Text

Miscellaneous Correspondence for the Clinton Initial Examination - July / August 2002
	ML023360476
Person / Time
Site:	Clinton
Issue date:	07/29/2002
From:	David Pelton; NRC/RGN-III/DRS/OLB
To:	;
References
	50-461/02-301
	Download: ML023360476 (53)
	v • d • e

MISCELLANEOUS CORRESPONDENCE FOR THE CLINTON INITIAL EXAMINATION - JULY/AUG 2002

AmerGen A PECO Energy/British Energy Company Clinton Power Station P.O. Box 678 Clinton, IL 61727

-Phone: 217 935-8881 U-603368 LA. 120 July 14, 2000 Mr. James E. Dyer Regional Administrator Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60632-4351

Subject:

Request for Operator License Examination Date

Dear Mr. Dyer:

AmerGen Energy Company, LLC (AmerGen) is scheduling an initial licensed operator class to begin in the July 2001 time frame. We are requesting to reserve a license examination date for this class on or around the weeks of August 01, 2002, through August 21, 2002. Class size will be approximately 16 people. AmerGen will be in communication with your staff on additional details concerning this request such as class composition and exam development. We would appreciate a response to this request as soon as possible as it directly impacts class scheduling. For questions concerning this letter, please contact David J. Russell at (217) 935-8881, extension 3815.

Sincerely yours, Vincent J. Cwietniewicz Manager-Nuclear Training JRF/blf cc:

NRC Clinton Licensing Project Manager David E. Hills, Reactor Projects Branch, USNRC D. R. McNeil, Reactor Projects Branch, USNRC NRC Resident Office, V-690 Illinois Department of Nuclear Safety (w/o attachments)

AmerGen A PECO Energyftttlh EnBWg COmPany Clinton Power Station P.O. Box 678 Clinton, IL. 61727 Phone: 217 935-8881 U-603423 1A.120 October 5. 2000 Docket No. 50-461 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Clinton Power Station Response to NRC Regulatory Issues Summary 2000-14

Dear Madam or Sir:

The purpose of this letter is to provide the AmerGen Energy Company, LLC (AmerGen) voluntary response to NRC Regulatory Issue Summary (RIS) 2000-14, "Preparation and Scheduling of Operator Licensing Examinations," for the Clinton Power Station (CPS). The infoiriition requested by RIS 2000-14 is attached to this letter.

Sincerely yours, Michael A. Reandeau MAR/blf Attachment cc:

NRC Clinton Licensing Project Manager Regional Administrator USNRC, Region mI NRC Resident Office, V-690 Illinois Department of Nuclear Safety

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Attachment to U-603423 NRC FORM 636 U.S NUCLEAR REGULATORY COMMISSION APPROVED BY M NO 315-0131 EXPIRES 07311002 (B.2000)

Esmed brden per res to om wt vunty Iormaton coalto request I hor,. Wiis Informion colleclton Is used to plan budgets and resources for operator examinations. Send comments relagar Wx~en estmte to fth Recrds OPERATOR LICENSING Wn*erne* B rr4 Ed U S Nula Ruaor Conri, W=sino. DC 2055INATIONrDAT Internet e-m,,to bjl e,,c.ao. W 1 t DekOffice. foeor EXAMINATON DATArid RegulatoryNfalr= NE06-10202 {3160-0131), Offe or Management and Budget WanNngton. DC 20503. I a means used to Inpose an Informatlon colecaion does not display a currencty valid 0MB control number, fte NRC may not conduct or sponsor, and a person Is not required lo respond to, the Information cosection.

FACILITY NRC REGION Clinton Power Station AmerGen Energy, LLC II1 PO Box 678 Clinton, IL 61727 A. PROPOSED EXAMINATION PREPARATION SCHEDULE PROPOSED NUMBER CY01 CY02 CY*o4 CY ESTIMATED NUMBER OF 1

1 1

UCENSEE-PREPARED EXAMINATIONS ESTIMATED NUMBER OF 0

0 0

NRC -PREPARED EXAMINATIONS B. INITIAL OPERATOR LICENSING EXAMINATIONS PROPOSED NUMBER CY01 CY02 CY04 CY NUMBER OF REACTOR 6

6 6

OPERATORS NUMBER OF SENIOR REACTOR 7

5 5

OPERATORS - INSTANT NUMBER OF SENIOR REACTOR 1

5 5

OPERATORS - UPGRADE NUMBER OF SENIOR REACTOR OPERATORS - UMITED 0

0 0

PROPOSED DATES 7116/01 - 7/27101 7/29102 - 8/9/02 4/5/04 - 4116104 PRIMARY DATE 7/16/01 7/29/02 4/5/04 ALTERNATE DATE 8/6/01 8/21/02 4119/04 C. PROPOSED GENERIC FUNDAMENTALS EXAMINATION (GFE) SCHEDULE CY01 CY03 PROPOSED NUMBER FIRST SECOND THIRD FIRST SECOND THIRD ESTIMATED NUMBER 0

12 0

0 OF CANDIDATES THIS FORM WAS DESiGNED USMNG INFORMS NRC FMRM 5M8 P-2000 PRINTED ON RECYCLED PAPER

April 2, 2001 Mr. Michael Heffley Vice President Clinton Power Station AmerGen Energy Company, LLC RR 3 P. 0. Box 228 Clinton, IL 61727

Dear Mr. Heffley:

In response to your facility letters dated July 14, 2000, and October 5, 2000, we have tentatively scheduled an initial licensing examination for your operator license applicants at the Clinton Power Station during the weeks of July 29 and August 5, 2002. Validation of the examination will occur at the station during the week of June 24, 2002. In the unlikely event that we are unable to support the examination during the scheduled weeks, we will inform you immediately upon discovery of such conditions and make arrangements to administer the examination at a mutually acceptable date.

As stated in your letter and confirmed in a telephone conversation between D. J. Russel, Clinton, and J. A. Hopkins, NRC, on February 26, 2001, your staff will develop the examination.

To support the examination administration date, we have tentatively scheduled the date of May 28, 2002, to begin our review of your submitted examination.

Your letter indicated you are training approximately 16 candidates for the examination. Please inform us if the number of candidates declines below 10 as this will impact the examination schedule. Please also inform us at your earliest opportunity if you discover you are unable to support the examination on the scheduled dates.

Once your staff has determined a schedule for examination development, please have them contact the Chief Examiner to arrange for a suitable examination outline submittal date for NRC review. The intent is for the examination outline to be submitted early in the examination development process. This is to preclude the need to make significant changes to developed examination material as a result of the NRC review of the outline. Mr. David L. Pelton has been tentatively assigned as the Chief Examiner and can be reached at 630-829-9732.

A supplementary letter will be sent to the training department approximately 120 days prior to the examination outlining examination security expectations, listing the materials required by the NRC to conduct the examination, reconfirming the examination dates, and reconfirming the number of candidates you have in the training program. If you have any questions concerning this information, please contact Mr. day-A-l%. Hpkins of my staff at 630-829-97-39 DAVI-)

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M. Heffley In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc,cov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

Sincerely, David E. Hills, Chief Operations Branch Division of Reactor Safety Docket No. 50-461 License No. NPF-62 cc:

M. Pacilio, Plant Manager M. Reandeau, Director - Licensing G. Rainey, Chief Nuclear Officer E. Wrigley, Manager-Quality Assurance M. Aguilar, Assistant Attorney General G. Stramback, Regulatory Licensing Services Project Manager General Electric Company Chairman, DeWitt County Board State Liaison Officer Chairman, Illinois Commerce Commission W. N. Lipscomb, Training Department ADAMS Distribution:

DFT JBH1 (Project Mgr.)

J. Caldwell G. Grant B. Clayton SRI Clinton DRP DRSIII PLB1 JRKI BAH3 D. C. Trimble, NRR:DIPM:IOLB M. A. Bies, DRS DOCUMENT NAME: G:\\DRS\\CLI0.

01DRS.WPD To receive a copy of this document, indicate in the box C Cop, w/o attach/end "E" = Copy with attach/end "N" = No copy OFFICE RIII:DRS RIII:DRS l

RIII:DRS NAME MABies:sd,n.w.4 JHopkins z /I DEHills Pig,'

DATE' 03/;;*/01 03/I'

/01 i

10o/- J01 OFFICIAL RECORD COPY AmerGen An Exelon/British Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 Phone: 217 935-8881 U-603544 March 15, 2002 U.S. Nuclear Regulatory Commission, Region III 801 Warrenville Road Lisle, IL 60532-4351 ATTN: Operator Licensing Branch Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 Docket No. 50-461

Subject:

Initial License Examination K/A Catalog Suppression Enclosed are the K/A statements that have been excluded from the random selection process which Clinton Power Station (CPS) is submitting for review, comment, and approval for the Initial License Examination scheduled to start the week of July 29, 2002, for two weeks at CPS.

This submittal includes K/A statements that were suppressed prior to exam outline generation.

This letter is submitted for the K/A suppression as required by NUREG 1021, Revision 8, Supplement 1, Section ES-401, D.l.b.

Should you have any questions concerning this letter, please contact Mr. W. S. Iliff, Regulatory Assurance Manager, at (217) 937-2800.

Respectfully, W. S. Iliff Regulatory Assurance Manager Clinton Power Station EET/blf

Enclosure:

Inapplicable K/A Statements cc:

NRC Document Control Desk - w/o enclosure Region III NRC Regional Administrator-w/o enclosure NRC Senior Resident Inspector - Clinton Power Station - w/o enclosure Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety - w/o enclosure

Clinton Power Station Suppressed KAs System #

System /Evolution Name K4 Statement Basis For Suppression 201001 Control Rod Drive Hydraulic System A1.04 Head spray flow: BWIR-3 Clinton is a BWR 6 and does not have this configuration K1.04 Head spray: BWR-3 Clinton is a BWR 6 and does not have this configuration K1.05 Feedwater (or reactor water cleanup)-CRD return to CRD does not return to the vessel through Feedwater vessel: Plant-Specific or Reactor Water Cleanup.

K3.04 Head spray: BWR-3 Clinton is a BWR 6 and does not have this configuration Reactor Manual Control System CRD drive water flow Control rod position Rod movement sequence lights Overall reactor power Local reactor power Rod movement sequence timer malfunctions Rod drift alarm Select block Control rod block Control rod block actuation Rod movement sequence lights Rod drift alarm Rod movement sequence timer malfunction alarm:

Plant-Specific Rod movement control switch Emergency in/notch override switch Rod drift test switch Timer malfunction test switch: Plant-Specific Rod select matrix Rod select matrix power switch Control rod drive hydraulic system Control rod and drive mechanism Control rod block interlocks/power operation refueling Rod block monitor Plant-Specific Rod worth minimizer: Plant-Specific Rod sequence control system: Plant-Specific Process computer: Plant-Specific Refueling interlocks: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

3/7/02 Pae of26ý-V aS-1,-mmMM0

ý KS #

201002 Al.01 A1.02 A1.03 A1.04 A1.05 A2.01 A2.02 A2.03 A2.04 A3.01 A3.02 A3.03 A3.04 A4.01 A4.02 A4.03 A4.04 A4.05 A4.06 K1.01 K1.02 K1.03 K1.04 K1.05 K1.06 K1.07 K1.08 317102 Page I of 26

System #

System /Evolution Name K/i #

K2.01 K2.02 K3.01 K3.02 K3.03 K4.01 K4.02 K4.03 K4.04 K4.05 K4.06 K4.07 K4.08 K6.01 201004 A1.01 A2.01 A2.02 A2.03 A3.01 A3.02 A3.03 A3.04 A3.05 A4.01 A4.02 A4.03 K1.01 K1.02 K1.03 K1.04 K3.01 K4.01 K4.02 K4.03 K4.04 K4.05 Rod Sequence Control System (Plant Reactor manual control system: BWR-4, 5 Loss of rod position information: BWR-4, 5 Attempting to move a stuck control rod: BWR-4, 5 Turbine trip: BWR-4, 5 Rod select switch light: BWR-4, 5 Rod select bottom lamp dimmer logic: BWR-4, 5 Back panel indicators: BWR-4, 5 Annunciator and alarm signals: BWR-4, 5 Verification of proper function/ operability: BWR-4, 5 System bypass switches: BWR-4, 5 RSCS console switches and indicators: BWR-4, 5 RSCS back panel switches and indicators: BWR-4, 5 Reactor manual control system: BWR-4, 5 Turbine generator system: BWR-4, 5 Rod position information system: BWR-4, 5 Rod worth minimizer: BWR4, 5 Reactor manual control: BWR-4, 5 Select blocks: BWR-4, 5 Insert rod blocks: BWR-4, 5 Withdraw rod blocks: BWR-4, 5 RSCS bypass as reactor power increases: BWR-4, 5 Rod movement, direction, and selection information:

BWR-4, 5 KA Statement Select matrix CRD HCU directional control valves Ability to move control rods Rod block monitor: Plant-Specific Ability to process rod block signals Detection of sequence timer malfunction Control rod blocks Detection of drifting control rods Single notch rod withdrawal and insertion Notch override rod withdrawal Emergency In rod insertion Timing of rod insert and withdrawal cycles (rod movement sequence timer)

Continuous In rod insertion Select matrix power Specific)

Clinton is a BWR-6 and does not utilize this system.

3/7/02M Pag 2 f2 Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

317102 Page 2 of 26

KA #

K4.06 K4.07 K5.01 K5.02 K5.03 K6.01 K6.02 K6.03 K6.04 201006 KA Statement Basis For Suppr*

Group notch control: BWR-4, 5 Clinton is a BWR-6 an Minimizing rod worth: BWR-4, 5 Clinton is a BWR-6 an Prevention of clad damage if a control rod drop Clinton is a BWR-6 an accident (CRDA) occurs: BWR-4, 5 Sequences and groups: BWR-4, 5 Clinton is a BWR-6 an Group notch control limits and rod density: BWR-4, 5 Clinton is a BWR-6 an Rod position information: BWR-4, 5 Clinton is a BWR-6 an Rod direction information: BWR-4, 5 Clinton is a BWR-6 an Rod movement information: BWR-4, 5 Clinton is a BWR-6 an Turbine generator (1st stage shell pressure): BWR-4, 5 Clinton is a BWR-6 an Rod Worth Minimizer System (R WM) (Plant Specific)

A1.01 Rod position: P-Spec(Not-BWR6)

A1.02 Status of control rod movement blocks; P-Spec(Not BWR6)

A1.03 Latched group indication: P-Spec(Not-BWR6)

A2.01 Power supply loss: P-Spec(Not-BWR6)

A2.02 Loss of steam flow input: P-Spec(Not-BWR6)

A2.03 Rod drift: P-Spec(Not-BWR6)

A2.04 Stuck rod: P-Spec(Not-BWR6)

A2.05 Out of sequence rod movement; P-Spec(Not-BWR6)

A2.06 Loss of reactor water level control input: P-Spec(Not BWR6)

A2.07 RWNM hardware/software failure: P-Spec(Not-BWR6)

A3.01 System window and light indication: P-Spec(Not BWR6)

A3.02 Verification of proper functioning/ operability: P Spec(Not-BWR6)

A3.03 Annunciator and alarm signals: P-Spec(Not-BWR6)

A3.04 Control rod movement blocks: P-Spec(Not-BWR6)

A3.05 Latched group indication: P-Spec(Not-BWR6)

A4.01 System bypass switch: P-Spec(Not-BWR6)

A4.02 Pushbutton indicating switches: P-Spec(Not-BWR6)

A4.03 Latched group indication: P-Spec(Not-BWR6)

A4.04 Rod withdrawal error indication: P-Spec(Not-BWR6)

A4.05 Rod insert error indication: P-Spec(Not-BWR6)

A4.06 Selected rod position indication: P-Spec(Not-BWR6)

K1.01 Reactor manual control: P-Spec(Not-BWR6)

K1.02 Rod position indication system: P-Spec(Not-BWR6)

K1.03 Reactor water level control (feed flow): P-Spec(Not BWR6)

K1.04 Steam flow/reactor power: P-Spec(Not-BWR6)

.ssion d does not utilize this system.

d does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

3/7/02~

Pae3.2 Page 3 of 26 System #

System/IEvolution Name 317102

System /Evolution Name KA #

KA Statement K1.05 Control rod drop accident: P-Spec(Not-BWR6)

K1.06 Rod sequence control system: P-Spec(Not-BWR6)

K1.07 Process computer P-Spec(Not-BWR6)

K1.08 Reactor power (turbine first stage pressure): P Spec(Not-BWR6)

K2.01 Rod worth minimizer: P-Spec(Not-BWR6)

K3.01 Reactor manual control system: P-Spec(Not-BWR6)

K4.01 Insert blocks/errors: P-Spec(Not-BWR6)

K4.02 Withdraw blocks/errors: P-Spec(Not-BWR6)

K4.03 Select blocks/errors: P-Spec(Not-BWR6)

K4.04 System bypass: P-Spec(Not-BWR6)

K4.05 Substitute rod position data: P-Spec(Not-BWR6)

K4.06 Correction of out of sequence rod positions: P Spec(Not-BWR6)

K4.07 Display of out of position control rods without rod blocks (transition zone): P-Spec(Not-BWR6)

K4.08 System testing: P-Spec(Not-BWR6)

K4.09 System initialization: P-Spec(Not-BWR6)

K5.01 Minimize clad damage if a control rod drop accident (CRDA) occurs: P-Spec(Not-BWR6)

K5.02 Low power set point: P-Spec(Not-BWR6)

K5.03 Low power alarm point (LPAP): P-Spec(Not-BWR6)

K5.04 Transition zone: P-Spec(Not-BWR6)

K5.05 High power set point: P-Spec(Not-BWR6)

K5.06 Rod groups and steps: P-Spec(Not-BWR6)

K5.07 Latch groups: P-Spec(Not-BWR6)

K5.08 Operating sequence: P-Spec(Not-BWR6)

K5.09 Select error: P-Spec(Not-BWR6)

K5.10 Withdraw error: P-Spec(Not-BWR6)

K5.1 1 Insert error: P-Spec(Not-BWR6)

K5.12 Withdraw block: P-Spec(Not-BWR6)

K5.13 Insert block: P-Spec(Not-BWR6)

K5.14 Alternate withdraw and insert limits: P-Spec(Not-BWR6)

K6.01 RWM power supply: P-Spec(Not-BWR6)

K6.02 Reactor water level control input: P-Spec(Not-BWR6)

K6.03 Rod position indication: P-Spec(Not-BWR6)

K6.04 Process computer P-Spec(Not-BWR6)

K6.05 Steam flow input: P-Spec(Not-BWR6)

Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BVVR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

202001 Recirculation System A2.09 Recirculation scoop tube lockup: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

3/7/02 Page 4 of26 System #

System lEvolution Name KA Statement Suppression pool level: BWR-2, 3, 4 Rod block monitor: Plant-Specific Isolation condenser: Plant-Specific MG set oil pumps: Plant-Specific Load following capabilities: Plant-Specific Isolation condenser: Plant-Specific Oil pump automatic starts: Plant-Specific Basis For Suppression Clinton is a BWR 6 Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

KA4#

A2.23 K1.14 K1.24 1K2.05 K3.02 K3.12 K4.08 202002 A2.05 A3.03 A4.06 K4.01 K4.04 K(4.08 K5.01 Scoop tube lockup: BWR-2, 3, 4 Scoop tube operation: BWR-2, 3, 4 Scoop tube power: BWR-2, 3, 4 Scoop tube break: Plant-Specific Automatic load following: Plant-Specific Automatic flow control valve positioning: BWR-5, 6 Fluid coupling: BWR-3, 4 RHR/LPCI: Injection Mode (Plant Loop selection logic failure: Plant-Specific A3.07 Loop selection: Plant-Specific A4.12 Condensate storage tank level: Plant-Specific A4.14 Testable check valves K1.05 Recirculation system: BWR-3, 4 K4.1 1 Loop selection logic: Plant-Specific K5.01 Testable check valve operation Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does utilize this system.

Clinton does not utilize this function.

Clinton is a BWR 6 and does not utilize this configuration.

Specific)

Clinton is a BWR 6 and does not utilize this configuration.

Clinton is a BWR 6 and does not utilize this function.

Clinton is a BWR 6 and does not utilize this configuration.

204000 Reactor Water Cleanup System A2.02 Pressure control valve failure: LP-RWCU Clinton utilizes a HP RWCU system.

A3.01 System pressure downstream of the pressure Clinton utilizes a HP RWCU system.

regulating valve: LP-RWCU K4.08 Reducing reactor pressure upstream of low pressure Clinton utilizes a HP RWCU system.

piping: LP-RWCU 205000 Shutdown Cooling System (RMR Shutdown Cooling Mode)

A2.11 Recirculation pump trips: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.09 Auxiliary steam supply: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K11.11 Nitrogen: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Page 5 of 26 System #

Recirculation Flow Control System 203000 A2.105 317102

System / Evolution Name KA Statement Isolation condenser: Plant-Specific Nitrogen: Plant-Specific 206000 Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

em A1.01 A1.02 A1.03 A1.04 A1.05 A1.06 A1.07 A1.08 A1.09 A2.01 A2.02 A2.03 A2.04 A2.05 A2.06 A2.07 A2.08 A2.09 A2. 10 A2.11 A2.12 A2.13 A2.14 A2.15 A2.16 A2.17 A3.01 A3.02 A3.03 A3.04 A3.05 A3.06 A3.07 A3.08 A3.09 3/7/02 System #

K4 #

K1.12 K6.07 tem High Pressure Coolant Injection Sysi Reactor water level: BWR-2, 3, 4 Reactor pressure: BWR-2, 3, 4 Condensate storage tank level: BWR-2, 3, 4 Suppression pool level: BWR-2, 3, 4 Suppression pool temperature: BWR-2, 3, 4 System flow: BWR-2, 3, 4 System discharge pressure: BWR-2, 3, 4 System lineup: BWR-2, 3, 4 Turbine speed: BWR-2, 3, 4 Turbine trips: BWR-2, 3, 4 Valve closures: BWR-2, 3, 4 Valve openings: BWR-2, 3, 4 A.C. failures: BWR-2, 3, 4 D.C. failures: BWR-2, 3, 4 Inadequate system flow: BWNR-2, 3, 4 Low suppression pool level: BWR-2, 3, 4 High suppression pool temperature: BWR-2, 3, 4 Low condensate storage tank level: BWR-2, 3, 4 System isolation: BWR-2, 3, 4 Low reactor water level: BWR-2, 3, 4 Loss of room cooling: BWR-2, 3, 4 Loss of applicable plant air systems: BWR-2, 3, 4 Flow controller failure: BWR-2, 3, 4 Loss of control oil pressure: BWR-2, 3, 4 High drywell pressure: BWR-2, 3, 4 HPCI inadvertent initiation: BWR-2, 3, 4 Turbine speed: BWR-2, 3, 4 System Flow: BWR-2, 3, 4 System lineup: BWR-2, 3, 4 Reactor pressure: BWR-2, 3, 4 Reactor water level: BWR-2, 3, 4 System discharge pressure: BWR-2, 3, 4 Lights and alarms: BWR-2, 3, 4 Condensate storage tank level: BWR-2, 3, 4 Response to system isolation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

Page 6 of 26

KA #

A4.01 A4.02 A4.03 A4.04 A4.05 A4.06 A4.07 A4.08 A4.09 A4. 10 A4.1 1 A4.12 A4.13 A4.14 K1.01 K1.02 K1.03 K1.04 K1.05 K1.06 K1.07 K1.08 K1.09 K1.10 K1.11 K1.12 K1.13 K1.14 K1.15 K1.16 K2.01 K2.02 K2.03 K2.04 K3.01 K3.02 K3.03 K4.01 System lEvolution Name KA Statement Turbine speed controls: BWR-2, 3, 4 Flow controller: BWR-2, 3, 4 Turbine temperatures: BWR-2, 3, 4 Major system valves: BWR-2, 3, 4 Reactor water level: BWR-2, 3, 4 Reactor pressure: BWR-2, 3, 4 Condensate storage tank level: BWR-2, 3, 4 Suppression pool temperature: BWR-2, 3, 4 Suppression pool level: BWR-2, 3, 4 System pumps: BWR-2, 3, 4 Turning gear: BWR-2, 3, 4(P-Spec)

Turbine trip controls: BWR-2, 3, 4 Turbine reset control: BWR-2, 3, 4 System auto start control: BWR-2, 3, 4(P-Spec)

Reactor vessel: BWR-2, 3, 4 Reactor water level: BWR-2, 3, 4 Reactor pressure: BWR-2, 3, 4 Reactor feedwater system: BWR-2, 3, 4 Condensate storage system: BWR-2, 3, 4 Suppression chamber: BWR-2, 3, 4 D.C. power: BWR-2, 3, 4 A.C. power: BWR-2, 3, 4 ECCS keep fill system: BWR-2, 3, 4(P-Spec)

Condensate storage and transfer system: BWR-2, 3, 4 PCIS: BWR-2, 3, 4 Nuclear boiler instrumentation: BWR-2, 3, 4 Main condenser: BWR-2, 3, 4(P-Spec)

SBGT: BWR-2, 3, 4(P-Spec)

Plant air systems: BWR-2, 3, 4 Containment/Torus pressure: BWR-2, 3, 4 System valves: BWR-2, 3, 4 System pumps: BWR-2, 3, 4 Initiation logic: BWR-2, 3, 4 Turbine control circuits: BWR-2, 3, 4 Reactor water level control: BWR-2, 3, 4 Reactor pressure control: BWR-2, 3, 4 Suppression pool level control: BWR-2, 3, 4 Turbine trips: BWR-2, 3, 4 3/7/02 Page 7 of 26 Basis For Suppression Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

System #

System lEvolution Name KA4 #

KA Statement K4.02 System isolation: BWR-2, 3, 4 K4.03 Resetting turbine trips: BWR-2, 3, 4 K4.04 Resetting system isolations: BWR-2, 3, 4 K4.05 Preventing water hammer in turbine exhaust line (procedural control): BWR-2, 3, 4 K4.06 Preventing water hammer in pump discharge line (procedural control ): BWR-2, 3, 4 K4.07 Automatic system initiation: BWR-2, 3, 4 K4.08 Manual system initiation: BWR-2, 3, 4 K4.09 Automatic flow control: BWR-2, 3, 4 K4.10 Surveillance for all operable components: BWR-2, 3, 4 K4.11 Turbine speed control: BWR-2, 3, 4 K4.12 Condensation of shaft sealing steam: BWR-2, 3, 4 K4.13 Turbine and pump lubrication: BWR-2, 3, 4 K4.14 Control oil to turbine speed controls: BWR-2, 3, 4 K4.15 Low speed turning of the turbine rotor: BWR-2, 3, 4(P Spec)

K4.16 Minimizing fission product concentration in the condensate storage tank (valve closures on system initiation): BWR-2, 3, 4(P-Spec)

K4.17 Protection against draining the condensate storage tank to the suppression pool: BWR-2, 3, 4 K4.18 Pump minimum flow: BWR-2, 3, 4 K4.19 Automatic transfer of HPCI pump suction: BWR-2, 3, 4 K5.01 Turbine operation: BWR-2, 3, 4 K5.02 Turbine shaft sealing: BWR-2, 3, 4 K5.03 GEMAC controllers: BWR-2, 3, 4(P-Spec)

K5.04 Indications of pump cavitation: BWR-2, 3, 4 K5.05 Turbine speed control: BWR-2, 3, 4 K5.06 Turbine speed measurement: BWR-2, 3, 4 K5.07 System venting: BWR-2, 3, 4 K5.08 Vacuum breaker operation: BWR-2, 3, 4 K5.09 Testable check valve operation: BWR-2, 3, 4 K5.10 Assist core cooling: BWR-2, 3, 4 K6.01 Plant air systems: BWR-2, 3, 4 1K6.02 D.C. power: BWR-2, 3, 4 K6.03 A.C. power. BWR-2, 3, 4 K6.04 Condensate storage tank level: BWR-2, 3, 4 K6.05 Suppression pool level: BWR-2, 3, 4 K6.06 SBGTS: BWR3-2, 3, 4(P-Spec)

K6.07 ECCS keep fill system: BWR-2, 3, 4(P-Spec)

Basis For Suppression Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

Page 8 of 26 317102

System /Evolution Name KA Statement Reactor pressure: BWR-2, 3, 4 Condensate storage and transfer system: BWR-2, 3, 4 PCIS: BWR-2, 3, 4 Nuclear boiler instrumentation: BWR-2, 3, 4 Reactor water level: BWR-2, 3, 4 Basis For Suppression Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

KA #

K6.08 K6.09 K6.10 K6.11 K6.12 207000 A1.01 A1.02 A1.03 A1.04 A1.05 A1.06 A1.07 A1.08 A1.09 A1.10 A2.01 A2.02 A2.03 A2.04 A2.05 A2.06 A2.07 A2.08 A3.01 A3.02 A3.03 A3.04 A3.05 A3.06 A3.07 A3.08 A4.01 A4.02 A4.03 A4.04 A4.05 A4.06 3/7/02 Isolation (Emergency) Condenser Isolation condenser level: BWR-2, 3 Shell side water temperature: BWR-2, 3 Steam flow: BWR-2, 3 Condensate flow: BWR-2, 3(P-Spec)

Reactor pressure: BWR-2, 3 Reactor water level: BWR-2, 3 Vent radiation level: BWR-2, 3 Cooldown rate: BWR-2, 3 Valve operations: BWR-2, 3 Primary side temperature: BWR-2, 3 Tube bundle leak: BWR-2, 3 High vent radiation: BWR-2, 3 PCIS signal resulting in system isolation: BWR-2, 3 Inadequate system flow: BWR-2, 3 Insufficient shell side makeup flow: BWR-2, 3 Valve openings: BWR-2, 3 Valve closures: BWR-2, 3 System initiation: BWR-2, 3 Isolation condenser level: BWR-2, 3 Reactor pressure: BWR-2, 3 Reactor water level: BWR-2, 3 Vent radiation levels: BWR-2, 3 System lineup: BWR-2, 3 Lights and alarms: BWR-2, 3 Primary and shell side temperatures: BWR-2, 3 System flow: BWR-2, 3 Isolation condenser level: BWR-2, 3 Steam line pressure: BWR-2, 3 Primary and shell side temperatures: BWR-2, 3 Vent line radiation levels: BWR-2, 3 Major system valves: BWR-2, 3 Shell side makeup valves: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

Page 9 of 26 System #

System #

System / Evolution Name KA #

K4 Statement A4.07 Manually initiate the isolation condenser: BWR-2, 3 K1.01 Reactor vessel: BWR-2, 3 KI.02 Reactor pressure: BWR-2, 3 K1.03 Reactor water level: BWR-2, 3 K1.04 Condensate transfer system: BWR-2, 3 K1.05 Demineralized water system: BWR-2, 3(P-Spec)

K1.06 Fire protection/service water: BWR-2, 3 K1.07 LPCI: BWR-2, 3(P-Spec)

K1.08 Recirculation system: BWR-2, 3 K1.09 Main steam system: BWR-2, 3 K1.10 Plant air systems: BWR-2, 3 K1.11 Primary containment isolation system: BWR-2, 3 K2.01 Motor operated valves: BWR-2, 3 K2.02 Initiation logic: BWR-2, 3 K3.01 Reactor pressure control during conditions in which the reactor vessel is isolated: BWR-2, 3 K3.02 Reactor water level (EPG's address the isolation condenser as a water source): BWR-2, 3 K4.01 Isolation of the system in the event of a line break:

BWR-2, 3 K4.02 Automatic initiation: BWR-2, 3 K4.03 Filling of the system: BWR-2, 3 K4.04 Steam and condensate flow indication: BWR-2, 3 K4.05 Detection of a tube bundle leak: BWR-2, 3 K4.06 Throttling of system flow: BWR-2, 3 K4.07 Manual operation of the system: BWR-2, 3 K4.08 Protection against incomplete steam condensation (condensate outlet valve does not fully open): BWR 2,3,(P-Spec)

K5.01 Flow measurement across an elbow using differential pressure: BWR-2, 3 K5.02 Heat exchanger operation: BWR-2, 3 K5.03 Heat transfer: BWR-2, 3 K5.04 Latent heat of vaporization: BWR-2, 3 K5.05 Saturated steam: BWR-2, 3 K5.06 Saturated liquid: BWR-2, 3 K5.07 Temperature sensing: BWR-2, 3 K5.08 Level indicator operation: BWR-2, 3 K5.09 Cooldown rate: BWR-2, 3 K5.10 System venting: BWR-2, 3 K6.01 Demineralized water system: BWR-2, 3(P-Spec)

Basis For Suppression Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

3/7/02 Page 10 of 26

System/Evolution Name KA Statement Fire protectionlservice water system: BWR-2, 3 Condensate transfer system: BWR-2, 3 Plant air systems: BWR-2, 3 Primary containment isolation system: BWR-2, 3 Recirculation system: BWR-2, 3 A.C. power: BWR-2, 3 D.C. power: BWR-2, 3 Basis For Suppression Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR-6 and does not utilize this system.

209001 Low Pressure Core Spray System A2.1 1 Loss of fire protection: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

A4.06 Testable check valves Clinton does not utilize this function.

A4.14 Containment level: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

K5.06 Recirculation operation: Plant-Specific(BWR-1)

Clinton is a BWR-6 and does not utilize this feature.

K6.09 Fire protection: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

209002 High Pressure Core Spray System (HPCS)

A4.06 Testable check valve: BWR-5, 6 Clinton removed this function.

K1.13 Instrument nitrogen: BWR-5, 6 Clinton is a BWR 6 and does not utilize this configuration.

211000 Standby Liquid Control System K1.10 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.09 Dampening of positive displacement pump discharge Clinton is a BWR 6 and does not utilize this oscillations (accumulators): Plant-Specific configuration.

K5.05 Accumulator operation: Plant-Specific Clinton is a BWR 6 and does not utilize this configuration.

K6.05 HPCI system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Reactor Protection System RPS motor-generator output voltage RPS motor-generator output amps RPS motor-generator output frequency: Plant-Specific Individual relay status: Plant-Specific RPS motor-generator set failure Partial system activation (half-SCRAM)

Failure of individual relays to reposition: Plant-Specific Individual system relay status: Plant-Specific Provide manual select rod insertion: Plant-Specific Individual system relay status: Plant-Specific RPS motor-generator sets Select rod insertion: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and utilizes a solid state system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and utilizes a solid state system.

Clinton is a BWR 6 and does not utilize this function.

Clinton is a BWR 6 and utilizes a solid state system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this function.

3/7/02 Page II of 26 System #

KA #

K6.02 K6.03 K6.04 K6.05 K6.06 K6.07 K6.08 212000 A1.01 A1.02 A1.03 A1.09 A2.01 A2.19 A2.21 A3.02 A4.03 A4.08 K2.01 K4.06 Page 11 of 26 317102

System #

System lEvolution Name KA #

KA Statement Basis For Suppression 214000 Rod Position Information System K1.01 RWM: Plant-Specific Clinton is a BWR-6 and does not utilize this system.

K1.02 RSCS: Plant-Specific Clinton is a BWR-6 and does not utilize this system.

K1.04 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this function.

K3.01 RWM: Plant-Specific Clinton is a BWR-6 and does not utilize this system.

K3.02 RSCS: Plant-Specific Clinton is a BWR-6 and does not utilize this system.

K3.03 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this function.

215001 Traversing In-Core Probe A1.03 Valve status: Mark-l&Il(Not-BWR1)

Clinton is a BWR 6 and does not utilize this configuration.

A2.01 Low reactor water level: Mark-I&ll(Not-BWR1)

Clinton is a BWR 6 and does not utilize this configuration.

A2.02 High primary containment pressure: Mark-I&ll(Not-Clinton is a BWR 6 and does not utilize this BWR1) configuration.

A2.06 Valve closures: Mark-I&ll(Not-BWR1)

Clinton is a BWR 6 and does not utilize this configuration.

A2.07 Failure to retract during accident conditions: Mark-Clinton is a BWR 6 and does not utilize this I&II(Not-BWR1) configuration.

A3.03 Valve operation: Not-BWR1 Clinton is a BWR 6 and does not utilize isolation valves.

A4.03 Isolation valves: Mark-I&ll(Not-BWR1)

Clinton is a BWR 6 and does not utilize this configuration.

K1.03 Nitrogen purge system: P-Spec(Not-BWR1)

Clinton does not utilize nitrogen purge for TIPS.

K2.01 Shear valves: Mark-I&ll(Not-BWR1)

Clinton is a BWR 6 and does not utilize this configuration.

K4.01 Primary containment isolation: Mark-I&ll(Not-BWR1)

Clinton is a BWR 6 and does not utilize this configuration.

K6.04 Primary containment isolation system: Mark-I&ll(Not-Clinton is a BWR 6 and does not utilize this BWR1) configuration.

215002 Rod Block Monitor System A1.01 Trip reference: BWR-3, 4, 5 A2.01 Withdrawal of control rod in high power region of core:

BWR-3, 4, 5 A2.02 Loss or reduction in recirculation system flow (flow comparator): BWR-3, 4, 5 A2.03 Loss of associated reference APRM channel: BWR-3, 4,5 A2.04 Power supply losses: BWR-3, 4, 5 A2.05 RBM high or inoperable: BWR-3, 4, 5 A3.01 Four rod display: BWR-3, 4, 5 A3.02 Meters and recorders: BWR-3, 4, 5 A3.03 Alarm and indicating lights: BWR-3, 4, 5 A3.04 Verification or proper functioning/ operability: BWR-3, 4,5 Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Page 12 of 26 317102

System/Evolution Name KA #

KA Statement A3.05 Back panel meters and indicating lights: BWR-3, 4, 5 A3.06 Transfer to alternate APRM when referenced APRM bypassed: BWR-3, 4, 5 A4.01 IRM/RBM recorder/switch: BWR-3, 4, 5 A4.02 RBM back panel switches, meters and indicating lights:

BWR-3, 4,5 A4.03 Trip bypasses: BWR-3, 4, 5 A4.04 Push to Check pushbutton: Plant-Specific A4.05 Setup pushbutton: Plant-Specific A4.06 Surveillance testing: BWR-3, 4, 5 K1.01 APRM: BWR-3, 4, 5 K1.02 LPRM: BWR-3, 4, 5 K1.03 Reactor manual control: BWR-3, 4, 5 K1.04 Recirculation system: BWR-3, 4, 5 K1.05 Four rod display: BVVR-3, 4, 5 K1.06 Control rod selection: BWR-3, 4, 5 K1.07 IRM: BWR-3, 4, 5 K2.01 RBM channels: BWR-3, 4, 5 K2.02 Recorders: BWR-3, 4, 5 K2.03 APRM channels: BWR-3, 4, 5 K3.01 Reactor manual control system: BWR-3, 4, 5 K3.02 Limiting control rod pattern: Plant-Specific K4.01 Prevent control rod withdrawal: BWR-3, 4, 5 K4.02 Allows stepping up of rod block setpoint: BWR-3, 4, 5 K4.03 Initiation point (30%): BWR-3, 4, 5 K5.01 Trip reference selection: Plant-Specific K5.02 Null sequence control: BWR-3, 4, 5 K6.01 RPS: BWR-3, 4, 5 K6.02 Instrument power: Plant-Specific K6.03 Essential power: Plant-Specific K6.04 APRM reference channel: BWR-3, 4, 5 K6.05 LPRM detectors: BWR-3, 4, 5 Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

5003 Intermediate Range Monitor (IRM) System K1.02 Reactor manual control Clinton is a BWR 6 and does not utilize this system.

K3.02 Reactor manual control Clinton is a BWR 6 and does not utilize this system.

Source Range Monitor (SRM) System K1.02 Reactor manual control K3.02 Reactor manual control: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Page 13 of 26 21 215004 317102 System#

System #

System /Evolution Name KA #

KA Statement Basis For Suppression 215005 Average Power Range Monitor/Local Power Range Monitor System K1.03 RBM: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.10 Reactor manual control system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.03 Reactor manual control system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

216000 Nuclear Boiler Instrumentation K1.14 High pressure coolant injection: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.15 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.14 High pressure coolant injection: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.15 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode A1.09 Suppression chamber air temperature: Plant-Specific Clinton is a BWR 6 and does not have a suppression chamber.

K1.07 Condensate transfer This system does not serve any purpose for suppression pool cooling.

K6.07 Condensate transfer This system is not utilized for this function.

223001 Primary Containment System andAuxiliaries A1.11 Reactor building to suppression chamber differential Clinton is a BWR 6 and does not utilize this system.

pressure: Plant-Specific A1.12 Moisture concentration Clinton is a BWR 6 and does not utilize this system.

A3.06 Drywell/suppression chamber differential pressure:

Clinton is a BWR 6 and does not utilize this system.

Mark-III A4.02 ACAD compressors: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

A4.10 Drywell nitrogen makeup: Mark-Ill Clinton is a BWR 6 and does not utilize this system.

K1.15 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.17 Reactor building HVAC: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.18 Drywell pneumatic compressors: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K2.02 Drywell compressors Clinton is a BWR 6 and does not utilize this system.

K2.03 Pumpback compressors: Plant-Specific Clinton is a BWR 6 and does not utilize this component.

K3.10 Containment/drywell moisture content Clinton is a BWR 6 and does not utilize this system.

K5.15 Moisture content measurement: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

223002 Primary Containment Isolation System/Nuclear Steam Supply Shut K11.04 High pressure coolant injection: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.05 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.13 Traversing in-core probe system Clinton utilizes a TIP system inside the primary containment.

K1.18 Reactor building drainage system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.22 Containment nitrogen inerting system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.04 Reactor building radiation level Clinton is a BWR 6 and does not utilize this system.

3/7/02 Page 14 of 26

System lEvolution Name KA Statement High pressure coolant injection: Plant-Specific Isolation condenser Plant-Specific Traversing in-core probe system K3.24 Reactor building drainage system K3.28 Containment nitrogen inerting system Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton utilizes a TIP system inside the primary containment.

Clinton is a BWR 6 and does not utilize this system.

6001 RIR/LPCI: Containment Spray System Mode A1.03 Suppression chamber pressure: Mark-I-Il Clinton is a BWR 6 and does not utilize this system.

A1.04 Suppression pool temperature: Mark-I-Il Clinton is a BWR 6 and does not utilize this system.

A2.19 Low (or negative) suppression chamber pressure Clinton is a BWR 6 and does not utilize this system.

during system operation: Mark-I-Il A4.15 Suppression chamber pressure: Mark-I-II Clinton is a BWR 6 and does not utilize this system.

K1.06 Condensate transfer Clinton is a BWR 6 and does not utilize this system.

K1.09 Drywell (spray penetration): Mark-I-Il Clinton is a BWR 6 and does not utilize this system.

K1.12 Suppression pool (spray penetration): Plant-Specific Clinton is a BWR 6 and does not utilize this suppression pool spray.

K6.06 Condensate transfer Clinton is a BWR 6 and does not utilize this system.

K6.09 Reactor building to suppression chamber vacuum Clinton is a BWR 6 and does not utilize this system.

breakers: Plant-Specific K6.10 Suppression chamber to drywell vacuum breakers:

Clinton is a BWR 6 and does not utilize this system.

Mark-l-II 230000 RHR/LPCI: Torus/Suppression Pool Spray Mode A1.01 Suppression chamber pressure Clinton is a BWR 6 and does not utilize this system.

A1.02 Suppression pool temperature Clinton is a BWR 6 and does not utilize this system.

A1.03 Drywell pressure Clinton is a BWR 6 and does not utilize this system.

A1.04 System flow Clinton is a BWR 6 and does not utilize this system.

A1.05 System pressure Clinton is a BWR 6 and does not utilize this system.

A1.06 Suppression pool level Clinton is a BWR 6 and does not utilize this system.

A1.07 Condensate storage tank level Clinton is a BWR 6 and does not utilize this system.

Al.08 Motor amps Clinton is a BWR 6 and does not utilize this system.

Al.09 Emergency generator loading Clinton is a BWR 6 and does not utilize this system.

A1.10 System lineup Clinton is a BWR 6 and does not utilize this system.

A1.11 Suppression chamber air temperature Clinton is a BWR 6 and does not utilize this system.

A2.01 Inadequate net positive suction head Clinton is a BWR 6 and does not utilize this system.

A2.02 Pump trips Clinton is a BWR 6 and does not utilize this system.

A2.03 Valve closures Clinton is a BWR 6 and does not utilize this system.

A2.04 Valve openings Clinton is a BWR 6 and does not utilize this system.

A2.05 A.C. electrical failures Clinton is a BWR 6 and does not utilize this system.

A2.06 D.C. electrical failures Clinton is a BWR 6 and does not utilize this system.

A2.07 Emergency generator failure Clinton is a BWR 6 and does not utilize this system.

3/7/02 Page 15 of 26 System #

KA #

K3.12 K3.13 K3.21 22

Systm #

System IlEvolution Name K4 #

A2.08 A2.09 A2.10 A2.11 A2.12 A2.13 A2.14 A2.15 A2.16 A3.01 A4.01 A4.02 A4.03 A4.04 A4.05 A4.06 A4.07 A4.08 A4.09 A4.10 A4.11 A4.12 A4.13 A4.14 A4.15 A4.16 K1.01 K1.02 K1.03 K1.04 K1.05 K1.06 K1.07 K1.08 K1.09 K1.10 K2.01 KA Statement Pump seal failure Inadequate room cooling Nuclear boiler instrument failures Motor operated valve failures Valve logic failure High suppression pool level Low (or negative) suppression pool pressure during system operation Loss of coolant accident Loss of, or inadequate, heat exchanger cooling flow Valve operation Pumps Spray valves Keep fill system Minimum flow valves Heat exchanger cooling flow Valve logic reset following automatic initiation of LPCI/RHR in injection mode System flow Pump/system discharge pressure Indicating lights and alarms Condensate storage tank level System venting Suppression pool level Suppression chamber pressure Suppression pool temperature Drywell pressure The override for suppression pool spray valve logic Suppression pool Condensate storage and transfer system LPCI/RHR piping LPCI/RHR pumps A.C. electrical Keep fill system D.C. electrical Nuclear boiler instrumentation Reactor building drain system Component cooling water systems Valves Page 16 of 26 Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Systemvluio Na#

317102

System #

System/Evolution Name KA #

K2.02 K3.01 K3.02 K3.03 K3.04 K4.01 K4.02 K4.03 K4.04 K4.05 K4.06 K4.07 K4.08 K4.09 K4.10 K5.01 K5.02 K5.03 K5.04 K5.05 K5.06 K5.07 K6.01 K6.02 K6.03 K6.04 K6.05 K6.06 K6.07 K6.08 K6.09 K6.110 233000 K1.07 K1.11 K6.05 KA Statement Pumps Suppression chamber pressure Suppression pool temperature Drywell pressure Suppression chamber air temperature Surveillance for all operable components Redundancy Unintentional reduction in vessel injection flow during accident conditions Prevention of piping overpressurization Pump minimum flow protection Pump motor cooling Prevention of water hammer Adequate pump net positive suction head Spray flow cooling Prevention of leakage to the environment through system heat exchanger System venting Pump cavitation Pressure measurement Evaporative cooling Convective cooling Heat exchanger operation Vacuum breaker operation A.C. electrical D.C. electrical Emergency generator Keep fill system Suppression pool Condensate storage and transfer system ECCS room cooling Nuclear boiler instrumentation Reactor building to suppression pool vacuum breakers Component cooling water systems Fuel Pool Cooling and Clean-up Condensate system: Plant-Specific Reactor building drainage system: Plant-Specific Condensate system Clinton is a BWR 6 and does utilize this configuration.

Clinton is a BWR 6 and does utilize this configuration.

3/7/02 Page 17 of 26 Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

System #

System/Evolution Name KA Statement Fuel Handling Equipment Reactor manual control system: Plant-Specific Reactor manual control system: Plant-Specific Reactor manual control system: Plant-Specific Main and Reheat Steam System High pressure coolant injection: Plant-Specific Isolation condenser system: Plant-Specific High pressure coolant injection system: Plant-Specific Isolation condenser: Plant-Specific Residual heat removal system: Plant-Specific Hydraulic operated MSIVs Basis For Suppression Clinton is a BWR 6 and does utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton does not utilize this function.

Clinton is a BWR 6 and does not utilize this system.

239002 Relief/Safety Valves K1.06 Drywell instrument air/ drywell pneumatics: Plant-Clinton is a BWR 6 and does not utilize this system.

Specific K1.09 Drywell pressure (for safety valves which discharge to Clinton is a BWR 6 and does not utilize this system.

the drywell airspace): Plant-Specific 241000 Reactor/Turbine Pressure Regulating System A3.15 Recirculation pump flow control: Plant-Specific Clinton is a BWR 6 and there is no tie to this system.

K1.15 D.C. electrical power DC does not supply power to this system.

K1.23 Recirculation flow control system: Plant-Specific Clinton is a BWR 6 and there is no tie to this system.

K1.37 Turbine stress evaluator: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.21 Recirculation flow control system: Plant-Specific Clinton is a BWR 6 and there is no tie to this system.

K4.1 1 Load following: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.12 Recirculation flow control: Plant-Specific Clinton is a BWR 6 and there is no tie to this system.

K5.01 Accumulator operation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K5.07 Unitized actuator operation: Fermi-Only Clinton is a BWR 6 and does not utilize this system.

K6.04 Recirculation flow control system: Plant-Specific Clinton is a BWR 6 and there is no tie to this system.

245000 Main Turbine Generator andAuxiliary Systems K2.03 Amplidyne: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K2.05 Air seal oil pumps: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Reactor Condensate System HPCI: Plant-Specific Isolation condenser Plant-Specific RHR (LPCI): Plant-Specific ECCS keep fill system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton does not utilize this function.

Clinton does not utilize this function from reactor condensate.

3/7/02 KA #

234000 K1.04 K3.01 K6.02 239001 K1.18 K1.21 K3. 10 K3.12 K3.14 K5.07 256000 K1.03 K1.12 K1.14 K1.17 Page 18 of 26

System/Evolution Name KA #

KA Statement K3.05 HPCI: Plant-Specific K3.07 Isolation condenser: Plant-Specific K4.01 Condensate and/or booster pump auto start: Plant Specific K4.08 Dedicated ECCS water supply: Plant-Specific Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton does not have an auto start on the CD/CB pumps.

Clinton does not utilize this function from reactor condensate.

259001 Reactor Feedwater System A3.11 Reactor feedpump runbacks: Plant-Specific Clinton does not utilize this function.

K1.02 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.18 Fire protection system (emergency cooling): Plant-Clinton does not utilize this function through reactor Specific feedwater.

K1.19 Redundant reactivity control system: Plant-Specific Clinton does not utilize this function.

K3.03 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.10 Feedpump runbacks: Plant-Specific Clinton does not utilize this function.

259002 Reactor Water Level Control System A1.06 Feedwater string(s) selected for FWCI: FWCI Clinton is a BWR 6 and does not utilize this system.

A2.08 Receipt of an ECCS initiation signal: FWCI Clinton is a BWR 6 and does not utilize this system.

A2.09 FWCI system failure alarm: FWCI Clinton is a BWR 6 and does not utilize this system.

A3.08 FWCI system initiation: FWCI Clinton is a BWR 6 and does not utilize this system.

A4.08 Manually initiate FWCI: FWCI Clinton is a BWR 6 and does not utilize this system.

K1.07 Rod worth minimizer: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.10 Emergency generator(s): FWCl/HPCI Clinton is a BWR 6 and does not utilize this system.

K1.11 Drywell pressure: FWCI/HPCI Clinton is a BWR 6 and does not utilize this system.

K1.12 Emergency condensate transfer pump: FWCI/HPCI Clinton is a BWR 6 and does not utilize this system.

K1.16 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K2.02 Feedwater coolant injection (FWCl) initiation logic:

Clinton is a BWR 6 and does not utilize this system.

FWCI/HPCI K3.03 Rod worth minimizer: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.02 Bypassing of the RWM: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.07 TDRFP 20% power interlock: TDRFP Clinton does not utilize this function.

1K4.15 Automatic initiation of the feedwater system upon Clinton is a BWR 6 and does not utilize this system.

receipt of an ECCS initiation signal: FWCI/HPCI 1K4.16 Dedication of feedwater string(s) to ECCS: FWCI/HPCI Clinton is a BWR 6 and does not utilize this system.

K5.08 Heat removal mechanisms: FWCI Clinton is a BWR 6 and does not utilize this system.

K5.09 Adequate core cooling: FWCl Clinton is a BWR 6 and does not utilize this system.

K6.07 Drywell pressure input: FWCI Clinton is a BWR 6 and does not utilize this system.

261000 Standby Gas Treatment System A1.05 Primary containment oxygen level: Mark-I&Il Clinton is a BWR 6 and does not utilize this configuration.

3/7/02 System #

Page 19 of 26

System #

System / Evolution Name KA #

KA Statement A1.06 Drywell and suppression chamber differential pressure:

Mark-I A4.05 Drywell to suppression chamber/torus differential pressure: Mark-l,Il K1.06 High pressure coolant injection system: Plant-Specific K3.03 Primary containment pressure: Mark-I&ll K3.04 High pressure coolant injection system: Plant-Specific K3.06 Primary containment oxygen content: Mark-I&ll 2002 Basis For Suppression Clinton is a BWR 6 and does not utilize this configuration.

Clinton is a BWR 6 and does not utilize this configuration.

Uninterruptable Power Supply (A. C./D. C.)

A1.02 Motor generator outputs A2.04 Abnormal battery operation: BWR-1 K1.04 Reactor manual control: Plant-Specific K1.07 Rod worth minimizer: Plant-Specific K1.09 Drywell ventilation control: Plant-Specific K1.10 Fire protection system: Plant-Specific K1.13 Recirculation pump speed control: Plant-Specific K1.15 Stack gas monitors: Plant-Specific K1.20 Plant communications equipment: Plant-Specific K3.02 Recirculation pump speed: Plant-Specific K3.04 Fire protection system: Plant-Specific K3.05 Rod worth minimizer: Plant-Specific K3.09 Drywell ventilation control: Plant-Specific K5.02 General principles of motor generator operation: Plant Specific K5.03 General principles of inertia fly wheel operation: Plant Specific 4000 Emergency Generators (Diesel/Jet) 26.,

26.

Gas generator temperature: Plant-Specific A1.08 Gas generator speed: Plant-Specific K2.03 Turning gear (jet engine): Plant-Specific K2.04 Ignition system (jet engine): Plant-Specific K6.04 Turning gear (jet engine): Plant-Specific K6.05 Ignition system (jet engine): Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

Clinton is a BWR-6 and does not utilize this feature.

Clinton is a BWR 6 and does utilize this configuration.

Clinton does not use jet engines to power emergency generators.

3/7/02 Page 20 of 26 A1.07

System #

System /Evolution Name KA #

KA Statement Basis For Suppression 271000 Offgas System A2.07 Low oxygen injection flow: Plant-Specific Clinton does not utilize this function.

K1.08 Oxygen injection system: Plant-Specific Clinton does not utilize this function.

K5.05 Oxygen concentration measurement Clinton does not utilize this function.

K6.06 Oxygen injection system: Plant-Specific Clinton does not utilize this function.

K6.13 Plant exhaust: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

272000 Radiation Monitoring System A2.07 Hydrogen injection operation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

A3.11 Circulating water system blowdown isolations: Plant-Clinton is a BWR 6 and does not utilize this system.

Specific K1.06 Reactor building ventilation system: Plant-Specific Clinton is a BWR 6 and does not utilize this configuration.

K1.07 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.12 Reactor building Clinton is a BWR 6 and does not utilize this system.

K1.15 Filter building: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K5.01 Hydrogen injection operation's effect on process Clinton is a BWR 6 and does not utilize this system.

radiation indications: Plant-Specific 286000 Fire Protection System A2.04 Applicable component cooling water system failure:

The only component cooled is the Fire Pumps which Plant-Specific are self cooled.

A4.02 Applicable component cooling water system: Plant-The only component cooled is the Fire Pumps which Specific are self cooled.

A4.03 Applicable component cooling water pressure The only component cooled is the Fire Pumps which are self cooled.

K1.01 Component cooling water systems The only component cooled is the Fire Pumps which are self cooled.

K1.02 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.06 Auxiliary (boiler) steam system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.08 Intake canals: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K5.08 Gas refrigeration: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K6.03 Applicable component cooling water system: Plant-The only component cooled is the Fire Pumps which Specific are self cooled.

288000 Plant Ventilation Systems K3.02 Reactor building temperature: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K3.05 Reactor building pressure: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

290001 Secondary Containment K1.01 Reactor building ventilation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.08 Exhaust stack: BWR-2, 3, 4 Clinton is a BWR 6 and does not utilize this system.

K1.10 Auxiliary boiler system: BWR-2, 3,4 Clinton is a BWR 6 and does not utilize this system.

3/7/02 Page 21 of 26

System #

System/ Evolution Name KA #

KA Statement K5.01 Vacuum breaker operation: BWR-4 K5.02 Flow measurement: BWR-3 K6.01 Reactor building ventilation: Plant-Specific K6.07 Auxiliary boiler system: BWR-3, 4 Basis For Suppression Clinton is a BWR 6 and does not utilize this configuration.

Clinton is a BWR 6 and does not utilize this configuration.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not have this configuration 290002 Reactor Vessel Internals K1.04 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.07 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K6.10 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K6.12 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

290003 Control Room HVAC K1.02 Chlorine amonia detectors: Plant-Specific Clinton does not utilize this component.

294001 2.2.3 (multi-unit) Knowledge of the design, procedural, and Clinton is a single-unit facility.

operational differences between units.

2.2.4 (multi-unit) Ability to explain the variations in control Clinton is a single-unit facility.

board layouts, systems, instrumentation and procedural actions between units at a facility.

295001 AA1.0 AA1.0 AK2.0 AK2.0 295002 AK3.0 295003 AK2.0 AK3.0 Partial or Complete Loss of Forced Core Flow Circulation 3

RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

8 Standby liquid control: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

5 LPCI loop select logic: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

8 Standby liquid control: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

i8

'5 7

Loss of Main Condenser Vacuum Recirculation system run-backs: Plant-Specific Partial or Complete Loss of A.C. Pow Isolation condenser. Plant-Specific Initiation of isolation condenser: Plant-Specific Clinton does not utilize this function.

er Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

295004 Partial or Complete Loss of D.C. Power AK1.01 Automatic load shedding: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

5005 Main Turbine Generator Trip AK2.09 Feedwater-HPCI: BWR-2 AK3.08 Feedwater-HPCI actuation: BWR-2 Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

3/7/02 29.

Page 22 of 26

System # -

Sy stemn/Evolution Name-KA Statement High Reactor Pressure Isolation condenser: Plant-Specific HPCI: Plant-Specific Isolation condenser operation: Plant-Specific HPCI operation: Plant-Specific Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

295008 High Reactor Water Level AA1.04 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK1.04 Containment integrity: Alis-Chalmers Clinton is a BWR 6 and does not utilize this system.

AK2.05 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK3.05 HPCI turbine trip: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

295010 High Drywell Pressure AA1.03 Nitrogen makeup: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AA2.04 Drywell humidity: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK1.01 Downcomer submergence: Mark-I&ll Clinton is a BWR 6 and does not utilize this system.

AK2.02 Drywellf/suppression chamber differential pressure:

Clinton is a BWR 6 and does not utilize this system.

Mark-I&ll AK2.04 Nitrogen makeup system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK3.06 Termination of drywell inerting: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

295011 High Containment Temperature (Mark II Containment Only)

AA2.03 Containment humidity: Mark-Ill Clinton does not utilize humidity monitoring instrumentation for the containment.

295012 High Drywell Temperature AA2.03 Drywell humidity: Plant-Specific Clinton does not utilize humidity monitoring instrumentation for the containment.

295014 Inadvertent Reactivity Addition AA1.03 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK1.01 Prompt critical Prompt criticality is addressed during fundamental training only.

AK2.08 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Incomplete SCRAM RMCS: Plant-Specific Rod worth minimizer: Plant-Specific RSCS: Plant-Specific RMCS: Plant-Specific Rod worth minimizer: Plant-Specific RSCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this component.

Clinton is a BWR-6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this component.

Clinton is a BWR-6 and does not utilize this system.

Page 23 of 26 KS #

295007 AA1.01 AA1.02 AK3.01 AK3.02 295015 AA1.03 AA1.05 AA1.06 AK2.02 AK2.05 AK2.06 3/7/02

System lEvolution Name KA #

KA Statement AK2.09 RPIS Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

295016 Control Room Abandonment AA1.09 Isolation/emergency condenser(s): Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AA2.07 Suppression chamber pressure Clinton is a BWR 6 and does not utilize this system.

295019 Partial or Complete Loss of Instrument Air AK2.13 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK2.17 High pressure coolant injection: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

295020 Inadvertent Containment Isolation AK2.05 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK2.06 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK2.08 Traversing in-core probes: Plant-Specific Clinton is a BWR 6 and Traversing In-Core Probes are inside Primary Containment.

AK3.08 Suppression chamber pressure response Clinton is a BWR 6 and does not utilize this system.

295022 Loss of CRD Pumps AK2.06 Shared components with other units: Plant-Specific Clinton is a single unit plant.

295023 Refueling Accidents AK3.05 Initiation of SLC/shut-down cooling: Plant-Clinton is a BWR-6 and does not utilize this feature.

Specific(BWR-1) 295024 High Drywell Pressure EA1.01 HPCI (FWCI): Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EAM.11 Drywell spray: Mark-I&ll Clinton is a BWR 6 and does not utilize this system.

EA1.12 Suppression pool spray: Mark-I&lI Clinton is a BWR 6 and does not utilize this system.

EA1.21 Recirculation system (LPCI loop select logic): Plant-Clinton is a BWR 6 and does not utilize this system.

Specific EA2.04 Suppression chamber pressure: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EA2.05 Suppression chamber air-space temperature: Plant-Clinton is a BWR 6 and does not utilize this system.

Specific EK2.01 HPCI (FWCI): Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.11 Drywell spray (RHR) logic: Mark-I&ll Clinton is a BWR 6 and does not utilize this system.

EK2.13 Suppression pool spray: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.17 Auxiliary building isolation logic: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK3.01 Drywell spray operation: Mark-l&ll Clinton is a BWR 6 and does not utilize this system.

EK3.02 Suppression pool spray operation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK3.09 Auxiliary building isolation: Plant-Specific.

Clinton is a BWR 6 and does not utilize this system.

295025 High Reactor Pressure IA1.04 HtI-'I: Plant-Specitic

'

3/7/02 Clinton is a BWR 6 and does not utilize this system.

Page 24 of 26 System #

System #

System /IEvolution Name KA Statement Isolation condenser: Plant-Specific RRCS: Plant-Specific Isolation condenser: Plant-Specific RRCS: Plant-Specific HPCI: Plant-Specific HPCI operation: Plant-Specific Isolation condenser initiation: Plant-Specific RRCs initiation: Plant-Specific 295026 Suppression Pool High Water Temperature EA1.02 Suppression pool spray: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.02 Suppression pool spray: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.03 Suppression chamber pressure: Mark-I&ll Clinton is a BWR 6 and does not utilize this system.

EK3.03 Suppression pool spray: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

295028 High Drywell Temperature EA1.01 Drywell spray: Mark-I&ll Clinton is a BWR 6 and does not utilize this system.

EA2.05 Torus/suppression chamber pressure: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EA2.06 Torus/suppression chamber air space temperature:

Clinton is a BWR 6 and does not utilize this system.

Plant-Specific EK2.01 Drywell spray: Mark-I&ll Clinton is a BWR 6 and does not utilize this system.

EK3.03 Drywell spray operation: Mark-l&ll Clinton is a BWR 6 and does not utilize this system.

295029 High Suppression Pool Water Level EA1.01 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.02 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

295030 Low Suppression Pool Water Level EA.1.05 HPCI Clinton is a BWR 6 and does not utilize this system.

EA2.04 Drywell/ suppression chamber differential pressure:

Clinton is a BWR 6 and does not utilize this system.

Mark-I&Il EK2.01 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK3.02 HPCI operation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

295031 Reactor Low Water Level EA1.02 High pressure (feedwater) coolant injection: Plant-Clinton is a BWR 6 and does not utilize this system.

Specific EA1.09 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.06 High pressure (feedwater) coolant injection Clinton is a BWR 6 and does not utilize this system.

(FWCI/HPCI): Plant-Specific 295035 Secondary Containment High Differential Pressure EK2.04 Blow-out panels: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

3/7/02 Page 25 of 26 Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

Clinton is a BWR 6 and does not utilize this system.

KA #

EA1.06 EA1.08 EK2.02 EK2.03 EK2.06 EK3.03 EK3.04 EK3.07

System #

System / Evolution Name KA #

KA Statement EK3.01 Blow-out panel operation: Plant-Specific Basis For Suppression Clinton is a BWR 6 and does not utilize this system.

295037 SCRAM Condition Present and Reactor Power Above APRM Downsc EA1.02 RRCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EA1.07 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.02 RRCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.11 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.14 RPIS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

295038 High Off-Site Release Rate EA1.05 Post accident sample system (PASS): Plant-Specific The PASS system is not operated nor monitored by licensed operators at Clinton.

300000 Instrument Air System (LAS)

K1.01 Sensor air Clinton is a single unit plant which does use this configuration.

K2.02 Emergency air compressor Clinton does not utilize this component.

K3.03 Cross-tied units Clinton is a single unit plant which does use this configuration.

K5.04 Service air refusal valve Clinton does not utilize this component.

K6.04 Service air refusal valve Clinton is a single unit plant which does use this configuration.

500000 High Containment Hydrogen Concentration EA1.05 Wetwell sprays Clinton is a BWR 6 and does not utilize this system.

EA1.06 Drywell sprays Clinton is a BWR 6 and does not utilize this system.

EA1.07 Nitrogen purge system Clinton is a BWR 6 and does not utilize this system.

EA2.04 Combustible limits for wetwell Clinton is a BWR 6 and does not utilize this system.

EK2.06 Wetwell Spray system Clinton is a BWR 6 and does not utilize this system.

EK2.08 Wet Well vent system Clinton is a BWR 6 and does not utilize this system.

EK2.09 Drywell nitrogen purge system Clinton is a BWR 6 and does not utilize this system.

EK3.05 Operation of wet well (suppression pool) sprays Clinton is a BWR 6 and does not utilize this system.

EK3.06 Operation of wet well vent Clinton is a BWR 6 and does not utilize this system.

EK3.08 Operation of drywell nitrogen purge system Clinton is a BWR 6 and does not utilize this system.

E xam D eveloper P e N m atur

/ate7

- O Facility Representative rntd¢ -)ae

'V?*Zi (("

_______'ate Printed Name Date 3/7/0 P_ g 26 f26 317102 Pag-e 26 of 26

March 20, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

Dear Mr. Skolds:

In a telephone conversation on March 14, 2002, between Mr. D. Pelton, NRC, and Mr. R. Price, Clinton, arrangements were made for the administration of licensing examinations at the Clinton Power Station the weeks of July 29, 2002, and August 5, 2002. In addition, the NRC will make an examination validation visit to your facility the week of June 24, 2002.

As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in Revision 8, Supplement 1, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The NRC regional office will discuss with your staff any changes that might be necessary before the examinations are administered.

To meet the above schedule, it will be necessary for your staff to furnish the examination outlines by April 25, 2002. The written examinations, operating tests, and the supporting reference materials identified in Attachment 2 of ES-201 will be due by May 28, 2002. Pursuant to 10 CFR 55.40(b)(3), an authorized representative of the facility licensee shall approve the outlines, examinations, and tests before they are submitted to the NRC for review and approval.

All materials shall be complete and ready to use. Any delay in receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled.

In order to conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final.

Appendix E of NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered.

To permit timely NRC review and evaluation, your staff should submit preliminary reactor operator and senior reactor operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024),

M/-

0-o0ogoo730

J. Skolds and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.

This letter contains information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the Office of Management and Budget, approval number 3150-0018, which expires on April 30, 2003.

The public reporting burden for this collection is estimated to average 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per response, including the time for reviewing instructions, gathering and maintaining the data needed, writing the examinations, and completing and reviewing the collection of information. Send comments on any aspect of this collection of information, including suggestions for reducing the burden, to the Information and Records Management Branch (T-6 F33), U.S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001, or by Internet electronic mail at BJS1 @NRC.GOV; and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-1 0202, (3150-0018), Office of Management and Budget, Washington, D.C. 20503.

The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number.

Thank you for your cooperation in this matter. Mr. Price has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the NRC's examination procedures and guidelines, please contact David Pelton at 630-829-9732, or me at 630-829-9733.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.qov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

cerely,

,/*-"./'/

David E. Hills, Chief Operations Branch Division of Reactor Safety Docket No. 50-461 License No. NPF-62 See Attached Distribution DOCUMENT NAME: G:DRS\\Cli03_O2DRS.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachmentfenclosure "E" = Copy with attachmentlenclosure "N" No copy OFFICE Rill RI I II NAME DLPelton:sd DEHiIls M-1 H

DATE 03/0P/02 03/u/02 OFFICIAL RECORD COPY J. Skolds Distribution cc:

J. Heffley, Vice President W. Bohlke, Senior Vice President Nuclear Services J. Cotton, Senior Vice President Operations Support M. Pacilio, Plant Manager K. Ainger, Director - Licensing C. Crane, Senior Vice President Mid-West Regional Operating Group J. Benjamin, Vice President - Licensing And Regulatory Affairs R. Hovey, Operations Vice President R. Helfrich, Senior Counsel, Nuclear Mid-West Regional Operating Group W. Illiff, Regulatory Assurance Manager Document Control Desk-Licensing Illinois Department of Nuclear Safety F. Tsakeres, Training Department ADAMS Distribution:

DCT AJM DFT JBH1 RidsNrrDipmlipb GEG HBC PLL DRPIII DRSIII PLB1 JRK1 M. A. Bies (Concurrence Copy)

AmerGen An Exelon/British Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 Phone: 217 935-8881 U-603556 May 23, 2002 Mr. James E. Dyer Regional Administrator U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Clinton Power Station, Unit 1 Facility Operating License Nos. NPF-62 NRC Docket Nos.50-461

Subject:

Submittal of Integrated Initial License Training Examination Materials

Reference:

Letter from D. Hills (U.S. NRC) to J. Skolds (Exelon Generation Company, LLC) dated March 20, 2002 Enclosed are the examination materials which AmerGen Energy Company (AmerGen),

LLC is submitting in support of the Initial License Examination scheduled for the weeks of July 29, 2002 and August 5, 2002 at Clinton Power Station. This submittal includes the Senior Reactor Operator and Reactor Operator Written Examinations, Job Performance Measures, and Integrated Plant Operation Scenario Guides.

These examination materials have been developed in accordance with NUREG-1021, "Operator Licensing Examination Standards," Revision 8, Supplement 1. Please note that reference materials are attached to each individual examination question or item.

Some minor modifications have been made to the Integrated Examination Outline with regard to the operational scenarios in order to improve balance and content. These changes improve examination quality and are in compliance with NUREG-1021.

In accordance with NUREG-1021, Section ES-201, 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. Bill Iliff at (217) 937-2800. For questions concerning examination materials, please contact Mr.

Robert Price at (217) 937-4135.

Repectfully, Michael J. Pacilio Plant Manager Clinton Power Station

May 23, 2002 U.S. Nuclear Regulatory Commission Page 2 of 2 EET/blf Attachments: (Hand delivered to Mr. David Pelton, Chief Examiner, NRC Region Ill)

RO/SRO Composite Examination (with references attached)

Control Room Systems and Facility Walk-Through Job Performance Measures (with references attached)

Administrative Topic Job Performance Measures (with references attached)

Integrated Plant Operation Scenario Guides Completed Checklists:

Operating Test Quality Checklist (Form ES-301-3)

Simulator Scenario Quality Checklist (Form ES-301-4)

Transient and Event Checklist (Form ES-301-5)

Competencies Checklist (Form ES-301-6)

Written Exam Quality Checklist (Form ES-401-7)

Record of Rejected K/As (Form ES-401-10)

Examination Security Agreements (Form ES-201-3) cc:

NRC Senior Resident Inspector - Clinton Power Station (w/o attachments)

Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety (w/o attachments)

Amer en An Exelon/British Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 U-603566 July 11, 2002 Mr. James E. Dyer Regional Administrator U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Clinton Power Station, Unit 1 Facility Operating License Nos. NPF-62 NRC Docket Nos.50-461

Subject:

Final Submittal of Integrated Initial License Training Examination Materials

Reference:

Letter from D. Hills (U.S. NRC) to J. Skolds (Exelon Generation Company, LLC) dated March 20, 2002 Enclosed are the examination materials which AmerGen Energy Company (AmerGen), LLC is submitting in support of the Initial License Examination scheduled for the weeks of July 29, 2002 and August 5, 2002 at Clinton Power Station. This submittal includes the Senior Reactor Operator and Reactor Operator Written Examinations, Job Performance Measures, and Integrated Plant Operation Scenario Guides.

These examination materials have been developed in accordance with NUREG-1 021, "Operator Licensing Examination Standards," Revision 8, Supplement 1. Please note that reference materials are attached to each individual examination question or item-Some minor modifications have been made to the Integrated Examination Outline with regard to the operational scenarios in order to improve balance and content. These changes improve examination quality and are in compliance with NUREG-1021.

In accordance with NUREG-1 021, Section ES-201, 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. Bill Iliff at (217) 937-2800. For questions concerning examination materials, please contact Mr. Robert Price at (217) 937-4135.

Re ctfull Michael J. Pacilio Site Vice President Clinton Power Station

U.S. Nuclear Regulatory Commission Page 2 of 2 EET/blf Attachments: (Hand delivered to Mr. David Pelton, Chief Examiner, NRC Region Ill)

RO/SRO Composite Examination (with references attached)

Control Room Systems and Facility Walk-Through Job Performance Measures (with references attached)

Administrative Topic Job Performance Measures (with references attached)

Integrated Plant Operation Scenario Guides Completed Checklists:

Operating Test Quality Checklist (Form ES-301-3)

Simulator Scenario Quality Checklist (Form ES-301-4)

Transient and Event Checklist (Form ES-301-5)

Competencies Checklist (Form ES-301-6)

Written Exam Quality Checklist (Form ES-401-7)

Record of Rejected K/As (Form ES-401-10)

Examination Security Agreements (Form ES-201-3) cc:

NRC Senior Resident Inspector-Clinton Power Station (w/o attachments)

Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety (w/o attachments)

U-603566

Subject:

Final Submittal of Integrated Initial License Training Examination Materials bcc:

Clinton Power Station Project Manager - NRR (w/o attachments)

USNRC Document Control Desk (w/o attachments)

M. J. Pacilio, V-275 (w/o attachments)

K. J. Poison, T-31A (w/o attachments)

W. S. Iliff, T-31A (w/o attachments)

F. S. Tsakeres, V-922 (w/o attachments)

T. J. Shortell, V-922 (w/o attachments)

R. L. Price, V-922 (w/o attachments)

Nuclear Safety Review Board Coordinator (R. Frantz), T-31J (w/o attachments)

Document Control Desk Licensing (Hard Copy - w/o attachments)

Document Control Desk Licensing (Electronic Copy - w/o attachments)

AmerGen An Exelon/British Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 Phone: 217 935-8881 U-603574 August 13, 2002 Mr. James E. Dyer Regional Administrator Region III U.S Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60632-4351 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket Number 50-461

Subject:

Comments Regarding Initial License Operator Examination Questions Administered on August 8, 2002 This letter is to request that credit be given for a second answer for questions #22, #32, #42 and #48 from the Initial License Operator Examination administered on August 8, 2002.

Enclosed are the questions and associated documentation that justifies this request.

If you should have any questions concerning this matter you may reach Mr. T. J. Shortell at (217) 937-4001 or Mr. M. J. Carey at (217) 937-4038.

Sincerely, W. S. I f IV Regulatory Assurance Manager EET/blf Enclosure cc:

NRC Senior Resident Inspector - Clinton Power Station

U-603574 August 13, 2002

SUBJECT:

Comments Regarding Initial License Operator Examination Questions Administered on August 8, 2002 bcc:

Clinton Power Station Project Manager - NRR Director - Licensing, Mid-West Regional Operating Group Manager - Licensing, Clinton Power Station (MWROG)

Document Control Desk Licensing (Hard Copy)

Document Control Desk Licensing (Electronic Copy)

NSRB Coordinator, T-31J

Clinton Power Station 2002 NRC Written Exam RECORD #22 QUESTION #22 - RO EXAM QUESTION #21 - SRO EXAM Discussion At the Clinton Power Station a DBA LOCA is a double ended shear of the Reactor Recirculation System suction piping. During this event, the steam/water energy that is released into the Drywell passes through the Suppression Pool Horizontal Vents where the majority of the steam is condensed by the Primary Containment's Suppression Pool.

Due to incomplete condensation by the Suppression Pool and potential for Drywell bypass leakage, steam may also be present in the Primary Containment. As the pressure in the Primary Containment increases, the Emergency Operating Procedures, EOP Primary Containment Control directs the operators to initiate Containment sprays (RHR Containment Spray mode) to prevent exceeding the Pressure Suppression Pressure limit.

The RHR Containment Spray mode reduces containment pressure by discharging Suppression Pool water through spray headers. This spray condenses any steam present in the Primary Containment (LP85205, revision 5, page 44). In CPS 3312.01, revision 35, page 19, these spray headers are referred to as "Containment Spray Spargers."

At CPS, the High Pressure Core Spray system, Low Pressure Core Spray system, Residual Heat Removal system and the Safety Relief Valves all contain components termed "spargers." Choice B does not specify which spargers.

The Horizontal Vents and the Residual Heat Removal System Containment Spray Spargers both promote steam condensation during a DBA LOCA. Since choice B did not specify which sparger, both A & B are correct.

Recommendation/Justifi cation Accept both answers A & B as a correct answer.

Clinton Power Station 2002 NRC Written Exam RECORD #32 QUESTION #32 - RO EXAM QUESTION #31 - SRO EXAM Discussion The Component Cooling Water (CCW) system cools the Reactor Water Cleanup (RT) Non Regenerative Heat Exchanger. At 90% reactor power, a leaking tube in the Non-Regenerative Heat Exchanger would cause primary coolant to enter the CCW system. The CCW system is a closed loop cooling water system that circulates water throughout the plant (LP85204, revision 4, figure 1).

Activity in the primary coolant that enters the CCW system will be circulated throughout the system. This will cause radiation levels to increase in areas where CCW system piping is located.

The increase in area radiation levels will be noted through RP surveys and possible alarm(s) in the Area Radiation/Process Radiation (AR/PR) system. Either of these conditions is a symptom for entry into Abnormal High Area Radiation Levels, CPS 4979.02 (4979.02, revision 7, page 2).

Therefore, a leaking tube in the Non-Regenerative Heat Exchanger will result in both IRIX PR037 alarm with entry into 4979.05, and increasing radiation levels in the plant, with entry into Abnormal High Area Radiation Levels, CPS 4979.02.

The second part of the question asks which procedure is used to control the consequences of this failure. In both 4979.05, revision 7, page 5 and in 4979.02, revision 7, page 2 the following subsequent operator actions are directed:

Take appropriate actions necessary to isolate, reduce or terminate the cause and consequences of the abnormal area [liquid for 4979.05]

radioactivity (e.g., re-aligning systems, securing heat exchangers, isolating system leaks).

Recommendation/Justification Accept both answers B & D as a correct answer.

Clinton Power Station 2002 NRC Written Exam RECORD #42 QUESTION #42 - RO EXAM QUESTION #40 - SRO EXAM Discussion Water transfer to Radwaste with RHR in Shutdown Cooling (SDC) occurs durng startup of RHR for SDC and when rejecting water to control RPV level. Prior to placing a RHR loop in SDC, the RHR loop must be flushed with Cycle Condensate (M05-1075, sheets 1 & 2) and warmed with Reactor Pressure Vessel water if not in Mode 4 or 5. The water from either case is directed to the Radwaste Surge Tank (M05-1076).

RHR A loop requires manual valve manipulation when transferring water to Radwaste. This manual valve operation can result in increased exposure to local operators. Operation of either RHR A or RHR B can increase radiation levels in the general area of the RHR cubicles.

Radiation Protection should be notified to conduct surveys as soon as possible (CPS 3312.01, revision 35, page 4).

Due to the physical layout of the RHR A loop, warming is limited by the discharge temperature to Radwaste (120 'F), which may not result in a complete elimination of thermal shock and differential expansion of the RHR pump and Heat Exchanger. (CPS 3312.03, revision 3d, page 27). This limitation is not in affect when placing RHR Loop B in SDC (CPS 3312.03, revision 3d, page 16) due to different physical layout. The drain tap for RHR A loop is between the RHR Pump A discharge and the RHR A Heat Exchanger. The drain tap for the RHR B loop is downstream of the RHR B Heat Exchanger (M05-1075, sheets 1 & 2; M05-1076 sheet 4; and M05-1085, sheet 1).

The question did not specify whether the water transfer occurred during warmup or reject.

During warmup, both ALARA and high temperature are a concern.

Recommendation/Justification Accept both answers B & C as a correct answer.

Clinton Power Station 2002 NRC Written Exam RECORD #48 QUESTION #48 - RO EXAM QUESTION #46 - SRO EXAM Discussion At 90% Reactor Power, a TDRFP trip causes a reduction in feed water flow that results in a decrease in Reactor Pressure Vessel (RPV) water level. RPV level drops below the RPV level 4 setpoint (30.8"), but should remain above the RPV level 3 Reactor Scram setpoint of 8.9".

During plant operation, if a Turbine Driven Reactor Feed Pump (TDRFP) trips and RPV level lowers to programmed Level 4, the Reactor Recirculation Flow Control Valve (RR FCVs) will partially close (runback) to -19% indicated open and a core flow of-42.25 mlbm/hr (CPS 4008.01, revision 18, page 4). The purpose of the runback is to reduce reactor power to within the capacity of one TDRFP. Assuming the plant is operating on the 100% rod line, the FCVs runback would result in a final steady state reactor power of-65% and RPV water level of approximately 34".

During the initial part of the feedwater transient the RPV level will decrease due to the steam flow/feed flow mismatch. This reduction in RPV level will cause carry under to increase and RPV downcomer subcooling to decrease (LP87570, revision 1, page 14; BWR Thermodynamics Chapter 8, Thermal Hydraulics, page 8). In addition, when the RR FCVs runback occurs, mass flow rate through the core is reduced.

The power level (Critical Power) required to achieve the Onset of Transition Boiling (OTB) somewhere in the bundle decreases as the inlet subcooling decreases. Critical Power also decreases with a reduction in core flow (BWR Thermodynamics Chapter 8, Thermal Hydraulics, page 13).

Therefore, during a TDRFP trip transient that results in lowering RPV level, the power level required to achieve the Onset of Transition Boiling is less. Thus, the margin to transition boiling is reduced during the transient.

Recommendation!Justification Accept both answers C & D as a correct answer.

Amer Gvei An Exelon/British Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 U-603575 August 13, 2002 Mr. David Hills Chief, Operations Branch Division of Reactor Safety U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

NRC Initial Examination Material By letters dated May 23, 2002 and July 11, 2002 (Letter Numbers U-603556 and U-603566),

the following Dynamic Simulator Scenarios and Reactor Operator Job Performance Measures (JPMs), and all supporting reference documentation, were submitted to the NRC for review and approval for use in the Clinton Power Station NRC Initial License Examination scheduled for the weeks of July 29, 2002 and August 5, 2002.

"* Dynamic Exam 6, ES-D-1, & ES-D-2

"* Dynamic Exam 7, ES-D-1, & ES-D-2

"* RO Administrative JPM A.1.A.3

"* RO Administrative JPM A.1.B.3

"* RO Administrative JPM A.2.3

"* RO Administrative JPM A.3.3

"* RO Administrative JPM A.4.3 These particular scenarios and JPMs were not selected for use during that examination. As a result, the Clinton Power Station staff request that these dynamic simulator scenarios and JPMs be withheld from public disclosure to allow for the potential use of the simulator scenarios and JPMs during future NRC Initial License Operator Examinations at Clinton Power Station.

The Clinton Power Station staff is hereby requesting, in accordance with IOCFR2.790, that the aforementioned dynamic simulator scenarios and JPMs contained in the May 23, 2002 and "05000461/LER-2002-002, Inadequate Preventive Maintenance Program for the Feedwater System Results in Lockup of a Turbine-Driven Reactor Feed Pump and Scram on High Reactor Pressure Vessel Water Level During Extended [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Testing|July 11, 2002 letter]]s be designated as proprietary information of AmerGen and be withheld from public disclosure. An affidavit for this action, pursuant to 1 OCFR2.790(a)(4) is contained in Attachment 1.

Auqust 13, 2002 U. S. Nuclear Regulatory Commission Page 2 of 2 If you require further clarification concerning these items, please contact Mr. T. J. Shortell, Operations Training Manager, at (217) 937-4001.

Respectfully, Regulatory Assurance Manager EET/blf Attachment cc:.Regional Administrator - NRC Region III (w/o Attachment)

NRC Lead Examiner, Mr. David Pelton NRC Senior Resident Inspector - Clinton Power Station (w/o Attachment)

Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety (w/o Attachment)

ATTACHMENT AFFIDAVIT FOR T. J. SHORTELL PAGE I OF 1 AFFIDAVIT 1, Thomas J. Shortell, being duly authorized and state as follows:

(1) I am the Operations Training Manager at Clinton Power Station, and have been delegated the function of reviewing the information described in paragraph 2 which is sought to be withheld, and have been authorized to apply for it withholding. The information sought to be withheld is Dynamic Simulator Scenarios, Dynamic Exam 6, ES-D-1, & ES-D-2 and Dynamic Exam 7, ES-D-1,. & ES-D-2 and, Reactor Operator Job Performance Measure RO Administrative JPM A.1.A.3, RO Administrative JPM A.I.B.3, RO Administrative JPM A.2.3, RO Administrative JPM A.3.3, and RO Administrative JPM A.4.3.

(2) These scenarios and JPMs and all supporting reference materials were submitted to the NRC for review and approval for use in the Clinton Power Station NRC Initial License Examination scheduled for the weeks of July 29, 2002 and August 5, 2002. The scenarios and JPMs and supporting reference materials are contained in two letters dated May 23, 2002 and July 11, 2002 (Letter Numbers U-603556 and U-603566),

(3) The information sought to be withheld was submitted to the NRC in confidence. The information is of a sort customarily held in confidence by AmerGen. The information sought to be withheld has, to the best of my knowledge, consistently been held in confidence by AmerGen, no public disclosure has been made, and is not available in public sources.

(4) Public disclosure of the information sought to be withheld is likely to cause harm to AmerGen in that there would be measurable investment in time and money to produce new examination scenarios and JPMs. Furthermore, the use of examination scenarios and JPMs that were unknowingly available in the public domain could adversely impact the integrity of licensed operator examination process described within 10CFR55, and as implemented by AmerGen.

Thomas J. Shortell, hereby affirms:

That I have read the foregoing affidavit and the matters therein are true and correct to the best of my knowledge, information, and belief.

Executed at 01/no^, a--

this /1-day of 4

-L,2002 Subscribed and affirmed before me this _Jay of 2002 "OFF[ICI.AL SEALU Jacqueline S. Matthias Notary Public, State of Illinois My Commission Exp. 11/24/2005

September 10, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

REQUEST TO WITHHOLD DYNAMIC SIMULATOR SCENARIOS AND JOB PERFORMANCE MEASURES FROM PUBLIC DISCLOSURE

Dear Mr. Skolds:

By letter dated August 13, 2002, Mr. W. Iliff, Regulatory Assurance Manager from your Clinton Power Station, requested that the NRC withhold from public disclosure certain material from a recently administered initial license exam. Specifically, Mr. Iliff requested that dynamic scenarios 6 and 7 as well as reactor operator job performance measures A.1.A.3, A.1.B.3, A.2.3, A.3.3, and A.4.3, submitted to the NRC on May 28, 2002, be withheld from public disclosure. An affidavit (pursuant to 10 CFR 2.790) signed by Thomas J. Shortell, Operations Training Manager, was provided.

We have reviewed Mr Iliff's request and concluded that this material was not used during the July/August, 2002 initial license examination administered at your Clinton Power Station.

Therefore, we see no regulatory need to maintain these documents or to make these documents publically available. In a telephone conversation between myself and Mr. T.

Shortell, Operations Training Director from your Clinton Power Station, we agreed to destroy all documentation of the above examination material.

If you have any questions regarding this matter, please contact me at 630-829-9732.

In accordance with 10 CFR Part 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/readinq-rm/adams.html (the Public Electronic Reading Room).

Sincerely, David L. Pelton, Acting Chief Operations Branch Division of Reactor Safety Docket No. 50-461 License No. NPF-62 See Attached Distribution oq/OoQ DOCUMENT NAME:G:\\DRS\\Cli 8--O2drs.wpd

See Previous Concurrence

/

S) 410 6 "receive a con. of this document indicate In the box: "C" = CoDV without attachmentienclosure "E" = Copy with attachment/enclosure "N" = No copy DPelton '4

/10

/02 OFFOCE RFIL Ri CO RC NAME DPelton:jb AMStone BBerson DATE 08/29/02 108129/02 09/09/02 OFFICIAL RECORD COPY

Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

REQUEST TO WITHHOLD DYNAMIC SIMULATOR SCENARIOS AND JOB PERFORMANCE MEASURES FROM PUBLIC DISCLOSURE

Dear Mr. Skolds:

By letter dated August 13, 2002, Mr. W. Iliff, Regulatory Assurance Manager from your Clinton Power Station, requested that the NRC withhold from public disclosure certain material from a recently administered initial license exam. Specifically, Mr. Iliff requested that dynamic scenarios 6 and 7 as well as reactor operator job performance measures A.1.A.3, A.1.B.3, A.2.3, A.3.3, and A.4.3, submitted to the NRC on May 28, 2002, be withheld from public disclosure.

We have reviewed Mr Iliff's request and concluded that this material was not used during the July/August, 2002 initial license examination administered at your Clinton Power Station.

Therefore, we see no regulatory need to maintain these documents or to make these documents publically available. In a telephone conversation between myself and Mr. T.

Shortell, Operations Training Director from your Clinton Power Station, we agreed to destroy all documentation of the above examination material.

If you have any questions regarding this matter, please contact me at 630-829-9732.

In accordance with 10 CFR Part 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.qov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely, David L. Pelton, Acting Chief Operations Branch Division of Reactor Safety Docket No. 50-461 License No. NPF-62 See Attached Distribution DOCUMENT NAME:G:\\DRS\\Cli 08 To receive a copy of this document, Indicate in the box iC" FIOFFICE IRIII INIRI

J. Skolds cc:

Site Vice President - Clinton Power Station Clinton Power Station Plant Manager Regulatory Assurance Manager - Clinton Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Clinton and LaSalle Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing ADAMS Distribution:

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