U-603625, Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004

Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004

ML041140184
Person / Time
Site:	Clinton
Issue date:	01/06/2004
From:	Pickley T Exelon Generation Co, Exelon Nuclear
To:	Office of Nuclear Reactor Regulation
References
50-461/04-301, U-603625 50-461/04-301
Download: ML041140184 (61)

Text

EXAMINATION OUTLINE SUBMITTAL WITH NRC COMMENTS FOR THE CLINTON INITIAL EXAMINATION - JANUARY 2004

AmerGen An ExelodBritish Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 Phone: 217 935-8881 U-603625 July 10, 2003 Mr. James E. Dyer Regional Administrator 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:

Submittal of Integrated Initial License Training Examination Outline Enclosed are the examination outlines which Amergen Energy Company (AmerGen), LLC is submitting in support of the Initial License Examination scheduled for the weeks of 1/5/2004 and 1/12/2004 at Clinton Power Station. This submittal includes the Senior Reactor Operator and Reactor Operator Written Examination Outlines, Job Performance Measures Outlines, Integrated Plant Operation Scenario Outlines and Clinton Power Station Suppressed WAS.

These examination outlines have been developed in accordance with NUREG-I 021, Operating Licensing Examination Standards, Draft Revision 9. In accordance with NUREG-I021, Section ES-201, Initial Operator Licensing Examination Process, please ensure that these materials are withheld from public disclosure until after the examinations are complete.

Should you have any questions related to this information, please contact Mr. Tom Pickley at (217) 937-4135.

Respectfully, William S. lliff Regulatory AssuranceY A anager Clinton Power Station EET/blf

July I O , 2003 U S . Nuclear Regulatory Commission Page 2 of 2 Attachments: (Hand delivered to NRC Region Ill Chief Examiner)

Examination Security Agreement (Form ES-201-3),

Administrative Topics Outline (Form ES-301-I),

Control Room/ln-Plant Systems Outline (Form ES-301-2),

BWR Examination Outline (Form ES-401-I),

Record of Rejected WAS (Form ES-401-4),

Operational Scenarios Outline (Form ES-D-1),

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

Outline Methodology for 2004 Clinton Power Station Written NRC Exam Clinton Power Station Suppressed WAS cc: R. S. Bement, V-275 (wlo Attachments)

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

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

K. A. McCall, V-922 (w/o Attachments)

L. T. Pickley, V-922 (w/o Attachments)

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facilit Item Task Description 1 ,initial;

( a ( b * ( c #

1.

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a. Venfy that the outline(s) fit(s) the appropriate model per ES-401. 1 LpI R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.l of ES-401 and whether all WA categories are appropriately sampled.

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c. Assess whether the outline over-emphasizesany systems, evolutions,or generic top;&.

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2.

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3.

the outline(s) contain(s) the required numb W no more than 30% of the test material is r I

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to implementan alternate path

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

4.

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d. Check for duplication and overlap among exam sections.

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e. Check the entire exam for balanceof coverage.

b. Facility Reviewer r)

c. NRC Chief Examiner (#)

d. NRC Supervisor Note: Not applicable for NRCdeveloped examinations.

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

NUREG-1021, Draft Revision 9 24 of 25

EXAMINATION OUTLINE QUALITY CHECKLIST ES-201-2

1. Minor error in attention to details. Identified three WAS which were suppressed in one part of the written examination Tier group, but not in another. In addition, several selected WAS (15) for the SRO only questions does not have specific 10 CFR 55.43 references. Remind licensee that these questions must exam on SRO responsibilities.

2. ES 301-5 shows that there is inadequate number of events for an SRO in the BOP position for scenario NRC 1-2. Although a normal evolution is noted for the BOP position, an SRO is not required to have a normal evolution as an RO. Given that the BOP also doe not have a reactivity for scenario NRC 1-2, an SRO standing only in the position of a BOP will not have sufficient credit of events (i.e., overall 3 C/I malfunction events). The scenario will require additional events.

3. Although approximately 30.4% (7 out of 23) of the total scenario malfunctions (not including reactivity or normal evolutions) are duplicated from the last NRC exam, they are not all assigned to just one scenario. The duplicated events are distributed between three submitted scenarios. It may require adjustments or modifications to lessen the potential of predictability.

4. Added enhancements may be required to include additional events and/or initial conditions for better discriminating value.

5. Excessive duplication (>30%)of Admin JPMs from last NRC exam. It will require modification and/or new JPMs.

NRC copy #1 ES-401 BWR Examination Outline Form ES-40 1- 1 d -

1 2 2 3 3

2. I I I I Plant 2 1 0 2 0 Systems Tier 3 2 5 3 Totals

3. Generic Knowledae and -

Abilities Categories 1 4 1 2 1 2 Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO Outline (i.e., the "Tier Totals" in each KIA category shall not beless than Lo). Refer to Section D.1.c for additional guidanceregarding SRO sampling.

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by k 1from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Select topics from many systems and evolutions; avoid selectingmore than two WA topics from a given system or evolution unless they relateto plant-specific priorities.

'W 4. Systemdevolutions within each group are identifiedon the associated outline.

5. The shaded areas are not applicable to the categoryhier.

6. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K" and "A". Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the KIA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

1

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant E K

.- - Ti

.ns

=

K UAPE #I Name I Safety Function WA Topic(s) IR #

ii 1 -

295001 Partial or Complete Loss of Forced 2.4.4 Ability to recognize abnormal 4.0 1 Core Flow Circulation I 1 & 4 indicationsfor system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. (CFR 41.10143.2 /45.6) --

295003 Partialor Complete Loss of ACI 6 AA1.04 Ability to operate andlor 3.6 1 monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: D.C. electrical distribution system (CFR 41.7 I 45.6) --

295004 Partial or Total Loss of DC Pwr I 6 AA1.02 Ability to operate andlor 3.8 1 monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Systems necessary to assure safe plant shutdown (CFR 41.7 145.6) --

295005 Main Turbine Generator Trip I 3 X AKI .02 Knowledge of the operational 3.2 1 implicationsof the following concepts as they apply to MAIN TURBINE GENERATOR TRIP: Core thermal limit considerations ( CFR 41.8 to 41.10) -

295006SCRAMIl

• j AA2.03 Ability to determine andlor 4.0 1 interpretthe following as they apply to SCRAM: Reactorwater level (CFR

41. I O 143.5) -

W 295016 Control Room Abandonment I 7 ,441.08 Ability to operate andlor 4.0 1 monitor the following as they apply to CONTROL ROOM ABANDONMENT:

Reactor pressure (CFR: 41.7 I 45.7) -

295018 Partialor Total Loss of CCW I8 AK2.02 Knowledge of the 3.4 1 interrelationsbetween PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:

Plant operations (CFR 41.7,45.8) --

t 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I 4 AA1.01 Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENTAIR: Backup air supply (CFR 41.7 145.6)

AK3.01 Knowledge of the reasons for the following responsesas they apply to LOSS OF SHUTDOWN COOLING:

Raising reactor water level (CFR 3.5 3.3 1

1 51.5 141.6) - -

295023 Refueling Acc Cooling Mode I 8 AA2.01 Ability to determine andlor 3.6 1 interpret the following as they apply to REFUELINGACCIDENTS: Area radiation levels (CFR: 41. I O 143.5 I 45.13) -

2

UAPE #I Name I Safety Function WA Topic(s) IR #

295024 High Drywell Pressure I5 EK3.08 Knowledge of the reasonsfor 3.7 1 the following responses as they apply to HIGH DRYWELL PRESSURE:

Containment spray: Plant Specific (CFR: 41.5 145.6) - -

295025 High Reactor Pressure I 3 EA2.04 Ability to determine andlor 3.9 1 interpret the following as they apply to HIGH REACTOR PRESSURE:

Suppression pool level (CFR: 41.I0 I 43.5 145.13) - -

295026 Suppression Pool High Water Temp. 2.1.27 Knowledgeof system purpose 2.8 1 I5 andlor function. (CFR: 41.7) -

295027 High Containment Temperature I5 2.4.31 Knowledge of annunciators 3.3 1 alarms and indications, and use of the response instructions. (CFR: 41.1 0 I 45.3) -

295028 High Drywell Temperature I 5 EK3.01 Knowledge of the reasons for 3.6 1 the following responses as they apply to HIGH DRYWELL TEMPERATURE:

Emergency depressurization (CFR:

41.5 145.6) - -

295030 Low Suppression Pool Wtr Lvl I 5 2.4.50 Ability to verify system alarm 3.3 1 setpoints and operate controls identified in the alarm response manual. (CFR: 45.3) -

295031 Reactor Low Water Level I 2 EK2.04 Knowledge of the 4.0 1 interrelations between REACTOR LOW WATER LEVEL and the following: Reactor core isolation cooling: Plant-Specific (CFR: 41.7 I 45.8) -

295037 SCRAM Condition Present and EA1.04 Ability to operate andlor 4.5 1 Power Above APRM Downscale or Unknown monitor the following as they apply to I1 SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKOWN: SBLC (CFR: 41.7 I45.6) 295038 High off-site Release Rate I 9 EA2.04 Ability to determine andlor 4.1 1 interpretthe following as they apply to HIGH OFF-SITE RELEASE RATE:

Source of off-site release (CFR:

41.10143.5145.13) - -

600000 Plant Fire On Site I 8 MI.01 Ability to operate andlor 3.0 1 monitor the following as they apply to PLANT FIRE ON SITE: Respirator air pack WA Category Totals: Grouo Point Total: 20 3

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evoli Ins Ti K K UAPE #I Name I Safety Function WA Topic(s) IR 1 2 295002 Loss of Main Condenser Vac I 3 295007 High Reactor Pressure I 3 295008 High Reactor Water Level I 2 -

295009 Low Reactor Water Level I 2 2.4.49 Ability to performwithout reference 4.0 to procedures those actions that require immediate operation of system components and controls. (CFR: 41.10 143.2 145.6) -

295010 High Drywell Pressure I 5 AA2.02 Ability to determine andlor interpret 3.8 the following as they apply to HIGH DRYWELL PRESSURE: Drywell pressure (CFR: 41.10143.5145.13) -

295011 High Containment Temperature / 5 X AKI .01 Knowledge of the operational 4.0 implications of the following concepts as they apply to HIGH CONTAINMENT TEMPERATURE (MARK 111 CONTAINMENT ONLY): Containment pressure: Mark-Ill (CFR: 41.8 to 41.10) -

295012 High Drywell Temperature I5 -

295013 High Suppression Pool Temp. I 5 X AK2.01 Knowledae of the interrelations 3.6 between HIGH SGPPRESSION POOL TEMPERATURE and the following:

Suppression pool cooling (CFR: 41.7 I 45.8)

AA1.02 Ability to operate andlor monitor 3.6 the following as they apply to LOSS OF CRD PUMPS: RPS (CFR: 41.7 I 45.6) 295029 High Suppression Pool Wtr Lvl I5 295032 High Secondary ContainmentArea Temperature I 5 295033 High Secondary ContainmentArea Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High Differential I 5 -

295036 Secondary Containment High SumpIArea X EK2.01 Knowledge of the interrelations 3.1 Water Level I5 between SECONDARY CONTAINMENT HIGH SUMPIAREA WATER LEVEL and the following: Secondary containment equipment and floor drain system (CFR:

- 41.7 I45.8) -

500000 High CTMT Hydrogen Conc. I 5 X EK3.01 Knowledge of the reasons for the 2.9 following responses as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Initiation of containment atmosphere control system (CFR: 41.5 145.6)

WA Category Totals: 1 2 Group Point Total:

4

ES-401 BWR Examination Outline Form ES-401-1 PI =

System # I Name KIA Topic(s) IR 203000 RHRILPCI: Injection K1.18 Knowledge of the physical 3.8 Mode connections andlor cause effect relationships between RHRILPCI:

INJECTION MODE and the following: Reactor vessel: Plant-Specific (CFR: 41.2 to 41.9 I 45.7 to 45.8) -

203000 RHRRPCI: Injection K3.04 Knowledae of the effect that a 4.6 Mode loss or malfunct'bn of the RHRILPCI:

INJECTION MODE will have on following: Adequate core cooling (CFR: 41.7 145.4) -

205000 Shutdown Cooling A1.09 Ability to Dredict andlor 2.8 monitor changes in parameters associated with operating the SHUTDOWN COOLING SYSTEMlMODE controls including:

SDClRHR pumplsystem discharge pressure (CFR: 41.5 145.5) -

205000 Shutdown Cooling A4.05 Ability to manually operate 3.2 andlor monitor in the control room:

Minimum flow valves (CFR: 41.7 I 45.5 to 45.8) -

206000 HPCl SUPPRESSED -

207000 Isolation (Emergency) SUPPRESSED Condenser -

209001 LPCS A2.04 Ability to (a) predict the 2.9 impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or oDerations: D.C.

failures (CFR:'41.5 145.6) -

209002 HPCS K6.03 Knowledge of the effect that a 2.5 loss or malfunction of the following will have on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS):

Component cooling water systems:

BWR-5,6 (CFR: 41.7 145.7) -

211000 SLC K2.02 Knowledge of electrical power 3.1 supplies to the following: Explosive valves (CFR: 41.7) -

212000 RPS K1.lo Knowledge of the physical 3.2 connections andlor cause- effect relationshipsbetween REACTOR PROTECTION SYSTEM and the following: Main turbine (CFR: 41.2 to 41.9 I 45.7 to 45.8) -

5

System # I Name WA Topic@) IR #

L 212000 RPS A3.04 Ability to monitor automatic 3.9 1 operations of the REACTOR PROTECTION SYSTEM including: System status lights and alarms (CFR: 41.7 145.7) -

215003 IRM K3.04 Knowledge of the effect 3.6 1 that a loss or malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following: Reactor power indication (CFR: 41.7 145.4) - -

215004 Source Range Monitor A3.04 Ability to monitor automatic 3.6 1 operations of the SOURCE RANGE MONITOR (SRM)

SYSTEM including: Control rod black status (CFR: 41.7 145.7) -

215005 APRM I LPRM 2.2.22 Knowledge of limiting 3.4 1 conditions for operations and safety limits. (CFR: 43.2 145.2) - -

217000 RCIC A3.01 Ability to monitor automatic 3.5 1 operations of the REACTOR CORE /SOLATION COOLING SYSTEM (RCIC) including: Valve operation (CFR: 41.7 I45.7) -

21aooo ADS K5.01 Knowledge of the 3.8 1 operational implicationsof the following concepts as they apply to AUTOMATIC W DEPRESSURIZATION SYSTEM:

ADS logic operation (CFR: 41.5 I 45.3) -

223002 PClSMuclear Steam 2.1.30 Ability to locate and 3.9 1 Supply Shutoff operate components, including local controls. (CFR: 41.7 I 45.7) - -

239002 SRVs A2.03 Abilitv to (a1 Dredict the 4.1 1 impacts of h e follohng on the RELIEFISAFETYVALVES; and (b) based on those predictions, use procedures to correct, control, or mitigatethe consequences of those abnormal conditions or operations: Stuck Open SRV (CFR: 41.5 I 45.6) - -

259002 Reactor Water Level K4.03 Knowledae of REACTOR 2.8 1 Control WATER LEVEL~ONTROL SYSTEM design feature@) andlor interlocks which provide for the following: Reactor feedpump runout protection: MDFP (CFR:

41.7) 6

System # I Name WA Topic(s) IR

\

c- 261000 SGTS K3.02 Knowledge of the effect that a 3.6 loss or malfunctionof the STANDBY GAS TREATMENT SYSTEM will have on following: Off-site release rate (CFR:

41.7 I 45.7) -

262001 AC Electrical K5.02 Knowledge of the operational 2.6 Distribution implications of the following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION: Breaker control (CFR:

41.5 I45.3) -

262002 UPS (ACIDC) A4.01 Ability to manually operate andlor 2.8 monitor in the control room: Transfer from alternative source to preferred source (CFR: 41.7 I45.5 to 45.8) -

263000 DC Electrical K4.02 Knowledge of D.C. ELECTRICAL 3.1 Distribution DISTRIBUTIONdesign feature(s) andlor interlocks which providefor the following:

Breaker interlocks, pemissives, bypasses and cross ties: Plant-Specific

{CFR: 41.7) -

263000 DC Electrical A2.01 Ability to (a) predict the impacts of 2.8 Distribution the following on the D.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Grounds (CFR: 41.5 145.6) -

264000 EDGs K5.06 Knowledge of the operational 3.4 W implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET): Load sequencing (CFR: 41.5 I45.3) -

300000 Instrument Air K4.03 Knowledae of IINSTRUMENT 2.8 AIR SYSTEM) iesign'feature(s) and or interlocks which providefor the following:

Securing of IAS upon loss of cooling water (CFR: 41.7) -

300000 InstrumentAir K2.01 Knowledge of electrical power 2.8 supplies to the following: Instrument air compressor (CFR: 41.7) -

400000 Component Cooling A3.01 Ability to monitor automatic 3.0 Water operations of the CCWS including:

Setpoints on instrumentsignal levels for normal operations, warnings, and trips that are applicable to the CCWS (CFR:

41.7 I 45.71 =

KIA Category Point Totals: Group Point Total:

7

ES-401 BWR Examination Outline F o ES-401-1

~

System # I Name

- I WA Topic@) #

201001 CRD Hydraulic A1 -10 Ability to predict and/or 1 monitor changes in parameters associated with operating the CONTROL ROD DRIVE HYDRAULIC SYSTEM controls including: CRD cooling water flow (CFR: 41.5 I 45.5) 201002 RMCS SuoDressed 201003 Control Rod and Drive Suppressed Suppressed K1.06 Knowledge of the physical connections andlor cause- effect relationships between ROD POSITION INFORMATION SYSTEM and the following: RCIS:

Plant-Specific (CFR: 41.2 to 41.9 145.7 to 45.8) 215001 Traversing In-core Probe 215002

- . ...- .RBM

.- ... Suppressed 216000 Nuclear Boiler Inst. 43.01 Ability to monitor automatic W

operations of the NUCLEAR BOILER Instrumentation including:

Relationship between meterlrecorder readings and actual parameter values: Plant-Specific (CFR: 41.7 / 45.7) 219000 RHRLPCI: ToruslPool

oolina Mode Y

!23001 Primary CTMT and Aux.

226001 RHRLPCI: CTMT Spray (6.04 Knowledge of the effect 1 Mode :hat a loss or malfunction of the bllowing will have on the IHRILPCI: CONTAINMENT SPRAY SYSTEM MODE: Keep ill system (CFR: 41.7 145.7) 8

A A System # I Name WA Topic(s) 3 4 230000 RHRILPCI: TorusIPool Spray Suppressed Mode 233000 Fuel Pool CoolingICleanup K5.06 Knowledge of the operational implicationsof the following concepts as they apply to FUEL POOL COOLING AND CLEAN-UP: Maximum normal heat load (CFR: 41.5 I45.3) 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSlV Leakage Control X A4.03 Ability to manually operate andlor monitor in the control room:

Main steamline pressures BWR-4,5,6 (CFR: 41.7 I 45.5 to 45.8) 241000 ReactorKurbinePressure Regulator 245000 Main Turbine Gen. and X A3.03 Ability to monitor automatic Auxiliaries operations of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS including: Generator megawatt output. (CFR:

. 41.7 I 45.7) 256000 Reactor Condensate 2.1.32 Ability to explain and apply system limits and precautions.

(CFR: 45.2 145.6) 259001 Reactor Feedwater 268000 Radwaste K3.04 Knowledge of the effect that a loss or malfunctionof the RADWASTE will have on following: Drain sumps . (CFR:

41.7 145.4) 271000 Offgas K5.08 Knowledae of the operational imptications of the following concepts as they apply to OFFGAS SYSTEM: Charcoal absorption of fission product gases (CFR 41.7 / 45.4) 272000 Radiation Monitoring 286000 Fire Protection K3.03 Knowledge of the effect that a loss or malfunctionof the FIRE PROTECTION SYSTEM will have on following: Plant protection (CFR: 41.7 145.4) 290002 Reactor Vessel lntemals K5.07 Knowledge of the operational implications of the following concepts as they apply to REACTOR VESSEL INTERNALS: Safety limits (CFR:

41.5 145.3)

WA Category Point Totals: Group Point Total: I 12 9

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant !O - =__

EIAPE #I Name I Safety Function IR #

295001 Partialor Complete Loss of Forced Core Flow Circulation I 1 & 40 - -

2.2.22 Knowledge of limiting 4.1 1 295003 Partial or Complete Loss of ACI 6 conditions for operation and safety limits. (CFR: 43.2 145.2) 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip I 3 -

295006 SCRAM I 1 2.1.32 Ability to explain and apply 3.8 1 system limits and precautions.

(CFR:41.10/43.2/45.12) 295016 Control Room Abandonment I 7 AA2.02 Ability to determine andlor 4.3 1 interpret the following as they apply to CONTROL ROOM ABANDONMENT : Reactor Water Level (CFR: 41.10 143.5 145.13) - -

295018 Partial or Total Loss of CCW I8 2.4.30 Knowledge of which events 3.6 1 related to system operationslstatus should be reported to outside aaencies.

(CFR: 43.5 145.11) -

295019 Partial or Total Loss of Inst. Air I 8 AA2.02 Ability to determine andlor 3.7 1 interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENTAIR: Status of safety-related instrument air system loads (see AK2.1-AK2.19) (CFR:

41.10 143.5 145.13) 295021 Loss of Shutdown Cooling I 4 295023 RefuelingAcc Cooling Mode I8 295024 High Drywell Pressure I 5 EK1.01 Knowledge of the 4.2 1 operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE:

Drywell integrity: Plant-Specific (CFR: 41.8 to41.10) - -

295025 High Reactor Pressure I 3 EA2.06 Ability to determine andlor 3.7 3.8 interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor Water Level -

295026 Suppression Pool High Water Temp. I 5 2.4.4 Ability to recognize abnormal 4.3 1 indicationsfor system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.IO 143.2 I45.6) - -

10

11 1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant I olution: SRO 1

ElAPE #/ Name / Safety Function K K 1 2 G I K/ATopic(s) 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure I 3 -

295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 andlor interpretthe following as they apply to LOW REACTOR WATER LEVEL : Reactor water 295010 High Drywell Pressure I 5 295011 High ContainmentTemperature / 5 295012 High Drywell Temperature / 5 X I-----

X

\

I 2.4.30 Knowledge of which events related to system operationslstatusshould be reportedto outside agencies.

(CFR: 43.5 / 45.1 1) -

AK2.02 Knowledge of the interrelationsbetween HIGH 1

295013 High Suppression Pool Temp. / 5 295014 Inadvertent ReactivityAddition I 1 295015 Incomplete SCRAM I 1 295017 High Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation I 5 & 7 295022 Loss of CRD Pumps I 1 X AKI .01 Knowledge of the operational implications of the following concepts as they apply to LOSS OF CRD PUMPS:

Reactor pressure vs. rod insertion capability (CFR: 41.8 to 41.10) 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary ContainmentArea SumplArea Water Level I 5 500000 High CTMT Hydrogen Conc. I 5 I -

I A Categoil%tals: 1 1 1 I Group Point Total: 4 12

ES-401 BWR Examin; in Outline Form ES-401-1 PI System # I Name K/A Topic@) IR 203000 RHRILPCI: Injection Mode 205000 Shutdown Cooling 2.1.23 Ability to perform specific 4.0 system and integrated plant procedures during different modes of plant operation. (CFR: 45.2 /

45.61 206000 HPCl Suppressed 207000 Isolation (Emergency) Suppressed 2.1.12 Ability to apply technical specifications for a system. (CFR:

43.2 143.5 145.3)

Supply Shutoff 239002 SRVs 259002 Reactor Water Level

'W Control 261000 SGTS 262001 AC Electrical Distribution 262002 UPS (ACIDC) 263000 DC Electrical Distribution -

264000 EDGs A I .01 Ability to predict and/or 3.0 monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEUJET) controls including:

Lube oil temperature (CFR: 41.5 I 45.5) I 13

14 3-401 BWR Examination Outlin Plant S Form ES-401-1 I

L' System # I Name

!01001 CRD Hydraulic

!01002 RMCS

!01003 Control Rod and Drive dechanism ...

!01004 RSCS Z01005 RClS

!01006 RWM

!02001 Recirculation

!02002 Recirculation Flow Control safety limits.

'CFR: 43.2 145.2)

!04000 RWCU

!I4000 RPlS

!15001 Traversing In-coreProbe

...-RBM

!I5002

!16000 Nuclear Boiler Inst.

!19000 RHRILPCI: ToruslPool Suppressed I I

dode

!30000 RHRRPCI: TonrslPool Spray dode

!33000 Fuel Pool CoolinglCleanup

'W !34000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSlV Leakage Control 241000 Reactorrurbine Pressure Regulator 245000 Main Turbine Gen. and 268000 Radwaste 271000 m a s 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 ReactorVessel lntemals A2.06 Ability to (a) predict the 4.5 impacts of the following on the REACTOR VESSEL INTERNALS ;and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Exceeding safety limits (CFR: 41.5 145.6)

KIA Category Point Totals: Group Point Total:

'W

ES-401 ~ Genefl%owledge and Abilities Outline (Tier 3) Form ES-401-3 16

NRC Outline Submittal Copy #1 Outline Methodolonv for 2004 Clinton Power Station Written NRC Exam Tier 1 and 2 Tier 1 and Tier 2 items were reviewed to determine those items that could be eliminated fkom the selection process due to inapplicability to Clinton Power Station (CPS). No Tier 1 items were eliminated from the selection process. Five (5) items in Tier 2 were eliminated fkom the selection process. Only those items with & l K and As their suppressed were eliminated fkom the selection process. All items that were eliminated fi-om the selection process are indicated by the notation suppressed in their WA Topic@)column.

For each individual group, the remaining items in the Tier groups were then sequentially numbered. Tokens were then gathered, one token for each of the sequentially numbered items in that group.

If a group required the same number of points as items remaining in that group (following elimination of inapplicable items) then each item in the group was selected for sampling.

If the required number of points in a group was greater than the items remaining in the group (following elimination of inapplicable items) then all items were automatically selected once and then tokens were randomly selected to determine the topics to be sampled twice.

• LJ If the required number of points in the group was less than the number of items remaining in the group (following elimination of inapplicable items) then tokens were randomly selected until the required number of items were selected for sampling.

After selection of the items for sampling in each of the Tier 1 and Tier 2 groups, a determination of the WA category was made for each item using the following method:

Tokens were gathered to represent each of the WA categories (Kl, K2, K3, Al, A2 and G for Tier 1 and K1 through K6, A1 through A4 and G for Tier 2). For each of the items selected for sampling, a token was randomly selected to determine the K/A category to sample. (Note: If a WA category for an item selected for sampling did not include any statements with importance equal or greater than 2.5 for the applicable license level, the token representing that WA category was not included for random selection).

AAer selection of the WA category, tokens were gathered to represent each of the unsuppressed statements in that category with an importance of 2.5 or greater for the applicable license level. A token was then randomly selected to determine the specific WA to sample.

For those items in Tier 1 and Tier 2 whose WA category was determined to be G, sixteen (16) tokens were gathered into a set, each token representing one of the following general WAS: 2.1.2,2.1.14,2.1.23,2.1.27,2.1.28,2.1.30,2.1.32,2.1.33, 2.2.22,2.2.25,2.4.4, W

2.4.6,2.4.30,2.4.31 ,2.4.49, and 2.4.50. For each of the G category items in Tier 1 and 1

NRC Outline Submittal Copy #1 Outline Methodolow for 2004 Clinton Power Station Written NRC Exam Tier 2, one of the sixteen tokens was randomly selected to determine which general WA

__ _. to sample.

Tier 3 Four tokens were gathered into a set, each token representing one of the four groups of Tier 3. For the RO portion of the outline one of the four tokens was randomly drawn fkom the set of tokens. Each time a token was drawn fkom the set, one sampling of that area was designated and then the token replaced in the set. This process continued until the number of items selected for sampling in Tier 3 was equal to ten (10).

The specific WA was then selected by gathering tokens representing all unsuppressed WASwith an importance rating in the RO license level of 2.5 or greater in the respective area. A token was then selected to determine the WA for sampling. This process was used for all four groups in Tier 3.

The process in the above two (2) paragraphs was utilized for the SRO position except that the tokens gathered represented WAS with an importance rating of 2.5 or greater for the SRO license level and only seven (7) total points were required.

Results were recorded on the ES-401-1 cover sheet to verify that two topics fiom every category were sampled as required in the RO license level. Tier 2 category K2 was sampled only one time. Further review showed that WA category K5 was sampled seven L../ (7) times. Since K5 was over sampled compared to the other catedgories it was selected to have one of its items moved to the K2 category.

Eaualization of Samdinq of RO WAS In order to provide a minimum sampling of two items in the K2 area, one K5 item was deselected for sampling and changed to a K2 item using the following method. Seven (7) tokens were gathered into a set representing each of the K5 category items sampled in Tier 2. One token was randomly selected and the item was then changed to a K2 item.

300000K5.13 was randomly deselected and replaced with 300000K2.01 (K2.01 being the only unsuppressed K2 item for 300000). Since this change followed the initial random sampling, this change was recorded on Form ES-401-4.

Selection of Replacement WAS in the SRO Outline in Tier 1 and Tier 2 Several SRO WASwere deselected fiom sampling due to limited applicability to 10 CFR 55.43 and no specific SRO-only objective. All WAS deselected were recorded on Form Form ES-401-4. The WASwere replaced by first randomly selecting the WA category (Note: When an SRO-only WA was rejected for the above reason only WA categories A2 and G were considered for replacement of the WA. This was done to ensure the SRO exam outline was weighted sufficiently in the G and A2 category per D.l .c of E$-401).

i-1 If category A2 was selected, tokens were gathered to represent each of the unsuppressed 2

NRC Outline Submittal Copy #1 Outline Methodologv for 2004 Clinton Power Station Written NRC Exam WASin that category with an SRO importance of 2.5 or greater. A token was then

-4 randomly selected to replace the deselected WA. If category G was selected, then sixteen (16 ) tokens were gathered into a set, each token representing one of the following general WAS: 2.1.2,2.1.14,2.1.23,2.1.27,2.1.28,2.1.30,2.1.32,2.1.33,2.2.22,2.2.25, 2,4.4,2.4.6,2.4.30,2.4.3 1,2.4.49, and 2.4.50. One of the sixteen tokens was then randomly selected to determine the replacement K/A to sample.

Selection of Replacement WASin the SRO Outline in Tier 3 One SRO WA was deselected fiom sampling in Tier 3 due to limited applicability to 10 CFR 55.43 and no specific SRO-only objective. The replacement WA was selected fiom the remaining WASby gathering tokens to represent the WAS in that General category.

The replacement token was then randomly selected to replace the deselected WA.

3

Clinton Power Station Suppressed KIAs System # System /Evolution Name KA # h2 Statement Basis For Suppression 201001 Control Rod Drive Hydraulic System A1.04 Head spray flow: BWR-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 retum 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 201002 Reactor Manual Control System A I .01 CRD drive water flow Clinton is a BWR 6 and does not utilize this system.

A I .02 Control rod position Clinton is a BWR 6 and does not utilize this system.

A I .03 Rod movement sequence lights Clinton is a BWR 6 and does not utilize this system.

A I .04 Overall reactor power Clinton is a BWR 6 and does not utilize this system.

A I .05 Local reactor power Clinton is a BWR 6 and does not utilize this system.

A2.01 Rod movement sequence timer malfunctions Clinton is a BWR 6 and does not utilize this system.

A2.02 Rod drift alarm Clinton is a BWR 6 and does not utilize this system.

A2.03 Select block Clinton is a BWR 6 and does not utilize this system.

4 A2.04 Control rod block Clinton is a BWR 6 and does not utilize this system.

A3.01 Control rod block actuation Clinton is a BWR 6 and does not utilize this system.

A3.02 Rod movement sequence lights Clinton is a BWR 6 and does not utilize this system.

A3.03 Rod drift alarm Clinton is a BWR 6 and does not utilize this system.

A3.04 Rod movement sequence timer malfunction alarm: Clinton is a BWR 6 and does not utilize this system.

Plant-Specific A4.01 Rod movement control switch Clinton is a BWR 6 and does not utilize this system.

A4.02 Emergency inlnotch override switch Clinton is a BWR 6 and does not utilize this system.

A4.03 Rod drift test switch Clinton is a BWR 6 and does not utilize this system.

A4.04 Timer malfunction test switch: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

A4.05 Rod select matrix Clinton is a BWR 6 and does not utilize this system.

A4.06 Rod select matrix power switch Clinton is a BWR 6 and does not utilize this system.

K1.01 Control rod drive hydraulic system Clinton is a BWR 6 and does not utilize this system, K1.02 Control rod and drive mechanism Clinton is a BWR 6 and does not utilize this system.

K1.03 Control rod block interlockslpower operation refueling Clinton is a BWR 6 and does not utilize this system.

K1.04 Rod block monitor: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.05 Rod worth minimizer: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.06 Rod sequence control system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

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

System # System /Evolution Name J a # KA Statement Basis For Suppression K1.08 Refueling interlocks: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K2.01 Select matrix Clinton is a BWR 6 and does not utilize this system.

K2.02 CRD HCU directional control valves Clinton is a BWR 6 and does not utilize this system.

K3.01 Ability to move control rods Clinton is a BWR 6 and does not utilize this system.

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

K3.03 Ability to process rod block signals Clinton is a BWR 6 and does not utilize this system.

K4.01 Detection of sequence timer malfunction Clinton is a BWR 6 and does not utilize this system.

K4.02 Control rod blocks Clinton is a BWR 6 and does not utilize this system.

K4.03 Detection of drifting control rods Clinton is a BWR 6 and does not utilize this system.

K4.04 Single notch rod withdrawal and insertion Clinton is a BWR 6 and does not utilize this system.

K4.05 Notch override rod withdrawal Clinton is a BWR 6 and does not utilize this system.

K4.06 Emergency In rod insertion Clinton is a BWR 6 and does not utilize this system.

K4.07 Timing of rod insert and withdrawal cycles (rod Clinton is a BWR 6 and does not utilize this system.

movement sequence timer)

K4.08 Continuous In rod insertion Clinton is a BWR 6 and does not utilize this system.

K6.01 Select matrix power Clinton is a BWR 6 and does not utilize this system.

201 004 Rod Sequence Control System (Plant Specipc)

A1.O1 Reactor manual control system: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

A2.01 Loss of rod position information: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

A2.02 Attempting to move a stuck control rod: BWR-4,5 Clinton is a BWR-6 and does not utilize this system.

'd A2.03 Turbine trip: BWR-4.5 Clinton is a BWR-6 and does not utilize this system.

A3.01 Rod select switch light: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

A3.02 Rod select bottom lamp dimmer logic: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

A3.03 Back panel indicators: BWR-4.5 Clinton is a BWR-6 and does not utilize this system.

A3.04 Annunciator and alarm signals: BWR-4. 5 Clinton is a BWRB and does not utilize this system.

A3.05 Verification of proper function/ operability: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

A4.01 System bypass switches: BWR-4, 5 Clinton is a BWRB and does not utilize this system.

A4.02 RSCS console switches and indicators: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

A4.03 RSCS back panel switches and indicators: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K1.01 Reactor manual control system: BWR-4.5 Clinton is a BWR-6 and does not utilize this system.

K1.02 Turbine generator system: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K1.03 Rod position information system: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K1.04 Rod worth minimizer: BWR-4,5 Clinton is a BWR-6 and does not utilize this system.

K3.01 Reactor manual control: BWR-4,5 Clinton is a BWR-6 and does not utilize this system.

K4.01 Select blocks: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K4.02 Insert rod blocks: BWR-4,5 Clinton is a BWR-6 and does not utilize this system.

K4.03 Withdraw rod blocks: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K4.04 RSCS bypass as reactor power increases: BWR-4,5 Clinton is a BWR-6 and does not utilize this system.

sfzY53t 4/3/03 Page 2 of 26

J KA # K A Statement Basis Fur Suppression K4.05 Rod movement, direction, and selection information: Clinton is a BWR-6 and does not utilize this system.

BWR-4,5 K4.06 Group notch control: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K4.07 Minimizingrod worth: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K5.01 Prevention of clad damage if a control rod drop Clinton is a BWR-6 and does not utilize this system.

accident (CRDA) occurs: BWR-4,5 K5.02 Sequences and groups: BWR-4,5 Clinton is a BWR-6 and does not utilize this system.

K5.03 Group notch control limits and rod density: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

K6.01 Rod position information: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system K6.02 Rod direction information: BWR-4, 5 Clinton is a BWR-6 and does not utilize this system K6.03 Rod movement information: BWR-4,5 Clinton is a BWR-6 and does not utilize this system K6.04 Turbine generator (1st stage shell pressure): BWR-4, 5 Clinton is a BWR-6 and does not utilize this system.

201006 Rod Worth Minimizer System (R (Plant Specipc)

A I .01 Rod position: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A I .02 Status of control rod movement blocks; P-Spec(Not- Clinton is a BWR 6 and does not utilize this system.

BWR6)

A I .03 Latched group indication: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A2.01 Power supply loss: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A2.02 Loss of steam flow input: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A2.03 Rod drift: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A2.04 Stuck rod: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A2.05 Out of sequence rod movement; P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A2.06 Loss of reactor water level control input: P-Spec(Not- Clinton is a BWR 6 and does not utilize this system.

BWR6)

A2.07 RWM hardwarelsohare failure: P-Spec(Not-BWR6) Clinton is a BWR-6 and does not utilize this system.

A3.01 System window and light indication: P-Spec(Not- Clinton is a BWR 6 and does not utilize this system.

BWR6)

A3.02 Verification of proper functioning/ operability: P- Clinton is a BWR 6 and does not utilize this system.

Spec(Not-BWR6)

A3.03 Annunciator and alarm signals: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A3.04 Control rod movement blocks: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A3.05 Latched group indication: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A4.01 System bypass switch: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A4.02 Pushbutton indicating switches: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A4.03 Latched group indication: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A4.04 Rod withdrawal error indication: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A4.05 Rod insert error indication: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

A4.06 Selected rod position indication: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K1.O1 Reactor manual control: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K1.02 Rod position indication system: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K1.03 Reactor water level control (feed flow): P-Spec(Not- Clinton is a BWR 6 and does not utilize this system.

BWR6) 4/3/03 Page 3 of 26

System # System /Evolution Name xA# h 3 Statement Basis For Suppression K1.04 Steam flowlreactor power: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K1.05 Control rod drop accident: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K1.06 Rod sequence control system: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K1.07 Process computer: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K1.08 Reactor power (turbine first stage pressure): P- Clinton is a BWR 6 and does not utilize this system.

Spec(Not-BWR6)

K2.01 Rod worth minimizer: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K3.01 Reactor manual control system: P-Spec(Not-BWRG) Clinton is a BWR 6 and does not utilize this system.

K4.01 Insert blocks/errors: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K4.02 Withdraw blocks/errors: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K4.03 Select blockslerrors: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K4.04 System bypass: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K4.05 Substitute rod position data: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K4.06 Correction of out of sequence rod positions: P- Clinton is a BWR 6 and does not utilize this system.

Spec(Not-BWR6)

K4.07 Display of out of position control rods without rod Clinton is a BWR 6 and does not utilize this system.

blocks (transition zone): P-Spec(Not-BWR6)

K4.08 System testing: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K4.09 System initialization: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.01 Minimize clad damage if a control rod drop accident Clinton is a BWR 6 and does not utilize this system.

(CRDA) occurs: P-Spec(Not-BWR6)

K5.02 Low power set point: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

d K5.03 Low power alarm point (LPAP): P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.04 Transitionzone: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.05 High power set point: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.06 Rod groups and steps: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.07 Latch groups: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.08 Operating sequence: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.09 Select error: P-Spec(Not-BWRG) Clinton is a BWR 6 and does not utilize this system.

K5.10 Withdraw error: P-Spec(Not-BWRG) Clinton is a BWR 6 and does not utilize this system.

K5.11 Insert error. P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.12 Withdraw block: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.13 Insert block: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K5.14 Alternate withdraw and insert limits: P-Spec(Not- Clinton is a BWR 6 and does not utilize this system.

BWR6)

K6.01 RWM power supply: P-SpeHNot-BWR6) Clinton is a BWR-6 and does not utilize this system.

K6.02 Reactor water level control input: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K6.03 Rod position indication: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K6.04 Process computer: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

K6.05 Steam flow input: P-Spec(Not-BWR6) Clinton is a BWR 6 and does not utilize this system.

P 4/3/03 Page 4 of26

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System # System /Evolution Name J IC4 # llil Statement Basis For Suppression 202001 Recirculation System A2.09 Recirculation scoop tube lockup: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

A2.23 Suppression pool level: BWR-2, 3, 4 Clinton is a BWR 6 K1.14 Rod block monitor: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.24 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

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

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

K3.12 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.08 Oil pump automatic starts: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

202002 Recirculation Flow Control System A2.05 Scoop tube lockup: BWR-2, 3 , 4 Clinton is a BWR 6 and does not utilize this system.

A3.03 Scoop tube operation: BWR-2, 3, 4 Clinton is a BWR 6 and does not utilize this system.

A4.06 Scoop tube power: BWR-2, 3.4 Clinton is a BWR 6 and does not utilize this system.

K4.01 Scoop tube break: Plant-Specific Clinton is a BWR 6 and does utilize this system.

K4.04 Automatic load following: Plant-Specific Clinton does not utilize this function.

K4.08 Automatic flow control valve positioning: BWR-5, 6 Clinton does not utilize this function.

K5.01 Fluid coupling: BWR-3, 4 Clinton is a BWR 6 and does not utilize this configuration.

203000 RHRZPCI: Injection Mode (Plant Specijic)

.d A2.15 Loop selection logic failure: Plant-Specific Clinton is a BWR 6 and does not utilize this configuration.

A3.07 Loop selection: Plant-Specific Clinton is a BWR 6 and does not utilize this configuration.

A4.12 Condensate storage tank level: Plant-Specific Clinton is a BWR 6 and does not utilize this function.

A4.14 Testable check valves Clinton is a BWR 6 and does not utilize this configuration.

K1.05 Recirculation system: BWR-3, 4 Clinton is a BWR 6 and does not utilize this configuration.

K4.11 Loop selection logic: Plant-Specific Clinton is a BWR 6 and does not utilize this configuration.

K5.01 Testable check valve operation 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 (RHR Shutdown Cooling Mode)

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

-.-w~$x.iTs%&?m%~

4/3/03 Page 5 of 26

System # System /Evolution Name RA # KA Statement Basis For Suppression K1.09 Auxiliary steam supply: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.I1 Nitrogen: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.I2 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K6.07 Nitrogen: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

~~~

206000 High Pressure Coolant Injection System A1.O1 Reactor water level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

Al.02 Reactor pressure: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

Al.03 Condensate storage tank level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

Al.04 Suppression pool level: BWR-2, 3.4 Clinton is a BWR-6 and does not utilize this system.

Al.05 Suppression pool temperature: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

Al.06 System flow: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

Al.07 System discharge pressure: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

Al.08 System lineup: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

Al.09 Turbine speed: BWR-2.3.4 Clinton is a BWR-6 and does not utilize this system.

A2.01 Turbine trips: BWR-2,3,4 Clinton is a BWR-6 and does not utilize this system.

A2.02 Valve closures: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

A2.03 Valve openings: BWR-2, 3, 4 Clinton is a BWRB and does not utilize this system.

A2.04 A.C. failures: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

- A2.05 A2.06 A2.07 D.C. failures: BWR-2, 3, 4 Inadequate system flow: BWR-2, 3, 4 Low suppression pool level: 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.

Clinton is a BWRB and does not utilize this system.

A2.08 High suppression pool temperature: BWR-2. 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.09 Low condensate storage tank level: BWR-2, 3,4 Clinton is a BWRB and does not utilize this system.

A2.10 System isolation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.11 Low reactor water level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.12 Loss of room cooling: BWR-2. 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.13 Loss of applicable plant air systems: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.14 Flow controller failure: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.15 Loss of control oil pressure: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.16 High drywell pressure: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A2.17 HPCl inadvertent initiation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A3.01 Turbine speed: BWR-2,3,4 Clinton is a BWR-6 and does not utilize this system.

A3.02 System Flow: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A3.03 System lineup: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A3.04 Reactor pressure: BWR-2.3, 4 Clinton is a BWR-6 and does not utilize this system.

A3.05 Reactor water level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A3.06 System discharge pressure: BWR-2,3,4 Clinton is a BWR-6 and does not utilize this system.

A3.07 Lights and alarms: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

4/3/03 Page 6 of 26

System # System /Evolution Name m# IC4 Statement Basis For Suppression A3.08 Condensate storage tank level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A3.09 Response to system isolation: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

A4.01 Turbine speed controls: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.02 Flow controller: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.03 Turbine temperatures: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.04 Major system valves: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.05 Reactor water level: BWR-2, 3.4 Clinton is a BWR-6 and does not utilize this system.

A4.06 Reactor pressure: BWR-2,3,4 Clinton is a BWR-6 and does not utilize this system.

A4.07 Condensate storage tank level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

~4.08 Suppression pool temperature: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.09 Suppression pool level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.10 System pumps: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

A4.11 Turning gear: BWR-2, 3, 4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

A4.12 Turbine trip controls: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.13 Turbine reset control: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

A4.14 System auto start control: BWR-2, 3, 4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

K1.01 Reactor vessel: BWR-2.3, 4 Clinton is a BWR-6 and does not utilize this system.

K1.02 Reactor water level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K1.03 Reactor pressure: BWR-2, 3.4 Clinton is a BWR-6 and does not utilize this system.

K1.04 Reactor feedwater system: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K1.05 Condensate storage system: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K1.06 Suppression chamber: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K1.07 D.C. power: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

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

K1.09 ECCS keep fill system: BWR-2, 3, 4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

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

K1.ll PCIS: BWR-2, 3.4 Clinton is a BWR-6 and does not utilize this system.

K1.12 Nuclear boiler instrumentation:BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K1.13 Main condenser BWR-2, 3, 4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

K1.14 SBGT: BWR-2, 3, 4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

K1.15 Plant air systems: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K1.16 Containmentrrorus pressure: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K2.01 System valves: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K2.02 System pumps: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K2.03 Initiation logic: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K2.04 Turbine control circuits: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K3.01 Reactor water level control: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K3.02 Reactor pressure control: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

- e -

System # System / Evolution Name KA# KA Statement Basis For Suppression K3.03 Suppression pool level control: BWR-2,3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.01 Turbine trips: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K4.02 System isolation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.03 Resetting turbine trips: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.04 Resetting system isolations: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.05 Preventing water hammer in turbine exhaust line Clinton is a BWR-6 and does not utilize this system.

(procedural control): BWR-2,3, 4 K4.06 Preventing water hammer in pump discharge line Clinton is a BWR-6 and does not utilize this system.

(procedural control ): BWR-2, 3, 4 K4.07 Automatic system initiation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.08 Manual system initiation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.09 Automatic flow control: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K4.10 Surveillance for all operable components: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.11 Turbine speed control: BWR-2,3,4 Clinton is a BWRB and does not utilize this system.

K4.12 Condensation of shaft sealing steam: BWR-2, 3.4 Clinton is a BWR-6 and does not utilize this system.

K4.13 Turbine and pump lubrication: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.14 Control oil to turbine speed controls: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K4.15 Low speed turning of the turbine rotor: BWR-2, 3,4(P- Clinton is a BWR-6 and does not utilize this system.

SP4 K4.16 Minimizing fission product concentration in the Clinton is a BWR-6 and does not utilize this system.

condensate storage tank (valve closures on system initiation): BWR-2, 3, 4(P-Spec)

K4.17 Protection against draining the condensate storage Clinton is a BWR-6 and does not utilize this system.

tank to the suppression pool: BWR-2, 3, 4 K4.18 Pump minimum flow: BWR-2, 3.4 Clinton is a BWR-6 and does not utilize this system.

K4.19 Automatic transfer of HPCl pump suction: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K5.01 Turbine operation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K5.02 Turbine shaft sealing: BWR-2, 3.4 Clinton is a BWR-6 and does not utilize this system.

K5.03 GEMAC controllers: BWR-2, 3, 4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

K5.04 Indications of pump cavitation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K5.05 Turbine speed control: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K5.06 Turbine speed measurement: BWR-2,3,4 Clinton is a BWR-6 and does not utilize this system.

K5.07 System venting: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K5.08 Vacuum breaker operation: BWR-2, 3, 4 Clinton is a BWRB and does not utilize this system.

K5.09 Testable check valve operation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K5.10 Assist core cooling: BWR-2, 3, 4 Clinton is a BWRB and does not utilize this system.

K6.01 Plant air systems: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K6.02 D.C. power: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K6.03 A.C. power: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K6.04 Condensate storage tank level: BWR-2, 3,4 Clinton is a BWR-6 and does not utilize this system.

K6.05 Suppression pool level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K6.06 SBGTS: BWR-2, 3,4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

4/3/03 Page 8 of 26

System # System /Evolution Name

~ -- ----

/ &I # KA Statement Basis For Suppression K6.07 ECCS keep fill system: BWR-2, 3, 4(P-Spec) Clinton is a BWR-6 and does not utilize this system.

K6.08 Reactor pressure: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K6.09 Condensate storage and transfer system: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K6.10 PCIS: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K6.11 Nuclear boiler instrumentation: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

K6.12 Reactor water level: BWR-2, 3, 4 Clinton is a BWR-6 and does not utilize this system.

207000 Isolation (Emergency) Condenser A1.O1 Isolation condenser level: BWR-2.3 Clinton is a BWR-6 and does not utilize this system.

Al.02 Shell side water temperature: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

Al.03 Steam flow: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

Al.04 Condensate flow: BWR-2, 3(P-Spec) Clinton is a BWR-6 and does not utilize this system.

A I .05 Reactor pressure: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A I .06 Reactor water level: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A I .07 Vent radiation level: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A I .08 Cooldown rate: BWR-2,3 Clinton is a BWR-6 and does not utilize this system.

A I .09 Valve operations: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A1.10 Primary side temperature: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A2.01 Tube bundle leak: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A2.02 High vent radiation: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

.,d A2.03 PClS signal resulting in system isolation: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A2.04 Inadequate system flow: BWR-2, 3 Clinton is a BWRB and does not utilize this system.

A2.05 Insufficient shell side makeup flow: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A2.06 Valve openings: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A2.07 Valve closures: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A2.08 System initiation: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A3.01 Isolation condenser level: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A3.02 Reactor pressure: BWR-2,3 Clinton is a BWR-6 and does not utilize this system.

A3.03 Reactor water level: BWR-2. 3 Clinton is a BWR-6 and does not utilize this system.

A3.04 Vent radiation levels: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A3.05 System lineup: BWR-2,3 Clinton is a BWR-6 and does not utilize this system.

A3.06 Lights and alarms: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A3.07 Primary and shell side temperatures: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A3.08 System flow: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A4.01 Isolation condenser level: BWR-2,3 Clinton is a BWR-6 and does not utilize this system.

A4.02 Steam line pressure: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A4.03 Primary and shell side temperatures: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A4.04 Vent line radiation levels: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A4.05 Major system valves: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

4/3/03 Page 9 of26 d

-*,n.--L__x-.X.-7-~

System # System /Evolution Name v EA # KA Statement Basis For Suppression A4.06 Shell side makeup valves: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

A4.07 Manually initiate the isolation condenser: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K1.01 Reactor vessel: BWR-2,3 Clinton is a BWR-6 and does not utilize this system.

K1.02 Reactor pressure: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K1.03 Reactor water level: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K1.04 Condensate transfer system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K1.05 Demineralized water system: BWR-2, 3(P-Spec) Clinton is a BWR-6 and does not utilize this system.

K1.06 Fire protection/service water: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K1.07 LPCI: BWR-2, 3(P-Spec) Clinton is a BWR-6 and does not utilize this system.

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

K1.09 Main steam system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K1. I O Plant air systems: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K1.ll Primary containment isolation system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K2.01 Motor operated valves: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K2.02 Initiation logic: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K3.01 Reactor pressure control during conditions in which the Clinton is a BWR-6 and does not utilize this system.

reactor vessel is isolated: BWR-2, 3 K3.02 Reactor water level (EPGs address the isolation Clinton is a BWR-6 and does not utilize this system.

condenser as a water source): BWR-2,3 K4.01 Isolationof the system in the event of a line break: Clinton is a BWR-6 and does not utilize this system.

BWR-2, 3 K4.02 Automatic initiation: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

.u K4.03 Filling of the system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K4.04 Steam and condensate flow indication: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K4.05 Detection of a tube bundle leak: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K4.06 Throttling of system flow: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K4.07 Manual operation of the system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K4.08 Protection against incomplete steam condensation Clinton is a BWR-6 and does not utilize this system.

(condensate outlet valve does not fully open): BWR-2,3,( P-Spec)

K5.01 Flow measurement across an elbow using differential Clinton is a BWR-6 and does not utilize this system.

pressure: BWR-2, 3 K5.02 Heat exchanger operation: BWR-2.3 Clinton is a BWR-6 and does not utilize this system.

K5.03 Heat transfer: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K5.04 Latent heat of vaporization: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K5.05 Saturated steam: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K5.06 Saturated liquid: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K5.07 Temperature sensing: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K5.08 Level indicator operation: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K5.09 Cooldown rate: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K5.10 System venting: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K6.01 Demineralized water system: BWR-2, 3(P-Spec) Clinton is a BWR-6 and does not utilize this system.

4/3/03 Page 10 of 26

-System # System /Evolution Name

-* n a

rr ar a-K4# Statement Basis For Suppression K6.02 Fire protectionkervicewater system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K6.03 Condensate transfer system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K6.04 Plant air systems: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K6.05 Primary containment isolation system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K6.06 Recirculation system: BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K6.07 A.C. power. BWR-2, 3 Clinton is a BWR-6 and does not utilize this system.

K6.08 D.C. power: BWR-2,3 Clinton is a BWR-6 and does not utilize this system.

~ _ _ _ _ ~~ ~ ~~ ~ _ _ _ _ _

209001 Low Pressure Core Spray System A2.11 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-I) 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: BWRQ, 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.

212000 Reactor Protection System A1.O1 RPS motor-generator output voltage Clinton is a BWR 6 and does not utilize this system.

A1.02 RPS motor-generator output amps Clinton is a BWR 6 and does not utilize this system.

A1.03 RPS motor-generator output frequency: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

Al.09 Individual relay status: Plant-Specific Clinton is a BWR 6 and utilizes a solid state system A2.01 RPS motor-generator set failure Clinton is a BWR 6 and does not utilize this system.

A2.19 Partial system activation (half-SCRAM) Clinton is a BWR 6 and does not utilize this system.

A2.21 Failure of individual relays to reposition: Plant-Specific Clinton is a BWR 6 and utilizes a solid state system A3.02 Individual system relay status: Plant-Specific Clinton is a BWR 6 and utilizes a solid state system.

A4.03 Provide manual select rod insertion: Plant-Specific Clinton is a BWR 6 and does not utilize this function.

A4.08 Individual system relay status: Plant-Specific Clinton is a BWR 6 and utilizes a solid state system.

K2.01 RPS motor-generator sets Clinton is a BWR 6 and does not utilize this system.

K4.06 Select rod insertion: Plant-Specific Clinton is a BWR 6 and does not utilize this function.

4/3/03 Page I 1 of 26

- -- System /Evolution Name System ##

___^_- --m rs --Y-%VmPn-,

d KA # K A Statement Basis For Suppression 214000 Rod Position Information System Kl.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&II(Not-BWRI) Clinton is a BWR 6 and does not utilize this configuration.

A2.01 Low reactor water level: Mark-l&II(Not-BWRI) Clinton is a BWR 6 and does not utilize this configuration.

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

A2.06 Valve closures: Mark-l&II(Not-BWRI) 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&lI(Not-BWRl) configuration.

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

A4.03 isolation valves: Mark-I&II(Not-BWRI) 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.

-4 K2.01 Shear valves: Mark-I&II(Not-BWRI) Clinton is a BWR 6 and does not utilize this configuration.

K4.01 Primary containment isolation: Mark-l&II(Not-BWRI) Clinton is a BWR 6 and does not utilize this configuration.

K6.04 Primary containment isolation system: Mark-i&II(Not- Clinton is a BWR 6 and does not utilize this BWRI) confiauration.

~~~

215002 Rod Block Monitor system A1.O1 Trip reference: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

A2.01 Withdrawal of control rod in high power region of core: Clinton is a BWR 6 and does not utilize this system.

BWR-3.4, 5 A2.02 Loss or reduction in recirculation system flow (flow Clinton is a BWR 6 and does not utilize this system.

comparator): BWR-3, 4, 5 A2.03 Loss of associated reference APRM channel: BWR-3, Clinton is a BWR 6 and does not utilize this system.

4,5 A2.04 Power supply losses: BWR-3,4,5 Clinton is a BWR 6 and does not utilize this system.

A2.05 RBM high or inoperable: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

A3.01 Four rod display: BWR-3,4, 5 Clinton is a BWR 6 and does not utilize this system.

A3.02 Meters and recorders: BWR-3,4, 5 Clinton is a BWR 6 and does not utilize this system.

A3.03 Alarm and indicating lights: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

A3.04 Verification or proper functioning/ operability: BWR-3, Clinton is a BWR 6 and does not utilize this system.

4, 5 A3.05 Back panel meters and indicating lights: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

4/3/03 Page 12 of 26

a System # System /Evolution Name

- m - z KA# RA Statement Basis For Suppression A3.06 Transfer to alternate APRM when referenced APRM Clinton is a BWR 6 and does not utilize this system.

bypassed: BWR3.4,5 A4.01 IRMlRBMrecorderlswitch: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

A4.02 RBM back panel switches, meters and indicating Clinton is a BWR 6 and does not utilize this system.

lights: BWR-3, 4, 5 A4.03 Trip bypasses: BWR-3,4,5 Clinton is a BWR 6 and does not utilize this system.

A4.04 Push to Check pushbutton: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

A4.05 Setup pushbutton: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

A4.06 Surveillance testing: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K1.01 APRM: BWR-3,4,5 Clinton is a BWR 6 and does not utilize this system.

K1.02 LPRM: BWR-3.4, 5 Clinton is a BWR 6 and does not utilize this system.

K1.03 Reactor manual control: BWR-3.4, 5 Clinton is a BWR 6 and does not utilize this system.

K1.04 Recirculation system: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K1.05 Four rod display: BWR-3,4,5 Clinton is a BWR 6 and does not utilize this system.

K1.06 Control rod selection: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K1.07 IRM: BWR-3,4, 5 Clinton is a BWR 6 and does not utilize this system.

K2.01 RBM channels: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K2.02 Recorders: BWR-3.4, 5 Clinton is a BWR 6 and does not utilize this system.

K2.03 APRM channels: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K3.01 Reactor manual control system: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K3.02 Limiting control rod pattern: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.01 Prevent control rod withdrawal: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K4.02 Allows stepping up of rod block setpoint: BWR-3, 4. 5 Clinton is a BWR 6 and does not utilize this system.

K4.03 Initiationpoint (30%): BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K5.01 Trip reference selection: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K5.02 Null sequence control: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K6.01 RPS: BWR-3.4.5 Clinton is a BWR 6 and does not utilize this system.

K6.02 Instrument power: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K6.03 Essential power: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K6.04 APRM reference channel: BWR-3, 4, 5 Clinton is a BWR 6 and does not utilize this system.

K6.05 LPRM detectors: BWR-3.4, 5 Clinton is a BWR 6 and does not utilize this system.

~______

215003 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.

21 5004 Source Range Monitor ( S W System K1.02 Reactor manual control Clinton is a BWR 6 and does not utilize this system.

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

I 21 5005 Average Power Range MonitorLocal Power Range Monitor System K1.03 RBM: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.I 0 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.

21 6000 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.

21 9000 RHBXPCI: TorudSuppression 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 Svstem and Auxiliaries A I .I 1 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-I,II A4.02 ACAD compressors: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

A4.10 Drywell nitrogen makeup: Mark-l,ll 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 Containrnentldrywell 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 SystemLWuclear Steam Supply Shut-K1.04 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.I 8 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.

swaz?G 4/3/03 Page 14 of 26

System # System /Evolution Name K4 # RA Statement Basis For Suppression K3.12 High pressure coolant injection: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.13 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.21 Traversing in-core probe system Clinton utilizes a TIP system inside the primary containment.

K3.24 Reactor building drainage system Clinton is a BWR 6 and does not utilize this system.

K3.28 Containment nitrogen inerting system Clinton is a BWR 6 and does not utilize this system.

226001 R H m P C I : Containment Spray System Mode Al.03 Suppression chamber pressure: Mark-1-11 Clinton is a BWR 6 and does not utilize this system.

Al.04 Suppression pool temperature: Mark-1-11 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-1-11 A4.15 Suppression chamber pressure: Mark-1-11 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-1-11 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 K6.70 Suppression chamber to drywell vacuum breakers: Clinton is a BWR 6 and does not utilize this system.

Mark-1-11 4 230000 RHWLPCI: Torus/Suppression Pool Spray Mode Al.01 Suppression chamber pressure Clinton is a BWR 6 and does not utilize this system.

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

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

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

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

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

A I .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.

A I .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.

A I .I1 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.

w x-w- -*__I System # System /Evolution Name K4# K A Statement Basis For Suppression A2.08 Pump seal failure Clinton is a BWR 6 and does not utilize this system.

A2.09 Inadequate room cooling Clinton is a BWR 6 and does not utilize this system.

A2.10 Nuclear boiler instrument failures Clinton is a BWR 6 and does not utilize this system.

A2.11 Motor operated valve failures Clinton is a BWR 6 and does not utilize this system.

A2.12 Valve logic failure Clinton is a BWR 6 and does not utilize this system.

A2.13 High suppression pool level Clinton is a BWR 6 and does not utilize this system.

A2.14 Low (or negative) suppression pool pressure during Clinton is a BWR 6 and does not utilize this system.

system operation A2.15 Loss of coolant accident Clinton is a BWR 6 and does not utilize this system.

A2.16 Loss of, or inadequate, heat exchanger cooling flow Clinton is a BWR 6 and does not utilize this system.

A3.01 Valve operation Clinton is a BWR 6 and does not utilize this system.

A4.01 Purnps Clinton is a BWR 6 and does not utilize this system.

A4.02 Spray valves Clinton is a BWR 6 and does not utilize this system.

A4.03 Keep fill system Clinton is a BWR 6 and does not utilize this system.

A4.04 Minimum flow valves Clinton is a BWR 6 and does not utilize this system.

A4.05 Heat exchanger cooling flow Clinton is a BWR 6 and does not utilize this system.

A4.06 Valve logic reset following automatic initiation of Clinton is a BWR 6 and does not utilize this system.

LPCllRHR in injection mode A4.07 System flow Clinton is a BWR 6 and does not utilize this system.

A4.08 Pumplsystem discharge pressure Clinton is a BWR 6 and does not utilize this system.

A4.09 Indicating lights and alarms Clinton is a BWR 6 and does not utilize this system.

A4.10 Condensate storage tank level Clinton is a BWR 6 and does not utilize this system.

A4.11 System venting Clinton is a BWR 6 and does not utilize this system.

A4.12 Suppression pool level Clinton is a BWR 6 and does not utilize this system.

A4.13 Suppression chamber pressure Clinton is a BWR 6 and does not utilize this system.

A4.14 Suppression pool temperature Clinton is a BWR 6 and does not utilize this system.

A4.15 Drywell pressure Clinton is a BWR 6 and does not utilize this system.

A4.16 The override for suppression pool spray valve logic Clinton is a BWR 6 and does not utilize this system.

K1.O1 Suppression pool Clinton is a BWR 6 and does not utilize this system.

K1.02 Condensate storage and transfer system Clinton is a BWR 6 and does not utilize this system.

K I .03 LPCllRHR piping Clinton is a BWR 6 and does not utilize this system.

K1.04 LPCllRHR pumps Clinton is a BWR 6 and does not utilize this system.

K1.05 A.C. electrical Clinton is a BWR 6 and does not utilize this system.

K1.06 Keep fill system Clinton is a BWR 6 and does not utilize this system.

K1.07 D.C. electrical Clinton is a BWR 6 and does not utilize this system.

K1.08 Nuclear boiler instrumentation Clinton is a BWR 6 and does not utilize this system.

K1.09 Reactor building drain system Clinton is a BWR 6 and does not utilize this system.

K1.10 Component cooling water systems Clinton is a BWR 6 and does not utilize this system.

K2.01 Valves Clinton is a BWR 6 and does not utilize this system.

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

s x

m n

m.m

--* xa$rw 4/3/03 Page 16 of 26

System # System /Evolution Name KA# R4 Statement Basis For Suppression K3.01 Suppression chamber pressure Clinton is a BWR 6 and does not utilize this system.

K3.02 Suppression pool temperature Clinton is a BWR 6 and does not utilize this system.

K3.03 Drywell pressure Clinton is a BWR 6 and does not utilize this system.

K3.04 Suppression chamber air temperature Clinton is a BWR 6 and does not utilize this system.

K4.01 Surveillance for all operable components Clinton is a BWR 6 and does not utilize this system.

K4.02 Redundancy Clinton is a BWR 6 and does not utilize this system.

K4.03 Unintentional reduction in vessel injection flow during Clinton is a BWR 6 and does not utilize this system.

accident conditions K4.04 Prevention of piping overpressurization Clinton is a BWR 6 and does not utilize this system.

K4.05 Pump minimum flow protection Clinton is a BWR 6 and does not utilize this system.

K4.06 Pump motor cooling Clinton is a BWR 6 and does not utilize this system.

K4.07 Prevention of water hammer Clinton is a BWR 6 and does not utilize this system.

K4.08 Adequate pump net positive suction head Clinton is a BWR 6 and does not utilize this system.

K4.09 Spray flow cooling Clinton is a BWR 6 and does not utilize this system.

K4.10 Prevention of leakage to the environment through Clinton is a BWR 6 and does not utilize this system.

system heat exchanger K5.01 System venting Clinton is a BWR 6 and does not utilize this system.

K5.02 Pump cavitation Clinton is a BWR 6 and does not utilize this system.

K5.03 Pressure measurement Clinton is a BWR 6 and does not utilize this system.

K5.04 Evaporative cooling Clinton is a BWR 6 and does not utilize this system.

K5.05 Convective cooling Clinton is a BWR 6 and does not utilize this system.

K5.06 Heat exchanger operation Clinton is a BWR 6 and does not utilize this system.

K5.07 Vacuum breaker operation Clinton is a BWR 6 and does not utilize this system.

K6.01 A.C. electrical Clinton is a BWR 6 and does not utilize this system.

K6.02 D.C. electrical Clinton is a BWR 6 and does not utilize this system.

K6.03 Emergency generator Clinton is a BWR 6 and does not utilize this system.

K6.04 Keep fill system Clinton is a BWR 6 and does not utilize this system.

K6.05 Suppression pool Clinton is a BWR 6 and does not utilize this system.

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

K6.07 ECCS room cooling Clinton is a BWR 6 and does not utilize this system.

K6.08 Nuclear boiler instrumentation Clinton is a BWR 6 and does not utilize this system.

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

K6.10 Component cooling water systems Clinton is a BWR 6 and does not utilize this system.

233000 Fuel Pool Cooling and Clean-up K1.07 Condensate system: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K1.I1 Reactor building drainage system: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K6.05 Condensate system Clinton is a BWR 6 and does utilize this configuration.

4/3/03 Page I7 of 26

m___l System # System /Evolution Name KA # K A Statement Basis For Suppression 234000 Fuel Handling Equipment K1.04 Reactor manual control system: Plant-Specific Clinton is a BWR 6 and does utilize this system.

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

K6.02 Reactor manual control system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

239001 Main and Reheat Steam System K1.18 High pressure coolant injection: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.21 Isolation condenser system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.10 High pressure coolant injection system: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.12 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K3.14 Residual heat removal system: Plant-Specific Clinton does not utilize this function.

K5.07 Hydraulic operated MSlVs 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 241 000 Reactorflurbine 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.

K4.11 Load following: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.12 Recirculationflow 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 and Auxiliary 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.

256000 Reactor Condensate System K1.03 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.12 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K1.14 RHR (LPCI): Plant-Specific Clinton does not utilize this function.

K1.17 ECCS keep fill system: Plant-Specific Clinton does not utilize this function from reactor condensate.

4/3/03 Page I8 of26

System # System /Evolution Name KA # K A Statement Basis For Suppression K3.05 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system K3.07 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K4.01 Condensate and/or booster pump auto start: Plant- Clinton does not have an auto start on the CD/CB Specific pumps.

K4.08 Dedicated ECCS water supply: Plant-Specific 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.I8 Fire protection system (emergency cooling): Plant- Clinton does not utilize this function through reactor Specific feedwater.

K1.I 9 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 A I .06 Feedwater string(s) selected for FWCI: FWCl Clinton is a BWR 6 and does not utilize this system.

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

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

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

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

K1.ll Drywell pressure: FWCllHPCl Clinton is a BWR 6 and does not utilize this system.

K1.12 Emergency condensate transfer pump: FWCVHPCI 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 (FWCI) initiation logic: Clinton is a BWR 6 and does not utilize this system.

FWCllHPCl 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.

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

receipt of an ECCS initiation signal: FWCllHPCl K4.16 Dedication of feedwater string@)to ECCS: FWCVHPCI 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: FWCl Clinton is a BWR 6 and does not utilize this system.

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

- 4/3/03 Page 19 of 26

-System ## System /Evolution Name

- - - - m Y w -*

KA # h 3 Statement Basis For Suppression A1.06 Drywell and suppression chamber differential pressure: Clinton is a BWR 6 and does not utilize this Mark-I configuration.

A4.05 Drywell to suppression chamber/torusdifferential Clinton is a BWR 6 and does not utilize this pressure: Mark-1.11 configuration.

K1.06 High pressure coolant injection system: Plant-Specific Clinton is a BWR 6 and does not utilize this configuration.

K3.03 Primary containment pressure: Mark-l&ll Clinton is a BWR 6 and does not utilize this configuration.

K3.04 High pressure coolant injection system: Plant-Specific Clinton is a BWR 6 and does not utilize this configuration.

K3.06 Primary containmentoxygen content: Mark-l&ll Clinton is a BWR 6 and does not utilize this configuration.

262002 Uninterruptable Power Supply (A.C.B.C.)

A I .02 Motor generator outputs Clinton is a BWR 6 and does utilize this configuration.

A2.04 Abnormal battery operation: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

K1.04 Reactor manual control: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K1.07 Rod worth minimizer: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K1.09 Drywell ventilation control: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K1.10 Fire protection system: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K1.13 Recirculation pump speed control: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K1.15 Stack gas monitors: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K1.20 Plant communications equipment: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K3.02 Recirculation pump speed: Plant-Specific Clinton is a BWR 6 and does utilize this Configuration.

K3.04 Fire protection system: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K3.05 Rod worth minimizer: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K3.09 Drywell ventilation control: Plant-Specific Clinton is a BWR 6 and does utilize this configuration.

K5.02 General principles of motor generator operation: Plant- Clinton is a BWR 6 and does utilize this configuration.

Specific K5.03 General principles of inertia fly wheel operation: Plant- Clinton is a BWR 6 and does utilize this configuration.

Specific 264000 Emergency Generators (DieseUJet)

A I .07 Gas generator temperature: Plant-Specific Clinton does not use jet engines to power emergency generators.

A I .08 Gas generator speed: Plant-Specific Clinton does not use jet engines to power emergency generators.

K2.03 Turning gear (jet engine): Plant-Specific Clinton does not use jet engines to power emergency generators.

K2.04 Ignition system (jet engine): Plant-Specific Clinton does not use jet engines to power emergency generators.

K6.04 Turning gear (jet engine): Plant-Specific Clinton does not use jet engines to power emergency generators.

K6.05 Ignition system (jet engine): Plant-Specific Clinton does not use jet engines to power emergency generators.

4/3/03 Page 20 of 26

System # System /Evolution Name KA # K A Statement Basis For Suppression 2 71000 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.

2 72000 Radiation Monitoring 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.I2 Reactor building Clinton is a BWR 6 and does not utilize this system.

K1.I5 Filter building: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

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.

K5.01 Vacuum breaker operation: BWR-4 Clinton is a BWR 6 and does not utilize this configuration.

K5.02 Flow measurement: BWR-3 Clinton is a BWR 6 and does not utilize this configuration.

4/3/03 Page 21 of 26

System # Sysfem/ Evolufion Name KA # Statement Basis For Suppression K6.01 Reactor building ventilation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

K6.07 Auxiliary boiler system: BWR-3, 4 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 Partial or Complete Loss of Forced Core FIow Circulation AA1 .03 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AA1.08 Standby liquid control: BWR-1 Clinton IS a BWR-6 and does not utilize this feature.

4 AK2.05 LPCl loop select logic: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK2.08 Standby liquid control: BWR-1 Clinton is a BWR-6 and does not utilize this feature.

295002 Loss of Main Condenser Vacuum AK3.08 Recirculation system run-backs: Plant-Specific Clinton does not utilize this function.

295003 Partial or Complete Loss of A.C. Power AK2.05 Isolation condenser: Plant-Specific Clinton ISa BWR 6 and does not utilize this system.

AK3.07 Initiation of isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

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

295005 Main Turbine Generator Trip AK2.09 Feedwater-HPCI: BWR-2 Clinton is a BWR 6 and does not utilize this system.

AK3.08 Feedwater-HPCI actuation: BWR-2 Clinton is a BWR 6 and does not utilize this system.

295007 High Reactor Pressure AA1.01 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AA1.02 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AK3.01 Isolation condenser operation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

P 4/3/03 Page 22 of 26

P P --. v 7 - m ---*,.?%->22Zs System # System /Evolution Name

, K4 # KA Statement Basis For Suppression AK3.02 HPCl operation: Plant-Specific 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 HPCl turbine trip: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

29501 0 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-l&ll Clinton is a BWR 6 and does not utilize this system.

AK2.02 Drywelllsuppression chamber differential pressure: Clinton is a BWR 6 and does not utilize this system.

Mark-l&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 111 Containment Only)

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

~ ~~~~

295012 High Dry well Temperature AA2.03 Drywell humidity: Plant-Specific Clinton does not utilize humidity monitoring d

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.O1 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.

295015 Incomplete SCRAM AA1.03 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

AA1.05 Rod worth minimizer: Plant-Specific Clinton is a BWR 6 and does not utilize this component.

AA1.06 RSCS: Plant-Specific Clinton is a BWR-6 and does not utilize this system AK2.02 RMCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system AK2.05 Rod worth minimizer: Plant-Specific Clinton is a BWR 6 and does not utilize this component.

AK2.06 RSCS: Plant-Specific Clinton is a BWR-6 and does not utilize this system AK2.09 RPlS Clinton is a BWR 6 and does not utilize this system.

29501 6 Control Room Abandonment AA1.09 Isolation/emergencycondenser(s): Plant-Specific Clinton is a BWR 6 and does not utilize this system.

p - _I. .

System # System /Evolution Name KA # KA Statement Basis For Suppression AA2.07 Suppression chamber pressure Clinton is a BWR 6 and does not utilize this system.

295019 Partial or CompleteLoss 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/shutdown cooling: Plant- Clinton is a BWRB and does not utilize this feature.

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

EA1.I1 Drywell spray: Mark-1811 Clinton is a BWR 6 and does not utilize this system.

EA1.12 Suppression pool spray: Mark-I811 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 HPCl (FWCI): Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK2.11 Drywell spray (RHR) logic: Mark-1811 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-1811 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 EA1.04 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EA1.06 Isolation condenser: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EA1.08 RRCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

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

EK2.03 RRCS: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

~ W

• l r a u s n S a z .

System # System /Evolution Name KA # liA Statement Basis For Suppression EK2.06 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK3.03 HPCl operation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK3.04 Isolation condenser initiation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK3.07 RRCs initiation: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

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: Mark4811 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-1811 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-l&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.O1 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 EA1.05 HPCl 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-1811 EK2.01 HPCI: Plant-Specific Clinton is a BWR 6 and does not utilize this system.

EK3.02 HPCl 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.

(FWCIIHPCI): 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.

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

29503 7 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.

4/3/03 Page 25 of 26

hL4 # K A Statement Basis For Suppression 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 (US)

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.

Exam Developer Pnnted Name YnC Facility Representative Signature Date 4/3/03 Page 26 of 26

Facility: Clinton Date of Examination: 1/5/2004 Examination Level (circle one): RO Operating Test Number: I Administrative Describe activity to be performed (see Note)

Verify conditions are met to enter Mode 2 from Mode 1 (New)

Conduct of Operations Mode Change KA 2.1.22 (2.8)

Conduct of Operations Determine if Power, Flow, or Core Thermal limits have been exceeded. (Faulted)

Plant Parameter Verification KA 2.1.19 (3.0)

Perform the Restoration Section of a Control Rod/Position Equipment Control Indication Operability Surveillance (Faulted)

KA 2.2.1 2 (3.0)

Determine the dress out requirements for a specified task. (new)

Radiation Control KA2.3.1 (2.6)

N/A Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-I021, Draft Revision 9 22 of 27

NRC Outline Submittal Copy #1

__,-. -- ~For.m-Es-3-o-l-l- - - _-- . -

Es:Bl

~

-\---I----

Administrative ToDics--uutline-Facility: Clinton Date of Examination: 1/5/2004 Examination Level (circle one): SRO Operating Test Number: 1 Administrative Describe activity to be performed (see Note)

Review and approve a Safeguards Event Notification Worksheet for Conduct of Operations a security threat. (New)

Security KA 2.1.18 (3.01 Conduct of Operations Determine if Power, Flow, or Core Thermal Limits have been exceeded. (Faulted)

Plant Parameter Verification KA 2.1 .I9 (3.0)

Review a Completed Control Rod/Position Indication Operability Equipment Control Surveillance and Identify Discrepancies (Faulted)

~

KA 2.2.12 (3.4)

Determine an emergency dose for a job and select a worker to perform the job. (new)

Radiation Control KA 2.3.4 (3.1)

Determine an EP Protective Action Recommendationwith a Emergency Plan subsequent wind direction change.

Protective Action Recommendation KA 2.4.44 (4.0)

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

,cz/ .

NUREG-I021, Draft Revision 9 22 of 27

w W ES-301

- NRC O u t l i n m a--- l._Copy #1 Control Room/ln-Plant System Outline Form ES-301-2 Facility: Clinton Date of Examination: 01/05/04 Exam Level (circle on Operating Test Number: 1 Control Room Systems ;7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Safety Code* Function

a. 202002 Recirculation Flow Control Svstem Reset a Recirc Flow N, s 1 Control Valve Lockout.

b. 209001 Low Pressure Core SDrav Manually Initiate LPCS, Logic Not Available I D,AyS I

c. 241000 Reactornurbine Pressure Regulating Svstem Turbine On-Line Tests

d. 239001 Main and Reheat Steam Equalize Around and Open

~

I NIAIS I Main Steam Isolation Valves

e. 223001 Primary Containment Svstem and Auxiliaries Perform Containment Hydrogen Purge per 4411.06

f. 264000 Emergencv Generators (DieseVJet) Transfer to Diesel Generator 1C due to High Voltage on 4.16 W Line

g. 272000 Radiation Monitorinq Shifting Off-Gas Post Treatment N.S D, s 7 Radiation Monitors

h. 290003 Control Room HVAC Startup the Control Room Ventilation System (VC) in the High Radiation Mode per 3402.01 In-Plant System (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. 201001 Control Rod Drive Hvdraulic Svstem Venting CRD D, p 1 Withdrawal Lines

j. 209002 Hish Pressure Core SDrav Throttling ECCS Injection D, R, L 2 Flow - HPCS

k. 263000 D.C. Electrical Distribution DC Load Shedding during a Station Blackout

~~

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate qath, (C)ontrol 23 of 27 NUREG-I021, Draft Revision 9

ES-30 1 Control Room/ln-Plant System Outline Form ES-301-2 Operating Test Number: 1 Control Room Systems (8 for &UcdSRO-l; 2 or 3 for SRO-U)

System / JPM Title I Type Code*

Safety Function

a. 202002 Recirculation Flow Control Svstem Reset a Recirc Flow 1 Control Valve Lockout.

b. 209001 Low Pressure Core SDrav Manually Initiate LPCS, Logic 2 Not Available

c. 241000 Reactornurbine Pressure Requlatinn Svstem Turbine 3 On-Line Tests

d. 239001 Main and Reheat Steam Equalize Around and Open 4 Main Steam Isolation Valves

- e. 223001 Primarv Containment Svstem and Auxiliaries Perform 5 Containment Hydrogen Purge per 441 1.06 W '

g. 272000 Radiation Monitoring Shifting Off-Gas Post Treatment 7 Radiation Monitors

h. 290003 Control Room HVAC Startup the Control Room 9 Ventilation System (VC) in the High Radiation Mode per 3402.01 In-Plant System (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. 201001 Control Rod Drive Hvdraulic Svstem Venting CRD 1 Withdrawal Lines

i. 209002 Hiqh Pressure Core Swav Throttling ECCS Injection 2 Flow - HPCS

k. 263000 D.C. Electrical Distribution DC Load Shedding during a 6 Station Blackout

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, @)imulator, &)ow Power, (R)CA 23 of 27 NUREG-I021, Draft Revision 9

_ _ ..I _ _ __ NRC Outline Submittal Copy #1 ES-301 Control Roomlln-Plant System Outline Form ES-301-2 Facility: Clinton [\ Date of Examination: 01/05/04 1

Exam Level (circle one): RO / SRO(I) SROCU) Operating Test Number: I Control Room Systems (8 for RO; 7 f o r w o r 3 for SRO-U)

System / JPM Title Safety

a. 202002 Recirculation Flow Control Svstem Reset a Recirc Flow Control Valve Lockout.

c. 241000 Reactornurbine Pressure Requlatinn Svstem Turbine On-Line Tests

h. 290003 Control Room HVAC Startup the Control Room N,A,S D, A, s I 9 Ventilation System o/C) in the High Radiation Mode per 3402.01 In-Plant System (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. 209002 High Pressure Core Sprav Throttling ECCS Injection D, R, L 2 Flow - HPCS

k. 263000 D.C. Electrical Distribution DC Load Shedding during a Station Blackout D,R,L I 6

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol 23 of 27 NUREG-I021, Draft Revision 9

Examiners: Operators:

nitial Conditions:

B A startup is in progress with power at 55%

the 100% rod line

, _ . . . - - .._.l,

.. .. Tumover:

t Continue with power ascension IAW GP.

Event Description RO I R Wlthdrawrods to the 100%rod line SRO Uncoupled Confrol Rod Loss of a CRD Pump 4 I RR15AA I I I RO Feedwater Level control Signal Failure Loss of Bus I J (restore Cycled Condensate)

OG Recombiner Level ControllerFailure BOP 7 RR03 Ad RO LOCA due to small Reactor Recirc leak I I 1 SRO 8 I/O I C I R O Fail Mode Switch in RUN RO 9 RP04 Auto scram failure,ARI successful SRO 10 EDO4C1 C BOP Loss ofDivision 3 bus I1 YARIMMP(2) c BOP RClC ir?jeciionvalve failsto open I I I

- __ ._ -- I - - _- --

I ~

(N)ormal, (R)eaCtivity, (I)nstru nent, (C)omponent, (M)ajor Transient

- ~ - .NRC Outline Submittal Copy # 1 Narrative Summary need to be used initially to control reactor pressure.

10 A loss of the DIV 3 Emergency Bus will cause a loss of HPCS 11 The RClC injection valve failure will then cause a loss of all high capacity high pressure injection Critical Tasks Performing Alternate Rod Insertion Performing Emergency Depressurization if cannot stay inside Figure N.

EOPs Entered EOP-1, RPV Control EOP-6, Primary Containment Control EOP Contingencies Entered EOP-3 Emergency RPV Depressurization

J-- __ly - Scenario Outline Facility: Clinton Power Station Scenario No.: NRC 1.2 Op Test No.: I Examiners: Operators:

Initial Conditions:

The Unit is operating at 80% reactor power following valve testing.

SLC Pump A is out of service.

Emergency Reserve Transformer out of service for bushing replacement.

Turnover:

Raise reactor power to 90%.

ShiR WTpumps to allow routine maintenance on pump.

Event No. I Malf. No.

I Event Type* Event Description I MA I RO SRO BOP Raise reactor power to 90%.

2 MA Swap WT Pumps SRO SRO rr 3 PCO7A A Drywell Chiller trips BOP yp_xMFTB c RO 4 A Control Rod driffs out.

SRO 5

(4127)

YP-XRUIAT (782)

, BOP SRO Standby air compressws fail to start on low air pressure and must be manual& started.

RO Instrument air header leak eventually causes multiple control rod driiis 6 IAOID requiring a manual Scram be inserted.

SRO 7 RPO3A M ALL A M , hydraulic lock.

RO 8 SLOl B SLC Pump B &ipsshortly d e r starting requiring alternate boron injection.

SRO

• (Nbrmal, (Rbactivity, (I)nstrument, (C)omponent, (M)ajor Transient

Narrative Summary Description Once the turnover is completed, The SRO should direct the RO to raise power to 90%

using recirculation flow.

The SRO should also direct the BOP to swap WT pumps to facilitate maintenance activities.

The running Drywell chiller trips requiring the shifting of the drywell fans, chilled water pumps, CCP chilled water supply and starting the standby drywell chiller.

Once Drywell cooling has been restored a control rod will begin drifting-outof the core.

The RO will respond per the abnormal procedure and fully insert the control rod. The SRO will refer to technical specification and declare the control rod inoperable and determine appropriate tech spec and administrative actions for the failure.

The instrument air header leak will require entry into the abnormal operating procedure and the standby air compressors will fail to start automatically requiring the BOP operator to start them to attempt to maintain air header pressure.

An instrument air header leak will occur and eventually will cause multi'ple-control rod drift alarms. The RO will manually scram the reactor based on this condition.

When the RO inserts a manual scram an A M l S hydraulic lock will occur, This will require the RO to perform alternate control rod insertions that will be complicated by the loss of control air pressure. Once actions have been taken to reduce reactor water level to control power and alternatq, boron injection has been directed the instrument air header leak will be reported as isolated allowing the crew to reset the scram and insert control rods.

The MSlVs will close due to loss of air pressure resulting in the BIT being approached.

The crew will start SLC, 15 seconds after SLC is started the pump will trip requiring Alternate Boron injection.

Critical Tasks Crew maintains reactor water level to suppress reactor power.

Inserting control rods to reduce power.

h EOPs Entered EOP-6, Primary Containment Control EOP ContingenciesEntered EOP-IA, ATWS RPV Control

-az 3

NRC Outline Submittal Copy #1 Facility: Clinton Power Stai5on Scenario No.: NRC 1.3 Op Test No.:

Examiners: Operators:

Initial Conditions:

A startup is in progress wifh power currently at 8% reactor power.

Mode switch has just been placed in RUN.

CRD A is out of service for motor replacement.

Turnover:

0 Continue with power ascension IAW GP.

Event No. Malf. No. Event Type* Event Description I MA R I Ro SRO Raise reactor p o w r with control rods.

Ro 2 LS02 I Control rod reed switch failure.

SRO BOP 3 I/O C Auto start of SX Pump with failure of SX isolation vafve to close.

SRO 4 HPI3H Inadvertent opening of an ADS SRV SRO

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5 PCIlB Inadvertent dump of the Upper Containment Pool I SRO RO 6 RR02A Reactor RecirculationPump Trip SRO 7 M All Seismic event causing LPCS suction line break (Unisolabie) 8 w-mfw C RO LossofMDRFP

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

NRC Outline Submittal Copy #I Event(s) Description I The SRO should direct the RO to continue the power increase with control rods.

2 While pulling control rods a reed switch fails requiring the use of substitute position.

3 A shutdown service water pump auto starts and the isolation valve fails to close.

This requires closing the valve with the hand switch. SRO must evaluate Tech Specs.

4 Inadvertent opening of an SRV requires entry in CPS 4009.01 Inadvertent opening safetyhelief valve and CPS 4005.01 Loss of feedwater heating. The SRV closes on the first attempt. The ADS SRV should be declared inop and the Tech Spec LCO entered 5 An inadvertent dump of the upper containment pool requires entry into EOP-6 on high suppression pool level.

6 A reactor recirculation pump trip requires actions for single loop.

7 A seismic event causes a LPCS suction line break that requires a scram and blowdown due to low suppression pool level.

-. .- 8 I A trip of the MDRFP requires transferring to another feedwater source.

Manually Scram prior to Emergency Depressurization.

Emergency Depressurize prior to Suppression Pool level reaching 15 1.

EOPs Entered EOP-8, Secondary Containment Control EOP-6, Primary Containment Control EOP-I ,RPV C~ntrol EOP Contingencies Entered EOP-3, Emergency RPV Depressurization

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