ML073170204

Examination Outline Submittal for the Quad Cities Nuclear Power Station Initial Examination June 2007

ML073170204
Person / Time
Site:	Quad Cities
Issue date:	11/09/2007
From:	NRC/RGN-III/DRS/OLB
To:	Exelon Generation Co, Exelon Nuclear
Shared Package
ML072010156	List: ML073170204 ML073170213 ML073170229 ML073170238 ML073170287 ML073170299 ML073170307
References
50-254/07-301, 50-265/07-301 50-254/07-301, 50-265/07-301
Download: ML073170204 (20)

Text

EXAMINATION OUTLINE SUBMITTAL FOR THE QUAD CITIES NUCLEAR POWER STATION INITIAL EXAMINATION JUNE 2007

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

b Item Task Description

1.

w R

i T

E

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

b. Assess whether the outline was systematically and randomly prepared in accordance with S'?.ctW D.1 of ES-401 andwhether all KIA categories are appropriately sampled.

c. Assess whether the outline 0ver.emphaSizes any systems, evolutions, or generic topics.

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

PI' A N\\4 Nb

a. Using Form ES-301-5, verily that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures. technical specifications, S

2' I and major transients.

I 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 cornpromising 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@), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

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

(1) the outline(s) contain@) the required number of control room and in-plant tasks distributed amona the safehr functions as soecified on the form

3.

w Nlq (21 task repel ton from the last M o hRC exam na1,ons s IN m n the mtts speclt ed on tne form (31 no tasfis are dupi catea from tne appl cants' aJad lesi(s) 1 Author b Facility Reviewer (+)

c NRC Chief Examiner (#)

d NRC Supervisor

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Note:

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

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

Facility: Quad Cities Units I 8 2 Date of Examination: June 2007 Examination Level (circle one): RO Operating Test Number: 2007-301 Conduct of Operations WA2.1.19 Conduct of Operations WA2.1.31 Equipment Control WA 2.2.13 Radiation Control WA 2.3.2 Emergency Plan I

I NIA P

Review Printout of Thermal Limits N

Electrical Distribution Surveillance M

Determine Isolation Points for a Clearance Order for the Safe Shutdown Makeup Pump M

Select Personnel for radiation work for surveillance testing 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 8 Criteria:

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

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

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

(S)imulator

ES-301 Administrative Topics Outline F

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ES-301-1 Administrative Topic Conduct of Operations (see Note)

WA 2.1.33 Conduct of Operations WA2.1.1 Equipment Control WA 2.2.13 Radiation Control WA 2.3.2 Facility:

Quad Cities Units 1 & 2 Date of Examination: June 2007 Examination Level (circle one): SRO Type Code*

M M

M M

Emergency Plan WA 2.4.46 & WA 2.4.4 II I

N, S Operating Test Number:

2007-301 Describe activity to be performed Electrical Distribution Surveillance Test Authorization of Overtime Determine Isolation Points for a Clearance Order for the Safe Shutdown Makeup Pump Select Personnel for radiation work for surveillance testing EAL Determination for OPRM/RPS Trip Failure during Power Oscillation Event & Complete NARS form.

I 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; i 4 for SROs & RO retakes)

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

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

(S)imulator

ES-301 Control Roomlln-Plant Systems Outline F

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ES-301-2

• Type Codes Facility: Quad Cities Units 1 & 2 Date of Examination:

June 2007 Exam Level (circle one): RO Operating Test No.: 2007-301 Control Room Systems" (8 for RO; 7 for SRO-I)

Criteria for RO / SRO-I I SRO-U System I JPM Title

a. Perform the MSlV Closure Timing Test

b. Roll The Turbine

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c. Perform the SBGT Monthly Operability Test with Heater Failure

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d. Start RClC (Failure of Auto Start) and Control Reactor Water Level

e. Bypass the Rod Worth Minimizer

f. Shutdown the U-1 Diesel Generator with Early Trip

g. Change-Over Reactor Feed Pumps with Failure of Auxiliary Oil Pump to Trip

h. Transfer Recirculation Flow Control from Manual to Master In-Plant Systems" (3 for RO; 3 for SRO-I)

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Safety I

Function Type Code' 1 N E 1

2

i. Locally Start-up the HPCl System to Control RPV Level

i. Transfer Power from Reserve Power to MG Set I N 1

7

k. Place RBCCW Heat Exchanger in Service 1 N,R 1

8

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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.

[A)lternate path

[C)ontrol room

[D)irect from bank

[E)mergency or abnormal in-plant fL)ow-Power (N)ew or (M)odified from bank including 1 (A)

P)revious 2 exams

[R)CA 4-6 I 4-6 / 2-3

< 9 / % 8 1 % 4 2 1 / 2 1 / 2 1 L 1 1 2 1 1 2 1

> 2 / > 2 1 > 1 I 3 I I 3 / I 2 (randomly selected)

L 1 1 2 I/>

1 (Sjimulator I

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 System I JPM Title

a. Perform the MSlV Closure Timing Test Type Code' Safety Function S, M 5

l S, N, L I

4

b. Roll The Turbine

h. Transfer Recirculation Flow Control from Manual to Master

c. Perform the SBGT Monthly Operability Test with Heater Failure I S, D, A, E, P I 9

S, N, A 1

d. Quarterly Testing - Turbine Stop Valve Testing I SIN 1

3

i. Perform IO-Minute Operator Actions per QCARP 0050-01

j. Transfer Power from Reserve Power to MG Set

k. Place RBCCW Heat Exchanger in Service

e. Bypass MSlV Group I Isolation Signal I S,D 1

7 N, E 2

N 7

N, R 0

f. Shutdown the U-1 Diesel Generator with Early Trip I S, D, A, E 1

6

• Type Codes (A)lternate path (C)ontrol room (D)irecl 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 (RPA (S)imulator l

2

g. Change-Over Reactor Feed Pumps with Failure of Auxiliary Oil Pump to Trip I S, D,A Criteria for RO I SRO-I I SRO-U 4-6 / 4-6 / 2-3 i 9 1 s 8 1 % 4 2 1 1 2 1 1 2 1 2 1 1 2 1 l L I 2 2 1 2 2 / > 1 i 3 I i 3 / < 2 (randomly selected)

L 1 / L 1 1 2 1 Need to delete one of the above Simulator JPM's for SRO!!

ES-401 BWR Examination Outline Form ES-401-1 Note:

1.

Ensure that at least two topics from every applicable KIA 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.

Systemslevolutions 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 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 WA 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 KIA catalog, and enter the KIA numbers, descriptions. IRs.

2.

3.

4.

e.

6.

7.'

8.

9.

2 FOIWI ES-401-1 ES-401 AA1.02EmergencyGeneratas 295005 Main Turbine G m t o t Trip I 3

295028 High Drpell Temprawre I 5 295030 Low Suppresson Poal Wtr Lvl I 5 295031 Reactor Lau water Level 12 295016 Contml Rmm Abandonment I 7 295018 Partial or Tdal Lms of CCW I8 04 03 2.4.41 (SRO)

EK2 04 D-ll venblabon 3 6 14 EK3 02 RPV Flooding 3 5 15 4 1 82 dassmcatons 2 4 41 (SRO) Knau(edge of me emergency a&n I& thresholds and 02 HPClapwabon 3 5 16 05 Reactw Core Iblaban Cmllna 4 3 17 -

295021 Lms of Shutdown Wing I 4 295023 Refueling Acc I 8 I

295024HighDrywellPressurel5 2 4 t Knowledge of EOP en@ mnddons and immediate adon steps 4 6 03 AK2 03 Contml R m

W A C 2 9 EReQIOnmm AK3 01 Backup air supply 21.7 Evaluate plant perromance and make o p e m a l judgements based on oprabng daradenskx 3 7 5

6 -

295026 Suppression Pml High Water Temp I EK3 05 Reador Swam

ES-401 3

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ES-401-1 295035 Secondary Conbmment Hgh Dlfferenbal PreUUre I 5 295036 Secondary Confainmem High SurnplARa Wafer Levd I 5 500000 Hiah CTMT H y d m Conc I 5 E M 0 1 BWR Examinallon Outline Form ES-401-I Emergency and Abnormal Plant Evolutions - Ter I/Gmup 2 (RO / SRO) 2 9 5 m Low Reauu Water L e d I 2 AK3 01 Reamlam pump run badl 01 Radiation releases 2 9 26 08 Wel Well vent svslern 3 2 21

ES-401 4

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ES-401 201-1 7 28 29 30 31 32 33 86 34 35 36 87 37 88 38 39 40 41 42 43 89 44 45 -

46 ES-401 BWR Examination Outline F o n ES Plant Systems - Ter ZGroup 1 (RO / SRO) 259002 Reactor water Level

K1.03Omlfe PoWerSWrceS

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ES-401-1 ES-401 5

cbaSesforEOPs I

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I I

I I

I I

I I

241000 ReadorITurbme Pressure 02 Reactor pressure Reguklor

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

Form ES-401-3

2.

Equipment Control Facility:

Date of Exam:

valuate parametric 2.2.24 Ability to analyze the effect of maintenance activities on LCO 2.6 69 2.2.13 Knowledge of tagging and clearance procedures 3.6 70 2.2.28 New and spent fuel movement procedures 2.6 71 2.2.26 Refueling administrative requirements 3.7 96 status

4.

Emergency Procedures /

Pian

3.

Radiation Control 2.4.12 General operating crew responsibilities during emergency 3.4 74 2.4.49 Ability to perfon without reference to procedures those actions 4.0 75 operations that require immediate operation of system components and controls.

2.4.28 Procedures relating to emergence response to sabotage 3.3 99 2.4.46 Ability to verify that the alarms are consistent with the plant 3.6 100

Appendix D Scenario Outline Form ES-D-1 Event Malf. No.

No.

1 NIA 2

N/A 3

nm1413249d 4

rrl9A 5

ms04c Event Event Type*

Description R (ATC)

Raise recirculation flow to achieve 100% power IAW QCOP 0202-03 and QCGP 3-1.

N (BOP)

Shut down RHR Torus Cooling IIC (ATC)

Fail LPRM 32-49-D Downscale. TS 3.3.1.1 TS (SRO)

IIC (BOP)

TS (SRO)

M (all)

ATWSIECCSIRFPIHPCIIRCiC~URB transmitter 1-0263-23A slowly fails downscale. TS 3.3.2.2, 3.3.4.1, 3.3.5.1, 3.3.5.2 Rising Containment pressure and temperature due to a LOCA. Initiate an Emergency Depressurization when torus pressure cannot be maintained or when drywell temperature cannot be restored. Includes a failure of Drywell Spray.

I I

Appendix D Scenario Outline F

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ES-D-1 Even t No.

1 2 & 3 4

5 Facility: Quad Cities Unit 1 8 2 Scenario No.: 2 Time Start:

Examiners:

Operators:

(SRO)

(ATC)

(BOP)

Malf. No.

Event Event Type' Descrlptlon R (ATC)

N/A Imf NMOBB I/C (ATC) 100 TS (SRO)

TS 3.3.1.1 N/A TS (SRO) ano9013b13 I/C (BOP)

ADS Timer initiation. Invalid signal. TS 3.3.5.1.3.5.1 Continue plant shutdown by inserting rods IAW step F.4 of QCGP 2-1 and 4-1.

APRM channel #2 fails upscale with a failure to % scram.

Large Lube Oil Leak from Unit 1 EDG. Unit 1 EDG to be declared INOPERABLE. TS 3.8.1,3.5.1,3.0.3 6

7 rrl Oa M (all)

Recirculation Suction line break.

e02 IIC (BOP)

I/C (ATC)

Station Blackout occurs. Take actions to monitor plant parameters and restore electrical power IAW QCOA 6100-04, QCOA 6100-03 and/or QCOP 6500-08.

L (N)ormal. (R)eactwlty. (1)nstrument. (C)omponant, (M)ajor, (T)echncal Specification

Appendix D Scenario Outline F

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ES-D-1 Facility: Quad Cities Unit 1 8 2 Scenario No.: 3 Time Start:

Examiners:

Operators:

(SRO)

(ATC)

(BOP)

Initial Conditions: Reactor power is at 47%.

Turnover: The shift will start the B SBGT system top perform its monthly Operability Surveillance I

5 eg07a msO9d Event Event N (BOP)

TS (SRO)

IIC (ATC)

Start Standby Gas Treatment System.

I C RHRSW Inoperable (All oil has leaked out of bearing.)

TS 3.7.1 Control Rod Drive Pump Failure.

I/C (ATC)

IIC (BOP)

TS (SRO)

I/C (BOP)

R (ATC)

Rod drift from 00 to 02 on CRD pump start.

Loss of Power to Bus 13-1 with a failure of the EDG to start.

TS 3.8.1~1, 3.0.1.0, 3.8.1.D, and 3.8.1.8 (Unit 2)

Turbine Generator slowly loses stator water cooling. Both ATC and BOP need to take actions IAW QCOA 5300-01.

Emergency down power by inserting control rods.

M (all)

I/C (all)

MSL break with a failure to receive a Group I isolation on low steam pressure, close the MSlVs to limit plant cooldown to less than 100 degrees, and recognize that a TS Safety Limit has been violated if pressure drops below 785 psig with power above 76%

Appendix D Scenario Outline F

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ES-D-1 Event NO.

1 Malf.

Event Event No.

Type*

Descrlptlon NIA R (ATC)

Lower 1A recirculation pump speed.

Start 1 B recirculation pump and monitor parameters IAW QCOP 0202-02.

3 4

5 6

7 N/A TS (SRO) imf IIC (ATC) rd03R2 TS (SRO) uncoupled and over-travels to position 49. Rod F-7 (22-27).

27 TS 3.1.3 swOlc IIC (BOP) imf I/C (ATC) fwl7c pump to start.

mcO8 M (all)

OPRM Part 21 Inoperability. TS 3.3.1.3.A and 3.3.1.3.6 Rod drifts from position 48 to 46. Upon return to 48, rod is found Trip of 112 Service Water Pump. Start 1B fails to start. Manual Start 1A or 2A Service Water Pump.

" C CondensateIBooster pump trip with a failure of the standby Loss of condenser vacuum leads to ATWS. Bypass valves eventually close due to lowering vacuum. SRVs used for pressure control.

IIC (all)

.I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification