ML030800068

Outline Submittal with NRC Comments for the Quad Cities Examination - Dec. 2002

ML030800068
Person / Time
Site:	Quad Cities   (DPR-029, DPR-030)
Issue date:	02/04/2003
From:	Lanksbury R NRC/RGN-III
To:	Skolds J Exelon Nuclear
References
50-254/02-301, 50-265/02-301
Download: ML030800068 (46)

Text

OUTLINE SUBMITTAL WITH NRC COMMENTS FOR THE QUAD CITIES EXAMINATION - DEC 2002

QUAD CITIES 2002 INITIAL EXAM OUTLINE REVIEW COMMENTS General Review of Audit topics to NRC topics:

Appeared to have similar topics between NRC and Licensee's Audit Exams.

"* SDC and RHR (diff modes) - found to be OK due to different locations

"* AC electrical transfer / supply buses - OK due to different actions

"* Bypass RPS and bypass reactor bldg. vent - OK similar in bypass but different effect

"* RCIC starting - RCIC manual start SRO Admin JPM:

General Note: ensure admin JPMs are task related and not a simple look-up type questions written in a JPM format.

Ensure A2, clearance authorization is for something safety related (significant equipment)

Ensure A4, challenges applicants and not a simple look up or follow flowchart Note: A.1.b, is similar in intent, i.e., K/A, knowledge of shift staffing/manning, as that of licensees audit exam - licensee ensured different actions Note: A4 must be careful, audit exam is to fill out NARS form for General Emergency which is part of the E plan actions which would include PARS. Ensure NRC exam is different then audit.

RO Admin JPM:

General Note: ensure the tasks are more than just one simple step or one simple critical step, or that is based on just a simple look up. Ensure there is some diagnosis and decision making tasks (steps).

A2, tagout - ensure it is on safety related (significant equipment)

A3, ensure it is not just a simple dose calculation, make it operationally oriented Systems JPM:

B.1.b, make it significantly different from the audit test. There was similarity and needed correction. Instead of just the failure of the push button (too easy as an alternate path) rather have it initially start, but with failure with auto flow or control and other auto lineup, which requires alternate path to manually fix/align and ensure tech spec flow requirements.

B.1.e, what's the success path for the alternate JPM?

B.1.g, what is the safety significance, even if an applicant does not correctly pressurize main steam line - check K/A designation? Suggest scrammed PCIS and now restore steam lines.

B.1.e, similar to audit simulator scenario normal evolution, i.e., perform CS surveillance.

Found to be OK, NRC exam has alternate path.

QUAD CITIES 2002 INITIAL EXAM OUTLINE REVIEW COMMENTS Simulator Scenarios:

Scenario # 1 Event 3 - B FWRV lockup appears to be similar to audit exam scenario normal evolution, i.e.,

manual control of B FWRV - consider replacing. Apparently different controls due to new electronic feed control system.

Need malfunction after major malfunction and after entry into EOPs.

Event 6, rod drift out, seems similar to JPM B.1.d. Found OK, actions different.

Seems not too challenging, major malfunction only an ATWS, no challenge in controlling level when all ECCS are available.

Appears no containment or reactor level challenges.

Appears to concentrate on one leg of EOPs - no challenge to others?

Recommended Additions and Changes:

Ensure rod drift and JPM actions are different.\\

Have a small break LOCA with no high pressure ECCS injection, which will require ADS with ATWS (ATWS - power/level control for power, with level decrease, but will require decision to use alternate injection sources for maintaining level control) Plus challenges to containment atmosphere, temperature/pressure, require torus spray/cooling and drywell spray Scenario # 2 Initial condition give 1B SW pump OOS, but event 3 has a SW pump trip. Narrative notes A SW (2B) pump trip requiring a standby pump to be manually started. B is already OOS, is there a third SW pump? Noted that they must start 2A and not the 1 / 2 pump?

Event 4, a rod drift one notch, not really significant malfunction? If no action no consequence, it appears within Tech Spec limits. Found must take action to restore, and address Tech Specs.

Scenario # 3 Event 3, IRM failure, seems too simplistic only require bypassing, OK, it still needs panel manipulation Event 4, reactor bldg radiation monitor failure - questionable with a rad monitor failure in the audit exam. Suggest different time of event, i.e., after the fuel failure, with vent isolation failure, this requires alertness and immediate action or release of radiation outside.

Also, malfunction similar to system relating to JPM B. 1.a, bypass reactor bldg vent isolation.

See similarity with system affected?? Suggest this malfunction as supporting malfunction after the reactor trip/fuel failure with reactor bldg vent fails to isolate (significant action to isolate),

also have challenges to SBGT.

QUAD CITIES 2002 INITIAL EXAM OUTLINE REVIEW COMMENTS Event 5, CRD pump trip similar as audit scenario, may need to change in NRC exam. Found to be different actions, in audit requires them to scram.

Event 8, fuel failure causing high rad and eventual emergency depressurization due to high rad - seems similar to audit scenario, fuel failure causing rad levels to increase, possibly replace. With changes to reactor vent isolation actions, will be significantly different. Also, audit was independently developed.

Scenario # 4 (initially noted by licensee as spare)

I like the spare scenario rather than scenario # 1, due to limited actions as written.

Written Exam Outline:

Noted that the licensee's outline incorrectly indicates in Note # 1, that to select at least one (1) topic from every K/A category within each tier. The Rev 8, Supplement 1, specifically notes "To ensure that at least two topics from every K/A category are sampled within each tier."

Discrepancy identified to licensee. Licensee used their old outline format. Outline submitted with written exam material specifically used the Supplement 1 form.

Appeared to sample multiple similar systems, which reduces the ability to select a wide and broad sampling of systems. However, appears to meet minimum requirements, and selection done randomly and systematically.

Exekn.m Exelon Generation Company, LLC Quad Cities Nuclear Power Station 22710 206" Avenue North Cordova, IL 61242-9740 www.exeloncorp.com Nuclear SVP-02-067 August 15, 2002 Regional Administrator Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Quad Cities Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Submittal of Integrated Initial License Training Examination Outline Enclosed are the examination outlines, supporting the Initial License Examination scheduled for the weeks of December 2, 2002, through December 13, 2002, at Quad Cities Station.

This submittal includes all appropriate Examination Standard forms and outlines in accordance with NUREG-1021, "Operator Licensing Examination Standards", Revision 8, Supplement 1.

In accordance with NUREG 1021, Revision 8, Supplement 1, 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 Mr. W. J. Beck, Regulatory Assurance Manager, at (309)-227-2800. For questions concerning examination outlines, please contact Ken Moreland at (309) 227-4030.

Respectfully, Quad Cities Nuclear Power Station

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ES-201 Examination Outline Examination Outline Form ES-201-2 Facility.

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L Date of Examination: 123

- It L/0 Initials Item Task Description a

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1.

a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

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b. Assess whether the outline was systematically and randomly prepared in accordance with I

Section D.1 of ES-401 and whether all KA categories are appropriately sampled.

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

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d. Assess whether the justification for deselected or rejected K/A statements are appropriate.

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2.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, and major transients.

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b. Assess whether there are enough scenario sets (and spares) to test the projected number and M

mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at least one new or Y71

%2 significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s)*,

and scenarios will not be repeated over successive days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and t&,

quantitative criteria specified on Form ES-301-4 and described in Appendix D.

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3.

a. Verify that:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks, W

(2) no more than 30% of the test material is repeated from the last NRC examination, V

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(3)* no tasks are duplicated from the applicants' audit test(s), and '

T (4) no more than 80% of any operating test is taken directly from the licensee's exam banks. v

b. Verify that:

(1) the tasks are distributed among the safety function groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the applicant to implement an alternate path procedure, (4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-plant walk-through requires the applicant to enter the RCA.

c. Verify that the required administrative topics are covered, with emphasis on performance-based activities./

d. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on successive days.

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4.

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

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

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

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d. Check for duplication and overlap among exam sections.

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e. Check the entire exam for balance of coverage.

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

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1M Pri Na/mpe / Si nature Date

a. Author

b. Facility Reviewer(*)

c. NRC Chief Examiner (#)

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d. NRC Supervisor

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NOTE:

• Not applicable for NRC-developed examinations.

1. Independent NRC Reviewer initial items in Column "c"' chief examiner concurrence required.

NUREG-1021, Revision 8, Supplement 1 MoTO:

Qualitv Checklist ES-201 23 of 24

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Quad Cities Date of Examination: 12-02-02 Examination Level (circle one): SRO Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A. 1 Ability to Verify readings for APRM Flow Biased High Flux (Heat Balance) recognize Calibration Test - QCOS 0700-06, partial for step H.4.

indications for systems which are entry-level conditions for tech specs.

2.1.33-4.0 Knowledge of Evaluate operator working hours to determine if they have shift staffing exceeded 82-12 requirements.

requirements.

2.1.4 -3.4 A.2 Knowledge of Authorize a clearance order.

tagging and clearance procedures.

2.2.13-3.8 A.3 Knowledge of Review a discharge permit.

the requirements for reviewing and approving discharge permits.

2.3.6 - 3.1 A.4 Knowledge of Determine PARS.

emergency plan protective action requirements.

2.4.44 -4.0 21 of 26 NUREG-1021, Revision 8, Supplement 1 CvfI

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Quad Cities Date of Examination: 12-02-02 Examination Level (circle one): RO Operating Test Number:

I Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Ability to perform Perform APRM Flow Biased High Flux (Heat Balance) Calibration procedures Test - QCOS 0700-06, partial for step H.4.

during all modes of plant operation.

2.1.23-3.9 Knowledge of Evaluate license maintenance requirements.

operator responsibilities during all modes of plant operation.

2.1.2-3.0 A.2 Knowledge of Generate an equipment status tag.

tagging and clearance procedures.

2.2.13-3.6 A.3 Ability to perform Determine Radiation Exposure.

procedures to guard against personnel exposure.

2.3.10-2.9 A.4 Knowledge of Activate ERDS.

emergency communications systems and techniques.

2.4.43 - 2.8 21 of 26 NUREG-1021, Revision 8, Supplement 1 coc~

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Quad Cities Date of Examination: 12-02-02 Exam Level (circle one): RO/SRO (I)

Operating Test Number: 1 B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

a. Reactor Building Ventilation / Bypass Reactor Building Ventilation D, S 9

Isolations. 286000 A4.01 3.3/3.2

b. RCIC / RCIC Manual Initiation (Hardcard) with failure of the N, A, S, L 4

manual initiation pushbutton. 290003 A4.01 3.2/3.2

c.

A.C. Electrical Distribution / Supply Bus 14-1 from Bus 24-1.

N, S 6

262001 A4.01 3.4/3.7

d. Reactor Protection System / Perform a manual scram functional M, A, S 7

test with rod drifts requiring a reactor scram. 212000 A4.01 4.6/4.6

e. Core Spray / Monthly Core Spray surveillance with failure of the D, A, S 2

minimum flow valve. 209001 A4.04 2.9/2.9

f. Containment / Vent primary Containment due to high H2 with a N, A, S 5

failure of the Torus 2" vent to open. 500000 EA1.03 3.4/3.2

g. Main Steam / Pressurize main Steam Lines.

D, S, L 3

293001 A4.01 4.2/4.0 B.2 Facility Walk-Through

a. Service Water / Align SSMP Room Cooler to Fire Header D, R, L 8

APE 295018 AA1.01 3.3/3.4

b. Control Rod Hydraulic / Depressurize the Scram Air Header D, R 1

EPE 295037 EA1.05 3.9/4.0

c. Residual Heat Removal Shutdown Cooling / Perform the Auxiliary D, L 4

Electric Room actions to start SDC. APE 295021 AA1.02 3.5/3.5

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow Power, (R)CA 22 of 26 NUREG-1021, Revision 8, Supplement 1

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Quad Cities Date of Examination: 12-02-02 Exam Level (circle one): SRO (U)

Operating Test Number: 1 B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

a.

b.

C.

d. Reactor Protection System / Perform a manual scram functional M, A, S 7

test with rod drifts requiring a reactor scram. 212000 A4.01 4.6/4.6

e.

f. Containment / Vent primary Containment due to high H2 with a N, A, S 5

failure of the Torus 2" vent to open. 500000 EA1.03 3.4/3.2

g. Main Steam / Pressurize Main Steam Lines.

D, S, L 3

293001 A4.01 4.2/4.0 B.2 Facility Walk-Through

a. Service Water/Align SSMP Room Cooler to Fire Header D, R, L 8

APE 295018 AA1.01 3.3/3.4

b.

c. Residual Heat Removal Shutdown Cooling / Perform the Auxiliary D, L 4

Electric Room actions to start SDC. APE 295021 AA1.02 3.5/3.5

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow Power, (R)CA 22 of 26 NUREG-1021, Revision 8, Supplement 1 ceI Y ý(

ES-301 Transient and Event Checklist Form ES-301-5 OPERATING TEST NO.: 1 Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Spare RO/BOP Reactivity 1

1/-

6/-

2/-

2/

Normal 1

-/4

-/1

-41

-/1 Instrument 4

3,6 2,4 3,5 3,6 Component

/2,5

/3,5

/4,6

/4,5 Major 1

7,8 7,8 7,8 7,8 Reactivity 1

1 6

2 2

Normal 0

As RO Instrument 2

3,6 2,4 3,5 3,6 Component Major 1

7,8 7,8 7,8 7,8 SRO-I Reactivity 0

Normal 1

4 1

1 1

As SRO Instrument /

2 2,3,5 2-5 3-6 3-6 Component

.6 Major 1

7,8 7,8 7,8 7,8 Reactivity 0

Normal 1

4 1

1 1

SRO-U Instrument /

2 2,3,5 2-5 3-6 3-6 Component

.6 Major 1

7,8 7,8 7,8 7,8 Instructions:

Author:

NRC Reviewer:

(1)

Enter the operating test number and Form each evolution type.

ES-D-1 event numbers for (2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3)

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

LZ~ --

NUREG-1021, Revision 8, Supplement 1 25 of 26

Apendix D 1

Form ES-D-1

• (N)ormal, (R)eactivity, (S)- SRO/US (R) - RO (B) - BOP/ANSO (I)nstrument, (C)omponent, (M)ajor FACILITY: QUAD CITIES OPERATORS:

EXAMINERS:

INITIAL CONDITIONS: - 35% power, 1 B Service Water Pump OOS, power ascension in progress.

TURNOVER: - 310 MWe. The following equipment is out of service: 1 B Service Water Pump.

Plant startup in progress lAW QCGP 1-1, step F.9.t. QNE directions are to increase power with recircs to - 4.5 MLBM/hr feedwater flow and place the 2nd FWRV in service.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A R - R, S Increase power using recirc pumps 2

SW11b C-B, S TBCCW pump trip 3

FW07 I - R, S B FWRV lockup 4

N/A N - B, S Place 2n" FWRV in service.

5 RP04b C - B, S Trip of RPS-B 6

RD04r C - R, S Rod drift out 7

TC01 M - All Turbine Trip 8

RD13 M - All Hydraulic ATWS (PSA identified event) c1 SCENARIO NO: 1 OP-TEST NO: I

Apendix D 1

Form ES-D-1

.3 Facility: Quad Cities Scenario No: 1 Op-Test No: 1 Summary:

The crew will take the shift at - 35% power. The RO will increase reactor power using Recirc pumps. (Reactivity Manipulation - RO, SRO) The A TBCCW pump will

-trip, requiring manual start of the B TBCCW pump. (Component - BOP, SRO)

During the power increase the B FWRV will lockup, requiring reset. (Instrument RO, SRO) When Feedwater flow is approximately 4.5 MLBM/hr the BOP will place the 2 nd FWRV in service. (Normal Evolution - BOP, SRO) Next a loss of "B" RPS will occur, requiring restoration of power and resetting of isolations and equipment.

(Instrument, TS - BOP, SRO) A rod will drift out of the core, requiring it to be manually inserted, scrammed and isolated. (Component, TS - RO, SRO) The turbine will trip, rods will not insert - Hydraulic ATWS, requiring entry into QGA 101.

(Major - All) The scenario is complete when the crew is controlling RPV water level lAW QGA 101 Power/Level Control leg and have worked through QCOP 0300-28 to the point of attempting individual rod insertion.

CT #1 - During an ATWS with conditions met to perform power/level control, TERMINATE AND PREVENT INJECTION, with the exception of boron, CRD and RCIC into the RPV until conditions are met to re-establish injection. (BVWROG RPV-6.3 PWR/LVL TERM/PREVENT)

CT #2 - When conditions are met to re-establish injection, use available injection systems to MAINTAIN RPV water level above the Minimum Steam Cooling RPV Water Level

(-166"). (BWROG RPV-6.4 ATWS PWR/LVL RESTORE RPV LVL)

CT #3 (Contingent on water level) - With a reactor scram required, reactor not shyltdown, and conditions for ADS blowdown are met, INHIBIT ADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion. (BWROG RPV-6.2 ATWS PWR/LVL INHIBIT ADS)

Appendix D 1

Form ES-D-1 FACILITY: QUAD CITIES EXAMINERS:

SCENARIO NO: 2 OPERATORS:

OP-TEST NO: 1 INITIAL CONDITIONS: IC-21, 100% Power, 1B Service Water Pump OOS For Motor Winding Ground.

TURNOVER: 912 MWe. The Following Equipment Is Out Of Service: lB Service Water Pump OOS For Motor Winding Ground. Currently Holding Power Constant.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A N - B, S SSMP Valve Timing (QCOS 2900-03) 2 NM08/

I - R, S APRM failure with failure of automatic 11/2 scram.

RP02 3

SWO1 C - B, S Service Water Pump Trip.

4 RD03 C-R, S Rod drift in 1 notch.

5 Ior I - B, S RHR Pump inadvertent start dihsl 10021c close 6

MC08 R - R, S Main Condenser air in leakage that requires a power reduction. (PSA identified event) 7 RR1OA M - All Recirc suction line rupture.

8 Batfwlowlow M - All Loss of all RFPs and failure of HPCI leads to RPV Blowdown HP01 at TAF and low pressure system injection. (PSA identified event)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (S)- SRO/US (R) - RO (B) - BOP/ANSO M-N ý(

Appendix D 1

Form ES-D-1 Facility: Quad Cities Scenario No: 2 Op-Test No: 1 Summary:

The crew will take the shift at 100% power and perform QCOS 2900 SSMP Valve Timing Surveillance. (Normal - BOP, SRO) An APRM will fail upscale with a failure of the automatic

/2 scram, requiring a manual / scram and bypassing of the failed APRM. (Instrument, TS - RO, SRO) A Service Water pump will trip, requiring a standby pump to be manually started. (Component - BOP, SRO) A control rod will drift in from 48 to 46, requiring it to be withdrawn back to 48. (Component - RO, SRO) An RHR pump will inadvertently start, requiring it to be manually tripped and Tech Specs to be addressed. (Instrument, TS - ANSO, SRO) Air in-leakage will develop in the Main Condenser Boot due to a rupture, requiring power reduction and a reactor scram. (Component, Reactivity - NSO, SRO) A Recirc Suction line will rupture along with a loss of all RFPs and a failure of HPCI, which will result in level reaching TAF and RPV blowdown. (Major - ALL) The scenario ends when the crew has performed an RPV Blowdown and reestablished core cooling with low pressure systems.

CT #1 - When Torus pressure exceeds 5 psig, INITIATE drywell sprays, while in the safe region of the drywell spray initiation limit (DSIL). (BWROG PC-5.1 INIT DW SPRAY)

CT #2 - With Reactor pressure greater than shutoff head of the Low pressure system(s) before RPV water level drops to -166", INITIATE emergency depressurization. (BWROG RPV-1.1 LOSS HP INJ E/D TAF)

CT #3 - Action is taken to restore RPV water level above TAF, by OPERATING available low pressure system(s) when RPV pressure decreases below the shut off head of the low pressure system(s). (BWROG RPV-1.2 LOSS HP IND RESTORE RPV LVL).

Appendix D 1

Form ES-D-1 FACILITY: QUAD CITIES EXAMINERS:

SCENARIO NO: 3 OPERATORS:

OP-TEST NO: 1 INITIAL CONDITIONS: -3% Power, Reactor Start-Up In Progress, Mode Switch In Startup/Hot Standby.

TURNOVER: Reactor Startup In Progress lAW QCGP 1-1 Step F.6. ad and ae. RWCU reject is ready to be secured and continue pulling rods for startup.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A N - B, S Secure RWCU Blowdown 2

N/A R - R, S Pull rods to increase power 3

NMO5 I - R, S IRM failure 4

RM02k/HV01 I - B, S Reactor Building Vent Rad Monitor fails upscale with failure of Rx Building vents to isolate.

5 RD07 C - R, S CRD Pump trip 6

SW06/SW07 C - All Loss of RBCCW/Trip of Recirc Pumps 7

RP05 M - All Reactor Scram with inadvertent Group 1.

8 RD14/CR01 M -All SDV Volume Rupture/Fuel Failure/QGA 300 RPV Blowdown

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (S)- SRO/US (R) - RO (B) - BOP/ANSO 64Y ý(

Appendix D 1

Form ES-D-1 clit: Quad Cities Scenario No: 3 Op-Test No: 1 Summary:

The crew will take the shift with the plant at - 3% power and secure RWCU reject blowdown. (Normal - BOP, SRO) The RO will then pull rods to increase power.

(Reactivity - RO, SRO) An IRM will fail while the NSO is pulling rods, requiring it to be bypassed. (Instrument, TS - RO, SRO) A Rx Building Vent Rad Monitor will fail upscale with a failure of the RB Vents to isolate, requiring them to be manually isolated. (Instrument, TS - BOP, SRO) A CRD pump will trip, requiring the standby CRD pump to be started. (Component - RO, SRO) A total loss of RBCCW will occur, requiring the Recirc pumps to be tripped (Component - All) and a Rx scram to be inserted. When the scram is inserted, an inadvertent Group 1 isolation will occur. (Major - All) A fuel failure and Scram Discharge Volume rupture that cannot be isolated will occur on the Rx Scram that leads to an RPV Blowdown on 2 areas above max safe rads. (Major - All) The scenario will be complete when the crew has completed the RPV blowdown.

CT #1 - The crew will recognize a failure of the Reactor Building Vents to isolate and manually isolate them using the control switch on the 912-1 Pnl.

CT #2 - The crew will recognize a trip of both recirc pumps and insert a manual reactor scram.

CT #3 - With a primary system discharging into the secondary containment and area radiation/temperature/water levels exceed maximum safe levels in more than one area of the same parameter, INITIATE an emergency depressurization. (BWROG SC-1.2 LOCA SC E/D)

Appendix D 1

Form ES-D-1 Facility: Quad Cities Examiners:

Scenario No: 4 Operators:

Op-Test No: 1 Initial Conditions: - 700 MWe, 75% power, 1A RHR Loop OOS, B SBGT running for monthly surveillance.

Turnover: The following equipment is out of service: 1A RHR loop. B SBGT was running for the monthly surveillance per QCOS 7500-05 and is ready to be shutdown per step H.2.p.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A N - B, S Shutdown SBGT 2

RR01 R - R, S Insert Control Rods to exit the instability region due to recirc drive motor breaker trip.

3 RD02 C-R, S Stuck control rod.

4 EG05 C - B, S Stator Cooling Pump Trip with failure of the Standby to auto start.

5 AD01 I - B, S ADS valve fails open due to setpoint drift - Rx scram 6

RP02/RP03 I - R, S Control rods fail to insert on manual scram - initiate ARI.

(PSA identified event) 7 MS05/RP05 M - All Steamline break in Drywell with a Group I.

8 Ior M - All Failure of Drywell Sprays and Cooling leads to RPV zdish11001S blowdown and flooding. (PSA identified event) 17(B)1 Bat DWCLRTRIP

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (S)- SRO/US (R) - RO (B) - BOP/ANSO M

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Appendix D 1

Form ES-D-1 Facility: Quad Cities Scenario No: 4 Op-Test No: 1 Summary:

The crew will take the shift with SBGT running. The surveillance is complete and needs to be shutdown. (Normal - BOP, SRO) After this, a Recirc Pump drive motor breaker will trip, requiring the RO to insert cram rods. (Reactivity manipulation, TS RO, SRO) While inserting cram rods, one of the rods will stick, requiring drive water pressure to be raised in order to drive it. (Component - RO, SRO) When they have inserted cram rods/exited the instability region, the running Stator Water Cooling Pump will trip and the standby will fail to auto start, requiring it to be manually started. (Component - BOP, SRO). An ADS valve will fail open and will not close when attempted manually, (Instrument, TS - BOP, SRO) requiring a manual scram to be inserted. When the manual scram pushbuttons are depressed, no rod movement will occur, requiring initiation of ARI to insert the rods. (Instrument - RO, SRO) After the rods are inserted, a steamline break will occur in the Drywell with an inadvertent Group 1 isolation. Coupled with a failure of Drywell Sprays and Cooling, this will lead to an RPV Blowdown and RPV Flooding. (Major - All) The scenario will be completed when the crew has identified the requirements to determine the Main Steam Lines are flooded.

CT #1 - Crew will recognize instabilities region has been entered and insert control rods to exit instabilities.

CT #2 - When Torus Pressure cannot be maintained below PSP curve and/or drywell temperature cannot be restored or held below 2800F, INITIATE emergency depressurization. below 2800F, INITIATE emergency depressurization.

CT #3 - When RPV level cannot be determined, INJECT into the RPV to maintain RPV flooded to the Main Steam Lines. (BWROG RPV-2.2 LOSS LVL INST MRPVFP)

ES-401 Facility:

Quad Cities BWR SRO Examination Outline Exam Date: 12/02/2002 Printed: 08/15/2002 Form ES-401-1 Exam Level:

SRO K/A Category Points Tier Group KI K2 K3 K4 K5 K6

1.

1 4

4 5

Emergency 2

3 3

3 Abnormal Plant Tier Evolutions Totals 7

7

2.

Plant Systems 1

3 2

2 2

2 2

Al 4

1 5

2 A2 5

4 9

2 A3 A4 2

G 4

3 7

3 Point Total 26 17 43 23 2

1 1

1 1

2 1

1 1

1 1

2 13 3

1 0

0 1

0 0

1 0

0 0

1 4

Tier Totals 5

3 4

4 4

3 3

2 6

40 Cat I Cat 2 Cat 3 Cat 4

3. Generic Knowledge And Abilities 4

4 4

5 17 Note:

1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.

2. Actual point totals must match those specified in the table.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category tier.

C9)(3/4L-ý I

L i

I

BWR SRO (

rmination Outline E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295003 Partial or Complete Loss of A.C. Power / 6 X 2.1.14 - Knowledge of system status criteria which 3.3 1

require the notification of plant personnel.

295003 Partial or Complete Loss of A.C. Power / 6 X

AK1.05 - Failsafe component design 2.7 1

295006 SCRAM / 1 X

AA2.05 - Whether a reactor SCRAM has occurred 4.6*

1 295007 High Reactor Pressure / 3 X

AAI.04 - Safety/relief valve operation: Plant-Specific 4.1

• 1 295009 Low Reactor Water Level / 2 X

AA2.03 - Reactor water cleanup blowdown rate 2.9 1

295009 Low Reactor Water Level / 2 X

AK2.03 - Recirculation system 3.2 1

295010 High Drywell Pressure / 5 X

AKI.03 - Temperature increases 3.4 1

295010 High Drywell Pressure / 5 X

AK3.05 - Temperature monitoring 3.4 1

295013 High Suppression Pool Temperature / 5 X

AKI1.01 - Pool stratification 2.6 1

295013 High Suppression Pool Temperature / 5 X 2.4.4 - Ability to recognize abnormal indications for 4.3 1

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

295015 Incomplete SCRAM / I X

AK2.01 - CRD hydraulics 3.9 1

295015 Incomplete SCRAM / 1 X 2.2.22 - Knowledge of limiting conditions for 4.1 1

operations and safety limits.

V C7.1 V A1 1 295016 Control Room Abandonment / 7 X

AK2.02 - Local control stations: Plant-Specific 4.1

• 1 Printed:

08/15/(

'u(a,Jties Facility:

ES - 401 I

BWR SRO (

mination Outline Emergencv and Abnormal Plant Evolutions - Tier 1 / Group 1 Printed:

0 8/ 15/( c Form ES-401-1 E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295023 Refueling Accidents / 8 X

AK1.03 - Inadvertent criticality 4.0 1

295023 Refueling Accidents / 8 X

AA2.02 - Fuel pool level 3.7 1

295024 High Drywell Pressure / 5 X

EK3.02 - Suppression pool spray operation:

3.8 1

Plant-Specific 295025 High Reactor Pressure / 3 X

EA1.04 - HPCI: Plant-Specific 3.9 1

295026 Suppression Pool High Water Temperature / 5 X

EK2.04 - SPDS/ERIS/CRIDS/GDS: Plant-Specific 2.8 1

295026 Suppression Pool High Water Temperature / 5 X

EK3.01 - Emergency/normal depressurization 4.1 1

295030 Low Suppression Pool Water Level / 5 X 2.1.33 - Ability to recognize indications for system 4.0 1

operating parameters which are entry-level conditions for technical specifications.

295030 Low Suppression Pool Water Level / 5 X

EA2.04 - Drywell/ suppression chamber differential 3.7 1

pressure: Mark-l&II 295031 Reactor Low Water Level / 2 X

EK3.04 - Steam cooling 4.3*

1 295037 SCRAM Condition Present and Reactor Power X

EA 1.11 - PCIS/NSSSS 3.6 1

Above APRM Downscale or Unknown / 1 295038 High Off-Site Release Rate / 9 X

EA2.01 - fOff-site 4.3*

1 295038 High Off-Site Release Rate / 9 X

EAI.03 - Process liquid radiation monitoring system 3.9 1

500000 High Containment Hydrogen Concentration / 5 X

EK3.06 - Operation of wet well vent 3.7 1

2 Qua,.ities Facility:

ES - 401

(

Facility:

Qua.. Jties ES - 401 E/APE #

BWR SRO(

imination Outline Emergency and Abnormal Plant Evolutions - Tier I / Group 1 Printed:

08/15/(

T

,-1I-T-T-r-r r

E/APE Name / Safety Function K/A Category Totals:

KI 4

K2 4

K3 5

Al 4

A2 5

G KA Topic Group Poini Form ES-401-1 Imp.

Total:

Points 26 3

Quau C2ities Printed:

08/15/'

Form ES-401-1 E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295001 Partial or Complete Loss of Forced Core Flow X

AK2.03 - Reactor water level 3.7 1

Circulation / I 295002 Loss of Main Condenser Vacuum / 3 X

AA 1.07 - Condenser circulating water system 2.9 1

295004 Partial or Complete Loss of D.C. Power / 6 X 2.2.22 - Knowledge of limiting conditions for 4.1 1

operations and safety limits.

295004 Partial or Complete Loss of D.C. Power / 6 X

AK3.01 - tLoad shedding: Plant-Specific 3.1 1

295005 Main Turbine Generator Trip / 3 X

AK3.05 - Extraction steam/moisture separator isolations 2.6 295012 High Drywell Temperature / 5 X

AA2.02 - Drywell pressure 4.1 1

295012 High Drywell Temperature / 5 X

AK3.01 - Increased drywell cooling 3.6 1

295020 Inadvertent Containment Isolation / 5 X

AK2.12 - Instrument air/nitrogen: Plant-Specific 3.2 1

295021 Loss of Shutdown Cooling / 4 X 2.2.25 - Knowledge of bases in technical specifications 3.7 1

for limiting conditions for operations and safety limits.

295021 Loss of Shutdown Cooling / 4 X

AK 1.04 - Natural circulation 3.7 295022 Loss of CRD Pumps / I X

AKI.01 - Reactor pressure vs. rod insertion capability 3.4 1

295028 High Drywell Temperature / 5 X

EA2.05 - Torus/suppression chamber pressure:

3.8 1

Plant-Specific 295028 High Drywell Temperature / 5 X

EK1.02 - Equipment environmental qualification

3.1 Facility

ES - 401 BWR SRO(

,mination Outline Emergency and Abnormal Plant Evolutions - Tier I / Group 2 I

BWR SRO(

imination Outline Emergency and Abnormal Plant Evolutions - Tier I / Group 2 K/A Category Totals:

3 3

3 1

4 3

Printed:

08/15I Form ES-401-1 Group Point Total:

17 2

Q(a, ;ities Facility:

ES - 401 E/APE #

E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.

Points 295029 High Suppression Pool Water Level / 5 X

EA2.03 - Drywell/containment water level 3.5 1

295032 High Secondary Containment Area Temperature / 5 X

EK2.02 - Secondary containment ventilation 3.7 1

295034 Secondary Containment Ventilation High Radiation /

X EA2.02 - Cause of high radiation levels 4.2*

1 9

600000 Plant Fire On Site / 8 X 2.2.25 - Knowledge of bases in technical specifications 3.7 1

for limiting conditions for operations and safety limits.

(

Printed:

08/19

'12 BWR SRO E(

iination Outline Plant Systems - Tier 2 / Group I Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 203000 RHR/LPCI: Injection Mode (Plant X

K2.01 - Pumps 3.5*

1 Specific) / 2 206000 High Pressure Coolant Injection X

K2.04 - Turbine control circuits: BWR-2, 3, 4 2.7*

1 System / 2 209001 Low Pressure Core Spray System / 2 X

A2.04 - D.C. failures 3.0 1

212000 Reactor Protection System / 7 X

K5.02 - Specific logic arrangements 3.4 1

215004 Source Range Monitor (SRM) System X

K4.02 - Reactor SCRAM signals 3.5 1

/7 215004 Source Range Monitor (SRM) System X

K5.01 - Detector operation 2.6 1

/7 215005 Average Power Range Monitor/Local X

A3.06 - Maximum disagreement between flow 3.1 1

Power Range Monitor System / 7 comparator channels: Plant-Specific 216000 Nuclear Boiler Instrumentation / 7 X

K6.02 - D.C. electrical distribution 3.0 1

216000 Nuclear Boiler Instrumentation / 7 X

A2.10 - Rapid vessel depressurizations 3.5 1

217000 Reactor Core Isolation Cooling X

K3.01 - Reactor water level 3.7 1

System (RCIC) / 2 223001 Primary Containment System and Auxiliaries / 5 X 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

4.0 1

Form ES-401-1 Facility:

ES - 401 Quad Cities I

(

Quad Cities Printed:

08/11 92 BWR SRO E(

iination Outline Plant Systems - Tier 2 / GrouD 1 Sys/Ev #

System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 223001 Primary Containment System and X

Kl.09 - SBGT/FRVS: Plant-Specific 3.6 1

Auxiliaries / 5 223002 Primary Containment Isolation X 2.2.22 - Knowledge of limiting conditions for 4.1 1

System/Nuclear Steam Supply operations and safety limits.

Shut-Off / 5 239002 Relief/Safety Valves / 3 X

K3.02 - Reactor over pressurization 4.4*

1 239002 Relief/Safety Valves / 3 X

A 1.03 - Air supply: Plant-Specific 2.9 1

259002 Reactor Water Level Control System /

X K1.15 - Recirculation flow control system 3.2 1

2 261000 Standby Gas Treatment System / 9 X

A 1.01 - System flow 3.1 1

262001 A.C. Electrical Distribution / 6 X 2.1.33 - Ability to recognize indications for 4.0 1

system operating parameters which are entry-level conditions for technical specifications.

262001 A.C. Electrical Distribution / 6 X

K1.04 - Uninterruptible power supply 3.4 1

264000 Emergency Generators (Diesel/Jet) / 6 X

K4.06 - Governor control 2.7 1

264000 Emergency Generators (Diesel/Jet) / 6 X

A4.02 - Synchroscope 3.4 1

290001 Secondary Containment / 5 X

K6.04 - Primary containment system Form ES-401-1 Facility:

ES - 401 4.1 2

I Q

(

Facility:

Quad Cities ES - 401 BWR SRO E(

iination Outline Plant Systems - Tier 2 / Groun 1 Printed:

08/1' 92 Form ES-401-1 K/A Category Totals:

3 2

2 2

2 2

2 2

2 1

3 Group Point Total:

23 3

Sys/Ev #

System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 GjI KATopic Imp.

Points 290001 Secondary Containment / 5 X

A3.02 - Normal building differential pressure:

3.5 1

Plant-Specific

(

Printed:

08/1(

92 BWR SRO E(

iination Outline Plant Systems - Tier 2 / Group 2 Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 201006 Rod Worth Minimizer System X

A 1.03 - Latched group indication:

3.0 1

(RWM) (Plant Specific) / 7 P-Spec(Not-BWR6) 201006 Rod Worth Minimizer System X

A3.02 - Verification of proper functioning/

3.4 1

(RWM) (Plant Specific) / 7 operability: P-Spec(Not-BWR6) 202001 Recirculation System / 1 X

K2.02 - MG sets: Plant-Specific 3.3 1

214000 Rod Position Information System / 7 X

K3.01 - RWM: Plant-Specific 3.2 I

214000 Rod Position Information System / 7 X

A4.02 - Control rod position 3.8*

1 215002 Rod Block Monitor System / 7 X

K6.05 - LPRM detectors: BWR-3, 4, 5 3.1 1

230000 RHR/LPCI: Torus/Suppression Pool X

K5.06 - Heat exchanger operation 2.6 1

Spray Mode / 5 245000 Main Turbine Generator and X 2.1.33 - Ability to recognize indications for 4.0 1

Auxiliary Systems / 4 system operating parameters which are entry-level conditions for technical specifications.

286000 Fire Protection System / 8 X

K5.02 - Effect of Halon on fires: Plant-Specific 2.6 290003 Control Room HVAC / 9 X 2.4.30 - Knowledge of which events related to 3.6 system operations/status should be reported to outside agencies.

290003 Control Room HVAC / 9 X

KI.05 - Component cooling water systems 3.0 Form ES-401-1 Facility:

ES - 401 Quad Cities I

Facility:

Quad Cities ES - 401 BWR SRO E(

iination Outline Plant Systems - Tier 2 / Group 2 Printed:

08/ (

02 Form ES-401-1 K/A Category Totals:

1 1

1 1

2 1

1 1

1 1

2 Group Point Total:

Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 300000 Instrument Air System (IAS) / 8 X

K4.03 - Securing of IAS upon loss of cooling 2.8 1

water 300000 Instrument Air System (IAS) / 8 X

A2.01 - Air dryer and filter malfunctions 2.8 1

13 2

(

Quad Cities Printed:

08/1'7 "92 BWR SRO E tination Outline Plant Systems - Tier 2 / Group 3 K/A Category Totals:

1 0

0 1

0 0

1 0

0 0

1 Form ES-401-1 Facility:

ES - 401 Sys/Ev #

System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 201003 Control Rod and Drive Mechanism / I X

A 1.01 - Reactor power 3.8 1

215001 Traversing In-Core Probe / 7 X 2.4.6 - Knowledge symptom based EOP 4.0 1

mitigation strategies.

215001 Traversing In-Core Probe / 7 X

K4.01 - Primary containment isolation:

3.5 1

Mark-I&II(Not-BWRl) 288000 Plant Ventilation Systems / 9 X

K1,06 - Plant air systems 2.7 1

Group Point Total:

4 I

Generic Knowledge and Abilities Outline (Tier 3)

(

BWR SRO Examination Outline Printed: 08/15/204 Form ES-401-5 Imp.

Points KA KA Topic Conduct of Operations 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, 3.1 1

and tables which contain performance data.

2.1.22 Ability to determine Mode of Operation.

3.3 1

2.1.17 Ability to make accurate, clear and concise verbal reports.

3.6 1

2.1.27 Knowledge of system purpose and/or function.

2.9 1

Category Total:

4 Equipment Control 2.2.11 Knowledge of the process for controlling temporary changes.

3.4*

1 2.2.27 Knowledge of the refueling process.

3.5 1

2.2.1 Ability to perform pre-startup procedures for the facility, including operating those 3.6 1

controls associated with plant equipment that could affect reactivity.

2.2.3 (multi-unit) Knowledge of the design, procedural, and operational differences between 3.3 1

units.

Category Total:

4 Radiation Control 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.

3.0 1

2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 1

personnel exposure.

2.3.11 Ability to control radiation releases.

3.2 1

2.3.9 Knowledge of the process for performing a containment purge.

3.4 1

Category Total:

Facility:

Quad Cities Generic Category 4

Q I

Generic Knowledge and Abilities Outline (Tier 3)

BWR SRO Examination Outline Printed:

08/15/2002(

Form ES-401-5 Imp.

Points KA KA Topic Emergency Plan 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency 3.6 1

operations including system geography and system implications.

2.4.32 Knowledge of operator response to loss of all annunciators.

3.5 1

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

3.4 1

2.4.25 Knowledge of fire protection procedures.

3.4 1

2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire 3.3 1

fighting equipment usage.

Category Total:

5 Generic Total:

17 2

(

Facility:

Quad Cities Generic Category

ES-401 Facility:

Quad Cities BWR RO Examination Outline Exam Date: 12/02/2002 Printed: 08/15/2002 Form ES-401-2 Exam Level: RO Tier P-I Point Group K/A Category Points KI K2 T

K3 K4 K5 K6 Al 1

1 2

5

1.

Emergency 2

4 4

3 Abnormal Plant 3

2 1

0 Evolutions Totals 7

7 8

Tier

2.

Plant Systems 1

2 2

2 3

3 3

3 1

7 2

A2 1

4 0

5 3

SA3 I A4 2

3 G

1 0

2 3

Point Total 13 19 4

36 28 2

2 2

2 2

2 2

2 1

2 2

0 19 3

1 0

1 1

0 0

0 1

0 0

0 4

1 1111 Tier Totals 5

4 6

5 5

5 4

5 4

5 51 Cat I Cat 2 Cat 3 Cat 4

3. Generic Knowledge And Abilities 3

3 3

4 13 Note:

1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.

2. Actual point totals must match those specified in the table.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category tier.

I

BWR RO ý mination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE ft E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295005 Main Turbine Generator Trip / 3 X

AK3.05 - Extraction steam/moisture separator isolations 2.5 1

295006 SCRAM / I X

AA2.05 - Whether a reactor SCRAM has occurred 4.6*

1 295007 High Reactor Pressure / 3 X

AA1.04 - Safety/relief valve operation: Plant-Specific 3.9 1

295009 Low Reactor Water Level / 2 X

AK2.03 - Recirculation system 3.1 1

295010 High Drywell Pressure / 5 X

AK1.03 - Temperature increases 3.2 1

295010 High Drywell Pressure / 5 X

AK3.05 - Temperature monitoring 3.5 1

295015 Incomplete SCRAM /I X

AK2.01 - CRD hydraulics 3.8 1

295015 Incomplete SCRAM / I X 2.2.22 - Knowledge of limiting conditions for 3.4 1

operations and safety limits.

295024 High Drywell Pressure / 5 X

EK3.02 - Suppression pool spray operation:

3.5 1

Plant-Specific 295025 High Reactor Pressure / 3 X

EA1.04 - HPCI: Plant-Specific 3.8 1

295031 Reactor Low Water Level / 2 X

EK3.04 - Steam cooling 4.0 1

295037 SCRAM Condition Present and Reactor Power X

EAI.11 - PCIS/NSSSS 3.5 1

Above APRM Downscale or Unknown / 1 500000 High Containment Hydrogen Concentration / 5 X

EK3.06 - Operation of wet well vent 3.1 1

K/A Category Totals:

1 2

5 3

1 1

Group Point Total:

Facility:

ES - 401 Qu

ities 0

13 1

Printed:

08/15* (

BWR RO ('

mination Outline Emergency and Abnormal Plant Evolutions - Tier I / Group 2 Form ES-401-2 E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295001 Partial or Complete Loss of Forced Core Flow X

AK2.03 - Reactor water level 3.6 1

Circulation / I 295002 Loss of Main Condenser Vacuum / 3 X

AA 1.07 - Condenser circulating water system 3.1 1

295003 Partial or Complete Loss of A.C. Power / 6 X

AKl.05 - Failsafe component design 2.6 1

295004 Partial or Complete Loss of D.C. Power / 6 X

AA2.02 - Extent of partial or complete loss of D.C.

3.5 1

power 295004 Partial or Complete Loss of D.C. Power / 6 X

AK3.01 - tLoad shedding: Plant-Specific 2.6 1

295008 High Reactor Water Level / 2 X

AA1.05 - RCIC: Plant-Specific 3.3 1

295012 High Drywell Temperature / 5 X

AK3.01 - Increased drywell cooling 3.5 1

295013 High Suppression Pool Temperature / 5 X

AKL.01 - Pool stratification 2.5 1

295013 High Suppression Pool Temperature / 5 X 2.4.4 - Ability to recognize abnormal indications for 4.0 1

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

295016 Control Room Abandonment / 7 X

AK2.02 - Local control stations: Plant-Specific 4.0*

1 295016 Control Room Abandonment / 7 X

AA2.02 - Reactor water level 4.2*

1 295020 Inadvertent Containment Isolation / 5 X

AK2.12 - Instrument air/nitrogen: Plant-Specific 3.1 1

295022 Loss of CRD Pumps / 1 X

AKI1.01 - Reactor pressure vs. rod insertion capability 3.3 1

I Facility:

ES - 401 QS(

_ities Printed:

08/15/7

BWR RO (

mination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 Group Point Total:

19 2

Facility:

ES - 401 QSIi Jities E/APE #

E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.

Points 295026 Suppression Pool High Water Temperature / 5 X

EK2.04 - SPDS/ERIS/CRIDS/GDS: Plant-Specific 2.5 1

295026 Suppression Pool High Water Temperature / 5 X

EK3.01 - Emergency/normal depressurization 3.8 1

295028 High Drywell Temperature / 5 X

EK1.02 - Equipment environmental qualification 2.9 1

295034 Secondary Containment Ventilation High Radiation /

X EA2.02 - Cause of high radiation levels 3.7 1

9 295038 High Off-Site Release Rate / 9 X

EA1.03 - Process liquid radiation monitoring system 3.7 1

600000 Plant Fire On Site / 8 X

AA2.10 - Time limit of long-term-breathing air system 2.9 1

for control room K/A Category Totals:

4 4

3 3

4 1

Printed:

08/15/(

BWR RO (

mination Outline Facility:

Q

.S ities ES - 401 Form ES-401-2 K/A Category Totals:

2 1

0 1

0 0

Group Point Total:

Emergency and Abnormal Plant Evolutions - Tier I / Group 3 E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295021 Loss of Shutdown Cooling / 4 X

AK1.04 - Natural circulation 3.6 1

295023 Refueling Accidents / 8 X

AKI.03 - Inadvertent criticality 3.7 1

295032 High Secondary Containment Area Temperature / 5 X

EK2.02 - Secondary containment ventilation 3.6 1

295035 Secondary Containment High Differential Pressure /

X EA1.02 - SBGT/FRVS 3.8 1

5 4

-z Printed:

08/15/A 1

I

C Printed:

08/1(

'92 BWR RO Et ination Outline Plant Systems - Tier 2 / Group 1 Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 203000 RHR/LPCI: Injection Mode (Plant X

K2.01 - Pumps 3.5*

1 Specific) / 2 203000 RHR/LPCI: Injection Mode (Plant X

K3.03 - Automatic depressurization logic 4.2*

1 Specific) / 2 206000 High Pressure Coolant Injection X

K2.04 - Turbine control circuits: BWR-2, 3, 4 2.5*

1 System / 2 206000 High Pressure Coolant Injection X 2.1.32 - Ability to explain and apply system 3.4 1

System / 2 limits and precautions.

209001 Low Pressure Core Spray System / 2 X

A2.04 - D.C. failures 2.9 1

209001 Low Pressure Core Spray System / 2 X

A4.05 - Manual initiation controls 3.8 1

211000 Standby Liquid Control System / 1 X

K6.03 - A.C. power 3.2 1

211000 Standby Liquid Control System / I X

A2.08 - Failure to SCRAM 4.1*

1 212000 Reactor Protection System / 7 X

K5.02 - Specific logic arrangements 3.3 1

215003 Intermediate Range Monitor (IRM)

X K6.05 - Trip units 3.1 1

System / 7 215003 Intermediate Range Monitor (IRM)

X 2.1.32 - Ability to explain and apply system 3.4 1

System / 7 limits and precautions.

215004 Source Range Monitor (SRM) System

/7 X

K4.02 - Reactor SCRAM signals Form ES-401-2 Facility:

ES - 401 Quad Cities 3.4 I

(

Quad Cities Printed:

08/1(

02 BWR RO ET- -ination Outline Plant Systems - Tier 2 / Group I Sys/Ev#

System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 215004 Source Range Monitor (SRM) System X

K5.01 - Detector operation 2.6 1

/7 215005 Average Power Range Monitor/Local X

A3.06 - Maximum disagreement between flow 3.0 1

Power Range Monitor System / 7 comparator channels: Plant-Specific 216000 Nuclear Boiler Instrumentation / 7 X

K6.02 - D.C. electrical distribution 2.8 216000 Nuclear Boiler Instrumentation / 7 X

A2.10 - Rapid vessel depressurizations 3.3 1

217000 Reactor Core Isolation Cooling X

K3.01 - Reactor water level 3.7 System (RCIC) / 2 217000 Reactor Core Isolation Cooling X 2.1.32 - Ability to explain and apply system 3.4 1

System (RCIC) / 2 limits and precautions.

218000 Automatic Depressurization System /

X K5.01 - ADS logic operation 3.8 3

218000 Automatic Depressurization System /

X A3.01 - ADS valve operation 4.2*

1 3

223001 Primary Containment System and X

K1.09 - SBGT/FRVS: Plant-Specific 3.4 1

Auxiliaries / 5 223002 Primary Containment Isolation X

A4.04 - System indicating lights and alarms 3.5 System/Nuclear Steam Supply Shut-Off/ 5 239002 Relief/Safety Valves / 3 X

K3.02 - Reactor over pressurization Form ES-401-2 Facility:

ES - 401 4.2*

1 2

BWR RO Et "ination Outline Plant Systems - Tier 2 / Group 1 Printed:

08/1(

02 Form ES-401-2 K/A Category Totals:

2 2

3 2

3 323233 Group Point Total:

(

Quad Cities Facility:

ES - 401 Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 239002 Relief/Safety Valves / 3 X

A1.03 - Air supply: Plant-Specific 2.8 1

259002 Reactor Water Level Control System /

X K1.15 - Recirculation flow control system 3.2 1

2 261000 Standby Gas Treatment System / 9 X

A 1.01 - System flow 2.9 1

264000 Emergency Generators (Diesel/Jet) / 6 X

K4.06 - Governor control 2.6 1

264000 Emergency Generators (Diesel/Jet) / 6 X

A4.02 - Synchroscope 3.4 1

28 3

Quad Cities Printed:

08/1(

92 BWR RO Ei "ination Outline Plant Systems - Tier 2 / Group 2 Sys/Ev#

System/ Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 201003 Control Rod and Drive Mechanism / I X

A1.01 - Reactor power 3.7 1

201006 Rod Worth Minimizer System X

A1.03 - Latched group indication:

2.9 1

(RWM) (Plant Specific) / 7 P-Spec(Not-BWR6) 201006 Rod Worth Minimizer System X

A3.02 - Verification of proper functioning/

3.5 1

(RWM) (Plant Specific) / 7 operability: P-Spec(Not-BWR6) 202001 Recirculation System / I X

K2.02 - MG sets: Plant-Specific 3.2 1

214000 Rod Position Information System / 7 X

K3.01 - RWM: Plant-Specific 3.0 1

214000 Rod Position Information System / 7 X

A4.02 - Control rod position 3.8*

1 215002 Rod Block Monitor System / 7 X

K6.05 - LPRM detectors: BWR-3, 4, 5 2.8 1

226001 RHR/LPCI: Containment Spray X

K3.02 - Containment/drywell/suppression 3.5 1

System Mode / 5 chamber temperature 230000 RHR/LPCI: Torus/Suppression Pool X

K5.06 - Heat exchanger operation 2.5*

1 Spray Mode / 5 262001 A.C. Electrical Distribution / 6 X

K 1.04 - Uninterruptible power supply 3.1 1

262001 A.C. Electrical Distribution / 6 X

K2.01 - Off-site sources of power 3.3 1

263000 D.C. Electrical Distribution / 6 X

A4.02 - Battery voltage indicator:

3.2 1

Plant-Specific I

I Form ES-401-2 Facility:

ES - 401 I

C Printed:

0 8/1('- '92 BWR RO ET "ination Outline Plant Svstems - Tier 2 / Groun 2 K/A Category Totals:

2 2

2 2

2 2

2 1

2 2

0 Group Point Total:

Form ES-401-2 Facility:

ES - 401 Quad Cities Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 272000 Radiation Monitoring System / 7 X

K4.01 - Redundancy 2.7 1

286000 Fire Protection System / 8 X

K5.02 - Effect of Halon on fires: Plant-Specific 2.6 1

290001 Secondary Containment / 5 X

K6.04 - Primary containment system 3.9 1

290001 Secondary Containment / 5 X

A3.02 - Normal building differential pressure:

3.5 1

Plant-Specific 290003 Control Room HVAC / 9 X

K1.05 - Component cooling water systems 2.8 1

300000 Instrument Air System (lAS) / 8 X

K4.03 - Securing of IAS upon loss of cooling 2.8 1

water 300000 Instrument Air System (lAS) / 8 X

A2.01 - Air dryer and filter malfunctions 2.9 1

19 2

BWR RO Er- "ination Outline Plant Systems - Tier 2 / Group 3 Printed:

08/1(

92 Form ES-401-2 Group Point Total:

4 Facility:

ES - 401 Quad Cities Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 215001 Traversing In-Core Probe / 7 X

K4.01 - Primary containment isolation:

3.4 1

Mark-I&II(Not-BWR1) 234000 Fuel Handling Equipment / 8 x

K3.03 - "Fuel handling operations 3.1 1

288000 Plant Ventilation Systems / 9 X

K1.06 - Plant air systems 2.7 1

288000 Plant Ventilation Systems /9 X

A2.04 - High radiation: Plant-Specific 3.7 K/A Category Totals:

1 0

1 1

0 0

0 1

0 0

0 S!

I

Generic Knowledge and Abilities Outline (Tier 3)

BWR RO Examination Outline Printed: 08/15/200(

Form ES-401-5 Imp.

Points KA KA Topic Conduct of Operations 2.1.17 Ability to make accurate, clear and concise verbal reports.

3.5 1I 2.1.27 Knowledge of system purpose and/or function.

2.8 1

2.1.28 Knowledge of the purpose and function of major system components and controls.

3.2 1

1 Category Total:

3 Equipment Control 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those 3.7 1

controls associated with plant equipment that could affect reactivity.

2.2.3 (multi-unit) Knowledge of the design, procedural, and operational differences between 3.1 1

units.

2.2.34 Knowledge of the process for determining the internal and external effects on core 2.8 1

reactivity.

Category Total:

3 Radiation Control 2.3.11 Ability to control radiation releases.

2.7 1

2.3.9 Knowledge of the process for performing a containment purge.

2.5 1

2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible 2.5 1

levels in excess of those authorized.

Category Total:

3 Emergency Plan 2.4.32 Knowledge of operator response to loss of all annunciators.

3.3 1

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

3.3 1

2.4.25 Knowledge of fire protection procedures.

2.9 1

2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire 2.9 1

fighting equipment usage.

I Category Total:

Generic Total:

4 13 Facility:

Quad Cities Generic Category I

(

(

ES-401 Record of Rejected K/As Form ES-401-10 Tier / Group Randomly Selected K/A Reason for Rejection SRO 1 / 1 500000 2.1.33 Not applicable at Quad Cities. Randomly replaced by 295023 A2.02 BOTH 1 / 2 295033 EA1.06 Performed by Radiation Protection at Quad Cities. Randomly replaced by 295034 A2.02 RO 2 / 3 233000 K2.02 Double Jeopardy with 203000 K2.01. Randomly replaced by 234000 K3.03 I

I

+

f

+

i f

+/-

+

+

.4

-4 I

-1

.4

-4 1

1

-4

.4

,f-.)

NUREG-1021, Revision 8, Supplement 1

( N I