ES-401-Emergency and Abnormal Plant Evolutions - Tier llGroup 2 (SRO) 0 0

0 1

1 0

0 0

a 0

0 0

0 0

0 1

0 0

0 0

K/A Category Totals 0

0 0 0 1

2 Group Point Total 1

1 1

1 I

I I

L-I' ES-401, Page 18 of 33

Form ES-401-1 ES-401 4

BWR Examination Outline F

o

~

ES-401-ES-40 1 ES-401, Page 19 of 33

ES-401 5

Form ES-401-1 ES401 BWR Examination Outline Plant Svstems - Tier Z/GrouD 2 (SRO)

ES-401, Page 20 of 33

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

F o

~

ES-401-3

[Facility Nan Category

l.

10 1

/ /

7.

y;

- - I 2

Conduct of Operations 1

2.

Equipment Controt- $$

--/

'-9

3.

Radiation.-

Control *'/

r 3:LaSalle County Station Date of Exam:March 07, 2005 RO SRC IR IR 2.1. 0 1 ~ n o w ~ g e of tonduct d operations requaements 3.7 1

3 8

12.

' 31 are ax~actly refledmg Ihe desired plant lneup 4.2 1

3.9 WA #

Topic Abillty to locate control mom switches. controls and mdidions and to determne that they I

I 3.8 1

Abillty to locate and operate components. lncludng local mtrols 3.9 3.4 2.1.

1 -

~2.2. 20 Knowledge ofthe process for managtng bwbleshootmg adivflles I

1 1

2 I 2.9 I 1 I 3.3 Abillty to pertarm procedures to reduce e x c e s w levels d radialon and guard aganst 2.3. 10 I personnel exposure I 2.9 2 4. 01 of EOP entry conditions and nnmediate adm steps 4.3 1

4.6 2.4. 34 3.8 1

3.6 Knowledge of RO tasks performed wtwde the man m r o l room durng emergency operatlw idwtng system eeography and system nplicatiw 2.4. 22 3

4 oo8(81ms 2.4. 40 \\ Knavlsdee d the SROs responubibtles n emergency plan nplementatm 4

2.4.

2.4.

d me bases fa pn0rltuu-q safety fvldms dunng abmnnaUemerpency 2.3 P

'.- 2, y, If 5 1 -

l 1

I k

ES-401, Page 26 of 33 J'

Turnover:

0 Continue the power ramp per the QNEs request L

Event Malf.

Event Event No.

No.

Type

• Description I

2.

kln24bnm (C)

BOP RCIC Drain Pot Failure

1.

NIA (R)

RO Increase Power per the QNE, using RR Flow Control (N)

SRO Supervises crew activities ro5 63 (C)

SRO Technical Specification Determination

3.

mrd280 (C)

RO CRD Pump trips/Start standby CRD pump SRO Directs actions per the annunciator and normal procedures

4.

mnb059 (I)

RO Instrument Line Break (1 C NR, RR AT, & HP LvI-8)

(I)

SRO Technical Specification Determination (M) SRO Automatic Scram Failure, manual scram works. LGA Entry 5.

mrc04 1 (M)

RO LOCA in the Drywell, with loss of High Pressure Injection sources.

Conditions

• (Nbrmal, (R)eactivity, (I)nstruement, (C)omponent, (M)ajor Transient Examiners:

Operators:

Initial Conditions:

0 0

Ramping to full power following a unit startup Rated Rod Line with core flow at -85 Mlbmhour Page 1 of2

Narrative Summary NRC Scenario-01:

Event Description

1.

Initial conditions have the plant completing a startup, LGP-3-1 is in progress. Power is approximately 93% RTP. The examinees are directed to continue ramping power to 100% using Reactor Recirculation Flow Control Valves.

The RCIC drain pot high level alarm will annunciate. The examinees will recognize that the drain bypass valve 1 E5 1 -F054 has automatically opened. Following the annunciator procedure, when the high level alarm does NOT clear, they will have to close the RCIC Trip and Throttle Valve lE51-F360. This will render the RCIC system inoperable and the Unit Supervisor will have to make a Technical Specification determination.

The running CRD Pump will trip. Per the annunciator procedure, the NSO will verify that Charging Water Pressure is greater than 500 psig, and then start the standby CRD pump, and follow up with normal operating procedure.

An instrument line reference leg will rupture in the reactor building.

Among other indications, this will cause the 1 A RR Pump Low Differential Temperature timer will initiate. By procedure, the NSO will bypass this timer. The Unit Supervisor will have to make another Technical Specification determination.

For this event a Reactor Recirculation line will break causing LOCA conditions in the Drywell. Automatic RPS Scram will fail however manual actions to scram will be successful. The Unit Supervisor will enter the EOPs and take actions to control Reactor Water Level and Drywell Pressure. The MDRFP trips shortly after starting. Bus 143 trips on overcurrent. RCIC is not available from an earlier event. This will require a blowdown for level control.

Termination The scenario can be terminated when the examinees have FWV and Containment parameters stable and under control.

2.

3.

4.

5.

Critical Steps:

1. Manually scram the reactor when automatic setpoint is exceeded.

2. Perform a blowdown per the EOPs when level cannot be restored and maintained above -1 50 inches.

Page 2 of 2

(C)

(C)

RO SRO B RPS Fails to scram (Electrical ATWS)

Facility: LaSalle County Station Scenario No.: Scenario-02 Op Test No.: 2003-01 NRC Exam Examiners:

Operators:

Initial Conditions:

0 Ramping to full power following a unit startup Full power with flow backed off to -85 Mlbmhour Turnover:

0 0

Start the 1 B CRD, shutdown 1 A CRD for oil change Continue the power ramp to 100% power per the QNE Event No.

Malf.

No.

Event Event Type*

Description (N)

RO Swap running CRD pumps I.

NIA

2.

rO60 1 Low ADS Bottle Bank Nitrogen Pressure Technical Specification Determination

'v

3.

various overrides 1 B TDRFP Seal Injection Pump trips and standby fails to start

4.

zc 1 1025 CRD Accumulator Trouble Alarm (low pressure)

(C) I R O SRO I Technical specification Determination

5.

k6k07wt8 (C) 1 RO 1 Loss of4160 vac Bus 141X (C)

SRO

6.

NIA Reduced of Heater Drain Pump Forward

~

~

~~~

Recirculation loop rupture - LOCA conditions in the Drywell

7.

mrc033

~~

mrpO 18

8. -

• (N)ormal, (R)eactiv Page 1 of 2

Narrative Summary NRC Scenario-02:

W Event

1.

2.

3.

4.

5.

6.

7.

8.

Termination Critical Steps:

1. Reduce power per the abnormal operating procedure to prevent a loss of Feedwater and resulting scram following loss of 14 1 X.

2. Use multiple methods per EOP Support procedure to insert control rods during an ATWS.

Description This event is a normal swap of the running CRD pump (from 1 A to 1 B) per the procedure.

Drywell pneumatic trouble alarm is received, an NLO is send to investigate. The NLO reports back to the control room that the South Bottle bank pressure is actually below the alarm setpoint. The Unit Supervisor is expected to make a Technical Specification determination.

The running TDRFP Seal Injection Pump will trip and the standby pump will fail to automatically start. The NSO will take actions per the annunciator procedure.

Next a CRD HCU Accumulator will alarm. The examinees are expected to dispatch an NLO to the effected HCU. The NLO reports that the accumulator has low pressure. The Unit Supervisor is expected to declare the accumulator inoperable and make a Technical Specification determination.

Bus 141X will trip. This causes loss of two Heater Drain pumps. The NSO is expected to start the standby Heater Drain pump.

The examinees are expected to enter LOA-HD-101 and reduce power. If this is not done before Heater Drain Tank level increases to 9-feet the HD Flushing valves will open and the Feedwater Pumps will trip on low suction pressure.

Next a LOCA will develop in the Drywell. The event is entered when directed by the lead examiner or immediately if the reactor automatically scrams due to loss of Feedwater. The examinees are expected to enter the EOP based on RPV Level and Containment Pressure.

This event is an electrical ATWS when RPS B fails to trip when required.

The examinees are expected to enter LGA-0 10 and LGA-NB-0 1 and take actions to shutdown the reactor. When the first fuse is pulled rods will start to move however the SDV will fill and they will have to reset the scram, drain the SDV and re-scram reactor to get rods to go full-in.

Scenario can be terminated when the examinees have RPV and Containment parameters stable and under control.

Page 2 of 2

Facility: LaSalle Countv Station Scenario No.: Scenario-03 Op Test No.: 2003-01 NRC Exam Examiners:

Operators:

6.

I mnbl05 (M)

RO Small Steam LOCA with containment bypass path mca008 (M)

SRO Initial Conditions:

0 0

Reactor Power is GO%

Startup in progress per LGP 1 Ready to roll the main turbine Turnover:

Continue to pull rods per the sequence package mrd218 mrd213 Event No.

(M)

SRO

1.

2.

3.

4.

5.

Malf.

No.

NIA Event Event Type

• Description (R)

RO Continue pulling control rods per the sequence package W)

SRO Stuck control rod, moves after increasing Drive Water pressure Loss of RPIS indication for rod 58-43 at notch 12 Technical Specification Determination Failure of 1C VR Fuel Pool Exhaust Radiation Monitor upscale Technical Specification Determination Off-Gas suction rupture and loss of vacuum and manual scram, 3 stuck rods (ATWS), manually drive rods in Page 1 of2

Narrative Summary NRC Scenario-03:

Event Description

1.

2.

The RO will continue to pull control rods per the startup sequence package.

One control rod is discovered to be stuck. Several attempts to free the rod using the normal operating procedure (LOP) will fail. The LOP will direct the operator to take actions per the abnormal operating procedure. When drive water pressure is increased sufficiently, the rod will free itself. And the startup can continue.

While pulling a control rod one of its RPIS reed switches will fail at the final withdrawal position. The crew will take actions per the abnormal operating procedure and the SRO will make a Technical Specification determination.

One of the four Reactor Building Ventilation Fuel Pool Exhaust Radiation Monitors fails upscale. This will cause an annunciator to alarm in the control room. The Unit Supervisor is expected to make a Technical Specification determination.

A rupture in the Off-Gas 2nd Stage Air Ejector line will cause a slow loss of vacuum. The crew will have time to dispatch operators to look for air leakage into the main condenser. The size of the leak continues to increase until the crew is forced to manually scram the reactor. When the reactor is scrammed, 3 control rods will stick full-out rendering a low power ATWS.

The RO will be able to close the Drive Water Pressure control valve and then manually drive the three control rods full-in.

Next a steam leak LOCA will develop with a containment bypass path.

Termination The scenario can be terminated when the examinees have RPV and Containment Parameters stable and under control.

3.

4.

5.

6.

Critical Steps:

1. Initiate Suppression Chamber Sprays and Drywell Sprays to control containment parameters

2. Use EOP Support Procedures to insert control rods following the scram.

Page 2 of 2

COMMENTS ON LASALLE 2005 EXAMINATION OUTLINE Outline Section Admin Topics System JPMs Written Exam I Written Exam Comment and Resolution Comment: Be sure that the JPM covering review of a Core Performance Log is clearly different than that given in the previous exam.

Resolution: Different initial conditions will be used and different parameters will be out of specification.

Comment: Be sure that the JPM covering review of a completed surveillance is safety significant.

Resolution: JPM required identification of an inop RClC system.

Comment: Be sure there or no JPMs with only one critical task, and be sure there is safety significance to each JPM.

Resolution: To be verified during on site validation.

Discussed how random selection of KAs was done.

Resolution: KA selection was random Discussed not over using 2 out of 2 twice type of question.

Resolution: Will be evaluated during written exam review.