ML032461297

Facility Ltr. Dtd 05/20/03 Draft/Final - Outlines

ML032461297
Person / Time
Site:	FitzPatrick
Issue date:	07/21/2003
From:	Berry P FitzPatrick
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-333/03-301
Download: ML032461297 (49)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations. Inc.

James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel315 349 6024 Fax 31 5 349 6480 T.A. Sullivan Vice President, Operations-JAF May 20, 2003 JAFP-03-0071 Mr. J. Williams, Examiner/Inspector United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 SUBJECT James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Licensed Operator Initial Examination Outlines

Dear Sir:

In accordance with NUREG-102 1 Draft Revision 9, please find the attached Initial License Examination written and operating outlines. Random sampling for written.:s items was completed per ES-401, Attachment 1.

Should you have any question concerning this report, please direct them to Mr. Richard DeVercelly, Senior Operations Instructor, at (3 15) 349-6074.

Very truly your&

TAS :PJB : SR: sr Enclosure

cc:

US. Nuclear Regulatory Commission ATTN: Document Control Desk Mail stop 0-P 1 - 17 Washington, DC 20555 Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Guy Vissing, Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop O W N 8C2 Washington DC 20555 Office of the Resident Inspector James A. Fitzpatrick Nuclear Power Plant U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. B. OGrady (JAF)

Mr. D. Johnson (JAF Mr. P. Berry (JAF)

Ms. C. Faison (WPO)

Mr. A. Halliday (JAF)

JAFP File JTRG File RMS - JAF

SAMPLE PLAN CHANGES 5/20/03 RO Emergency Plan JPM 0 Originally to perform an EAP-1.1 off site notification communicator hction.

In reviewing, it was determined that this JPM was too similar to a JPM performed in the last NRC examination.

The WA 2.4.43 was retained and the JPM changed to complete a related emergency communication function, which activates the ERO per EAP-17.

RO/SRO JPM (c) to conduct Emergency Rod In Functional Test Upon further review it was discovered that this JPM was an alternate path JPM This brings the total to 5 Alternate Path JPMs. Still within the guidance of 4-6.

Walkthrough Outline pages 1,3,5 and 7 updated th reflect alternate path status.

LOI-03-0 1 NRC/AUDIT EXAMINATION OVERLAP MATRIX ST Results ST Results RO Admin JPM RO Admin JPM ST-SDIE NIA 5

6 111 2.1.7 NIA RO Admin JPM NIA 2.4.43

ES-401 BWR SI33 Examination Outline Form ES-401-1 11 Facilitv:

I James A FitzPatrick Date of Exam:

7/21-2513 mn-h&

II I

I RO WA Category Points 11 SRO-Only Points

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 21 from that specified in the table based on NRC revisions. The final RO exam must total 1-88 75 points and the SRO-only exam must total 25 points.

Select topics from many systems and evolutions; avoid selecting more than two w

1. wee WA topics from a given system or evolution unless they relate to plant-specific priorities.

Systemdevolutions within each group are identified on the associated outline.

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

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.

On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) for the SRQ applicable license level, and the point totals for each system and category. 4Wb-kbw 2.5 5 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.

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

Refer to ES-401,, for guidance regarding the elimination of inappropriate WA statements.

3.

4.

5.

6.*

It

7.

8.

9.

Page 1 of27 Created on 5/7/2003 1 1 :24 AM

Form ES-401-1 10CRF-55.43 b related topica ES-401 BWR S4-Q Examination Outline Emergency and Abnormal Plant Evolutions - Tier l/GrouD 1 Cae / SROf ElAPE # / Name / Safety Function K

1 295016 Control Room Abandonment I 7 295019 Partial or Total Loss of Inst. Air I 8 295025 High Reactor Pressure I 3 K/A Topic(s)

Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF AX. POWER :

(CFR 41.10 /43.5/ 45.13)

AA2.05 Whether a partial or complete loss of A.C. power has occurred 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation.

(CFR: 45.2 / 45.6)

Link to 10CFR-55.43(bX6)

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :(CFR: 41.10 /43.5 / 45.13)

AA2.01 Instrument air system pressure implications of the following concepts as they apply to REFUELING ACCIDENTS :(CFR 41.8 to 41.10)

AK I.O I Radiation exposure hazards Also 10CFR-55.43 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:

(CFR: 41.10/43.5/45.13)

EA2.05 Decay heat generation Page 2 of 27 Created on 5/7/2003 1 1 :24 AM

B W R SRQ Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1IGroup 1 (RQ I SRO)

Form ES401-1 10CRF55.43 b related topics ES-401 EIAPE # I Name I Safety Function 295030 Low Suppression Pool Wtr Lvl I 5 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 WA Category Totals:

1 2

WA Topic@)

Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL

(CFR: 41.10 /43.5 / 45.13)

EA2.04 Drywell/ suppression chamber differential pressure: Mark-I&II NOT RANDOMLY SELECTED Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR 41.10 143.5 / 45.13)

EA2.05 Control rod position 2.2.10 Knowledge of the process for determining if the margin of safety / as defined in the basis of any technical specification is reduced by a proposed change /

test or experiment.

(CFR 43.3 / 45.13)

Link to 1 OCFR-55.43@)(2)

IR 3.7 4.3 Page 3 of 27 Created on 5/7/2003 1 1 :24 AM

ES-401 BWR Scua Examination Outline Form ES-401-1 10CRF-55.43 b related topics Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 fae 1 SRO)

EIAPE # I Name I Safety Function 295014 Inadvertent Reactivity Addition I 1

295022 Loss of CRD Pumps I 1 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High SumpIArea Water Level I 5 1(0 o(0 211 KIA Topic@)

Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTIVITY ADDITION :

(CFR: 41.8 to 41.10)

AKl.01 Prompt critical Also 10CFR-55.43(b)(6)

Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS : (CFR 41.10 /43.5 145.13)

AA2.02 Cm svstem status performing a containment puEe.

(CFR 43.;/

45.10)

Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL:

(CFR: 41.10/43.5/45.13)

EA2.01 Operability of components within the affected area.

CT Group Point Total:

3.4 3.4 3.2 Page 4 of 27 Created on 5/7/2003 1 1 :24 AM

IS-401 Form ES-401-1 10CRF-55.43 b related topics BWR SRQ Examination Outline W / SRO)

System # I Name 21 1000 SLC 215005 APRM I LPRM 21 7000 RCIC

?4JBmms 223002 PClSlNuclear Steam Supply Shutoff Plant Systems -Tier 2lGroup WA Topic@)

loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:

(CFR 41.7 / 45.4)

K3.02 Core spray line break detection system: Plant-Specific Link to lOCFX-55.43@)(2) 2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.

(CFR 41.10 / 43.5 /45.12)

Knowledge of electrical power supplies to the following:

(CFR: 41.7)

K2.04 Gland seal compressor (vacuum pump)

Link to 10CFR-55.43@)(2)

NOT RANDOMLY SELECTED Knowledge of electrical power supplies to the following:

(CFR 41.7)

K2.01 Logic power supplies Link to 10CFR-55.43@)(5) 2.6 S56 Page 5 of 27 Created on 5/7/2003 1 1 :24 AM

Page 6 of 27 Created on 5/7/2003 1 1 :24 AM

s-401 BWR SRQ Examination Outline Plant Systems -Tier 2IGroup 2 (+?Q / SRO)

~~

jystem # I Name 239001 Main and Reheat Steam 10CRF-55.43 brelated topics I K/A Topic@)

I Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR 41.5 / 45.6)

A2.0 1 Malfunction of reactor turbine pressure regulating system Link to 10CFR-55.43@)(5)

NOT RANDOMLY SELECTED I

Page 7 of 27 Created on 5/7/2003 1 1 :24 AM

ES-401 System # I Name 271000 Offgas WA Category Point Totals Page 8 of 27 BWR SW Examination Outline Plant Systems -Tier 2lGro Form ES-401-I 10CRF55.43 b related topics K/A Topic@)

associated with operating the OFFGAS SYSTEM controls including: (CFR: 41.5 / 45.5)

Created on 5/7/2003 1 1 :24 AM

WA# I Topic RO I SRC 2.2.17 2.2.6 Subtotal 2.2.32 2.2.

2.2.

2.2.

ES-40 1 Facility: James A FitzPatrick Category Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-53 SRO Only 1 OCRF-55.43 b related topics Date of Exam: 7/21 -25/03

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control (CFR: 43.6)

I l

l 2.3.6 and contamination control / including permissible levels in excess of those authorized. (CFR: 43.4 / 45.10) reviewing and approving release permits.

(CFR: 43.4 / 45.10)

Subtotal I

I I

3nly 0

S70 S72 2

s74 S76 2

Page 9 of 27 Created on 5/7/2003 1 1 :24 AM

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

Form ES401-53 Facility: James A FitzPatrick SRO Only 1 OCRF-55.43 b related topics Date of Exam: 7/21 -25/03 WA #

2.4.47 2.4.16 2.4.30 2.4.22 2.4.

2.4. -

hierarchy and coordination with other support procedures. (CFR: 41.10 / 43.5 /

45113)

I l

l I

I I

Knowledge of which events related to I 3.6 system operations/status should be reported to outside agencies.

(CFR: 43.5 / 45.1 1)

(CFR: 43.5 / 45.12)

I l

l

-Only s94 S96 S I 00 3

Page 10of27 Created on 5/7/2003 1 1 :24 AM

Tier I Group 1 11-2 I12 1 214 2 211 2 212 212 213 2 213 2 212 Randomly Selected WA 500000 EA1.04 29501 9 AKI.XX 226001 K5.01 290001 K1.06 201001 K2.07 271000 K2.01 215001 K2.01 215001 A2.04 271000 A1.04 Note 1:

Note 2:

Reason for Rejection See Notes Below No JAF procedural direction to operate Dwell Recirculation (Cooling) Fans to control containment hykogen. Note 1 No WAS exist under AKI. Note 1 Importance rating at 2.2 (<2.5) and no plant priority to justify.

Note 1 NIA JAF BWR-6 only. Note 1 Importance rating at 2.1 (~2.5) and no plant priority to justify.

Note 1 Importance rating at 1.5 (~2.5) and no plant priority to justify.

Note 1 Importance rating at 2.1 (<2.5) and no plant priority to justify.

Note 1 Importance rating at 2.0 (~2.5) and no plant priority to justify.

Note I Importance rating at 2.4 (<2.5) and no plant priority to justify.

Note 2 Rejected during generation of rbvision 8 outline. Strike out indicates change in tiedgroup from rev 8 to rev 9.

Rejected during conversion from rev 8 to pilot rev 9 outline.

Tiedgroup is as described in rev 9.

Page 11 of 27 Created on 5/7/2003 1 1 :24 AM

BWR SR0 Examination Outline Emergency and Abnormal Plant Evolutions -Tier IlGroup 1 (RO I SRO)

Form ES-401-1 IR 2 32.9 WA Topic(s) 2.3.2 Knowledge of facility ALARA program.

(CFR: 41.12 / 43.4 / 45.9 / 45.10)

ElAPE # I Name I Safety Function 1 12 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I6 295004 Partial or Total Loss of DC Pwr I6 295005 Main Turbine Generator Trip I 3

~

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Cause of partial or complete loss 0fA.C. power Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following: (CFR: 41.7 / 45.8)

AK2.01 Battery charger Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: (CFR: 41.7 / 45.8)

AK2.07 Reactor pressure control Knowledge of the operational implications of the following concepts as they apply to SCRAM :

(CFR: 41.8 to 41.10)

AK 1.03 Reactivity control 213 3.413.7 3.113.1 3.613.7 3.714.0 314 415 516 11 295006 SCRAM I 1 Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following:

(CFR: 41.7 / 45.8)

AK2.03 Control room HVAC 2.913.1 6ff 295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I 8 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :

(CFR: 41.8 to41.10)

AK1.O1 Effects on componentlsystem operations 3.513.6 718 2.2.26 Knowledge of refueling ad ministrat ive requirements.

(CFR 43.5 / 45.13) 2.513.7 819 Page 12 of 27 Created on 5/7/2003 1 1 :24 AM

K A

3 1

1 1

1 ES-401 BWR SI20 Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier l/Group 1 (RO I SRO)

KIA Topic@)

911 0 IR EIAPE # I Name I Safety Function 295021 Loss of Shutdown Cooling I 4 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.7 / 45.6)

AA 1.04 Alternate heat removal methods 3.713.7 Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS :

(CFR: 41.5 / 45.6)

AK3.02 Interlocks associated with fuel handling equipment 3.413.8 1011 1 295023 Refueling Acc Cooling Mode I 8 Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE : (CFR: 41.8 to 41.10)

EK1.01 Drywell integrity: Plant-Specific 4.114.2 11112 295024 High Drywell Pressure I 5 Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:

(CFR: 41.7 / 45.6)

EA1.07 ARI/RPT/ATWS: Plant-Specific 4.114.1 12113 Ability to determine andlor interpret the following as they apply to HIGH REACTOR PRESSURE:

(CFR: 41.10 / 43.5 / 45.13)

EA2.06 Reactor water level Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE :

(CFR 41.8 to 41.10)

EK1.O1 Pump NPSH N/A JAF. MARK Ill ONLY Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Drywell temperature 3.713.8 3.013.4 1311 6 1411 7 295028 High Drywell Temperature I 5 4.014.1 1511 8 Page 13 of 27 Created on 5/7/2003 1 1 :24 AM

Form ES-401-1 ES-401 BWR SRQ Examination Outline Emergency and Abnormal Plant Evolutions - Tier 11Group 1 (RO I SRO)

EIAPE # I Name I Safety Function 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2 r

11 295037 SCRAM Condition Present and 295038 High Off-site Release Rate I9 600000 Plant Fire On Site / 8 Note 1 Note 1: Randomly selected during ll conversion from rev 8 to pilot rev 9 outline KIA Topic@)

2.4.48 Ability to interpret control room indications to verify the status and operation of system / and understand how operator actions and directives affect plant and system conditions.

(CFR 43.5 / 45.12)

Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL :

(CFR 41.5 / 45.6)

EK3.01 Automatic depressurization system actuation Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR 41.10 / 43.5 / 45.13)

EA2.02 Reactor water level Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following:

(CFR: 41.7 / 45.8)

EK2.02 Offgas system Ability to operate and / or monitor the following as they apply to PLANT FIRE ON SITE:

AAI.06 Fire alarm IR 3.513.8 3.914.2 4.114.2 3.613.8 3.013.0 16/19 17120 18/21 19122 20123 Page 14 of 27 Created on 5/7/2003 1 1 :24 AM

BWR SFS Examination Outline Emergency and Abnormal Plant Evolutions -Tier IIGrouD 2 (RO I SRO)

E/APE # I Name I Safety Function 295002 Loss of Main Condenser Vac I3 295007 High Reactor Pressure I3 295014 Inadvertent Reactivity Addition I 1 Form ES-401-1 WA Topic(s)

IR Ability to determine andor interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM :

(CFR: 41.10 143.5 1 45.1 3) 2.913.1 AA2.0 1 Condenser vacuum/absolute pressure Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following:

(CFR 41.7 / 45.8)

AK2.04 LPCS 3.213.3 1 Knowledge of the interrelations between INADVERTENT REACTIVITY ADDITION and the following: (CFR: 41.7 / 45.8) 2.3.10 Ability to perform 2.913.3 procedures to reduce excessive levels of radiation and guard against personnel exposure.

(CFR: 43.4 / 45.10) 21/24 22125 23/26 24/28 Page 15 of 27 Created on 5/7/2003 1 1 :24 AM

BWR Si40 Examination Outline Emergency and Abnormal Plant Evolutions - Tier l1GrouP 2 (RO / SRO)

Form ES-401-1 ES-401 EIAPE # I Name I Safety Function K

1 295033 High Secondary Containment Area Radiation Levels I 9 295036 Secondary Containment High SumpIArea Water Level I 5 500000 High CTMT Hydrogen Conc. I 5 WA Category Point Totals 0

WA Topic@)

Ability to operate and/or monitor the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS :

(CFR: 41.7 / 45.6)

EA1.05 Affected systems so as to isolate damaged portions Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL

(CFR 41.5 / 45.6)

EK3.01 Emergency depressurization Ability to operate and monitor the following as they apply to HIGH CONTAINMENT HYDROGEN CONTROL: (CFR: 41.7 / 45.6)

EA 1.06 Drywell sprays Group Point Total:

IR 3.914.0 2.612.8 3.313.4 25/29 26/31 27/32 714 Page 16 of 27 Created on 5/7/2003 1 1 :24 AM

ES-401 Form ES-401-1 BWR SR0 Examination Outline Plant Systems -Tier 2lGroup 1 (RO / SRO)

System # I Name 203000 RHRILPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCl 209001 LPCS KIA Topic(s)

Ability to predict and/or monitor changes in parameters associated with operating the RHWLPCI:

INJECTION MODE (PLANT SPECIFIC) controls ncluding: (CFR: 41.5 / 45.5)

AI -05 SUDD~eSSiOIl DO01 level Ability to manually operate and/or monitor in the control room:

(CFR 41.7 / 45.5 to 45.8)

A4.11 Indicating lights and alarms Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: (CFR 41.7 / 45.4)

K3.04 Recirculation loop temperatures 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. (CFR.

41.12 / 43.4. 45.9 / 45.10)

Knowledge of the physical connections andfor cause effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.07 D.C. power: BWR-2,3,4 ISOIAT SYSTE 2.2.13 Knowledge of tagging and clearance procedures.

(CFR: 41.10 / 45.13)

IR 3.813.7 3.713.5 3.713.7 2.613.0 28/33 29/36 30137 31/39 32144 33/45 Page 17 of 27 Created on 5/7/2003 1 1 :24 AM

BWR SR0 Examination Outline Form ES-401-1 ES-401

~

Plant Systems -Tier ZlGroup 1 (RO I SRO)

IR KIA Topic@)

Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following: (CFR: 4 1.7 / 45.4)

K3.02 ADS logic 34146 N/A JAF. NO HIGH PRESSURE CORE SPRAY SYSTEM 2.1.9 Ability to direct personnel activities inside the control room.

(CFR: 45.5 / 45.12 / 45.13) 2.514.0 35/47 Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM : (CFR: 41.5 145.3)

K5.02 Specific logic arrangements 3.313.4 36\\48 1

3.513.5 37/49 Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including: (CFR 41.7 / 45.7)

A3.04 Control rod block status Ability to monitor automatic operations of the SOURCE RANGE MONITOR (SRM)

SYSTEM including:

(CFR 41.7 / 45.7)

A3.04 Control rod block status Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITORLOCAL POWER RANGE MONITOR SYSTEM including: (CFR: 41.7 / 45.7)

A3.02 Full core display Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on following:

(CFR: 41.7 / 45.4)

K3.0 1 Reactor water level 1

3.613.6 38/50 1

39/51 3.513.5 3.713.7 1

40153 Page 18 of 27 Created on 5/7/2003 1 1 :24 AM

BWR SiW Examination Outline Plant Systems -Tier 2IGroup 1 (RO I SRO WA Topic(s)

Ability to monitor automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: (CFR 41.7 / 45.7)

A3.06 Lights and alarms Knowledge of the physical connections and/or cause effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following:

(CFR 41.2 to 41.9 / 45.7 to 45.8)

K 1.06 Safetdrelief valves Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMNJCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR 41.5 / 45.6)

A2.04 Process radiation monitoring system failures 2.1.10 Knowledge of conditions and limitations in the facility license.(CFR: 43.1 / 45.13)

Knowledge of the physical connections and/or cause effect relationships between RELIEF/SAFETY VALVES and the following:

(CFR 41.2 to 41.9 / 45.7 to 45.8)

K1.O1 Nuclear boiler Form ES-401-1 R

3.513.4 3.913.9 2.913.2 2.713.9 3.813.9 41/54 42157 43/58 44/60 45/62 Page 19 of 27 Created on 5/7/2003 1 1 :24 AM

BWR SRQ Examination Outline Plant Systems -Tier 2lGroup 1 (RO I SRO)

Form ES-401-1 KIA Topic(s)

Knowledge of the physical connections andor cause effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following:

(CFR41.2to41.9/45.7to 45.8)

K 1.13 Condensate system Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM Will have on following:

(CFR: 41.7 /45.6)

K3.05 Secondary containment radiation/ contamination levels Knowledge of electrical power supplies to the following:

(CFR 4 1.7)

K2.0 1 Off-site sources of power 2.2.13 Knowledge of tagging and clearance procedures.

(CFR: 41.10 / 45.13)

Ability to (a) predict the impacts of 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:

(CFR: 41.5 / 45.6)

A2.01 Grounds Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET) :

(CFR: 41.7 / 45.7)

K6.02 Fuel oil pumps IR 3.213.2 3.213.5 3.313.6 3.613.8 2.813.2 3.613.6 U

46/63 47/64 48/65 49/66 50168 51/69 Page 20 of 27 Created on 5/7/2003 1 1 :24 AM

ES-401 System # I Name 300000 Instrument Air 400000 Component Cooling Water WA Category Point Totals Page 21 of 27 BWR SR0 Examination Outline Plant Systems -Tier 2lGroup 1 (RO / SRO)

K K

2 3

1 K

K 4

5 A

A 3

4 K/A Topic(s)

Knowledge of the connections and I or cause effect relationships between INSTRUMENT AIR SYSTEM and the following:

(CFR 41.2 to 41.9 /45.7 to 45.8)

K1.05 Main Steam Isolation Valve air Knowledge of electrical power supplies to the following:

(CFR 41.7)

K2.01 CCW pumps Group Point Total:

Form ES-401-1 IR 3.113.2 2.9/3.0 Created on 5/7/2003 1 1 :24 AM 5217 1 53/73 2644

ES-401 201001 CRD Hydraulic BWR SR0 Examination Outline Plant Systems -Tier 2/Group 2 (RO / SRC KIA Topic(s)

Knowledge of electrical Jower supplies to the rollowing: (CFR 41.7)

(2.03 Backup SCRAM valve

olenoids WNDOMLY DESELECTED 3URING REV 8 TO REV 9 ZONVERSION Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations

(CFR: 41.5 / 45.6)

Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.06 Selected rod position indication:P-Spec(-B WR6)

D RANDOMLY DE-SELECTED CONVERSION Knowledge of REACTOR WATER CLEANUP SYSTEM design feature(s) and/or interlocks which provide for the following:

(CFR 4 1.7)

K4.03 Over temperature protection for system corn ponen t s Ability to monitor automatic operations of the ROD POSITION INFORMATION SYSTEM including: (CFR 41.7 / 45.7)

A3.02 Alarm and indicating lights R

5.513.6 3.413.6 3.213.2 2.912.9 3.213.1 U

54/75 55/77 56/78 57/79 58/80 Page 22 of 27 Created on 5/7/2003 1 1 :24 AM

BWR SR0 Examination Outline Plant Systems -Tier 2lGroup 2 (RO I SRO)

Form ES-401-1 ES-401 IR 2.712.8 K/A Topicis)

NOT RANDOMLY SELECTED Ability to predict andlor monitor changes in parameters associated with operating the ROD BLOCK MONITOR SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.O1 Trip reference: BWR-3 34s Knowledge of the effect that a loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION :

(CFR 41.7 / 45.7)

K6.01 A.C. electrical System # I Name 59/81 215002 RBM 21 6000 Nuclear Boiler Inst.

3.113.3 60182 Knowledge of the physical connections and/or cause effect relationships between RHWLPCI:

CONTAINMENT SPRAY SYSTEM MODE and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.I2 Suppression pool (spray Denetration): Plant-SDecific 3.013.0 61183 226001 RHRILPCI: CTMT Spray Mode 230000 RHWLPCI: ToruslPool Spray Mode 3.813.6 62/84 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.02 Spray valves Knowledge of FUEL POOL UP design feature(s) andlor interlocks which provide for the following:

(CFR: 41.7)

K4.03 Maintenance of adequate pool temperature COOLING AND CLEAN-233000 Fuel Pool CoolinglCleanup 2.W3.1 63185 Created on 5/7/2003 1 1 :24 AM Page 23 of 27

I l 4 O l Form ES-401-1 BWR Si4-Q Examination Outline WA Category Point Totals 1

1 1

2 1

1 1

1 0 / SRO)

A A

G WA Topic@)

IR 3

4 operational Implications of the following concepts as they apply to REACTOWURBINE PRESSURE REGULATING SYSTEM :

(CFR 41.5 / 45.3)

K5.05 Turbine inlet pressure vs. turbine load I

I I Knowledgeoftheeffectthat I 4.014.4 a loss or malfunction of the SECONDARY CONTAINMENT will have on following:

(CFR 41.7 / 45.4)

K3.01 ?Off-site radioactive 64/86 65/87

=

1 a2 Page 24 of 27 Created on 5/7/2003 1 1 :24 AM

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

Form ES401-53 1 Facility: JamesA.

Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control FitzPatrick Date of Exam: 7/21 -25103 Topic 2.1.32 2.1.29 Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12)

Knowledge of how to conduct and verify Subtotal 2.2.1 Ability to perform pre-startup procedures for the facility 1 including operating those controls associated with plant equipment that could affect reactivity. (CFR: 45.1)

Knowledge of surveillance procedures.

(CFR 41.10 / 45.13)

Knowledge of the process for determining the internal and external effects on core 2.2.1 2 2.2.34 Subtotal 2.3.9 Knowledge of the process for performing a containment maze.

(CFR 43.4 / 45110)-

Knowledge of 10 CFR: 20 and related facility 2.3.1 I radiation control requirements.

Subtotal RO SRO-Only IR IR 3.4 66 3.8 88 3.4 67 3.3 89 Page 25 of 27 Created on 5/7/2003 1 1 :24 AM

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

Form ES-401-53

=acility: James A. FitzPatrick Date of Exam: 7/21 -25/03

~

RO 2.4.15 Knowledge of communications 3.0 73 procedures associated with EOP implementation.

(CFR 41.10 / 45.13) requirements including fire brigade and portable fire fighting equipment usage.

2.4.26 Knowledge of facility protection 2.9 74

4.

Emergency Procedures I Plan SRO-Only 3.5 97 3.3 98 2.4.39 (CFR 43.5 / 45.12)

Knowledge of the RO's responsibilities in 3.3 75 3.1 99 emergency plan implementation.

Subtotal Page 26 of 27 5

431 0 Created on 5/7/2003 1 1 :24 AM

Tier I Randomly Selected Group WA Reason for Rejection See Note Below 1 Rejected during outline review due to oversampling Importance rating at 2.3 (~2.5) and no plant priority to justify 1

3 2.2.18 11 3

1 2.3.4 Note I Rejected during outline review due to oversampling All rejected during generation of revision 8 outline. No additional rejections during rev 8 to rev 9 conversion. Strike out indicates change in tiedgroup from rev 8 to rev 9.

Page 27 of 27 Created on 5/7/2003 1 1 :24 AM

SROI JPM MATRIX JPM ID JPM NUMBER JPM BRIEF DESCRIPTION SAFETY FUNCTION SIMULATOR DUPLICATION DIRECT FROM BANK (< 80%)

MODIFIED FROM BANK NEW FROM LAST LO1 EXAM c 30%)

hl OR LOW POWER (2 1)

ALT. PATH EOPlAOP ACTION (2 1)

RCA ENTRY LINKED TO SIM EXAM (4-6)

(> 1) -

IN PLANT SYSTEMS 3 DIFFERENT SECTION 1.9 (3 JPMs)

CONTROL ROOM SYSTEMS 7 DIFFERENT SECTION 1.9 SAFETY FUNCTIONS (7 JPM's)

Page 1 of8 Created on 4/17/2003 1 :3 1 PM ADMIN TOPICS (5 JPMs)

J J

J J

J

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

James A. FitzPatrick Date of Examination:

21-25 July, 2003 Examination Level (circle one): =lW / SRO Operating Test Number:

Administrative Topic -

4%sw@m- (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control M

Emergency Plan Describe activity to be performed

2. -

L P

Given plant conditions, apply technical specifications and complete LCO tracking documentation. Possible references include TIS, AP-03.1 1 and AP-12.08 WA 2.1. 1 2 Given plant conditions of a fire assess the need for control room evacuation and direct the appropriate actions of AOP-43 WA 2.1.20 IR 4.2 IR 4.0 Given surveillance test results, evaluate the level I and level II acceptance criteria and identify the required actions per TIS, AP-03.11 and AP-I 9.01 WA 2.2.12 IR 3.4 Given a partially completed worksheet, complete a Radwaste liquid release approval per OP-49.

Perform in Simulator WA 2.3.6 IR 3.1 Classify the event following examination scenario l(2) per IAP-2 WA 2.4.41 IR 4.1.

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.

Page 2 of 8 Created on 5/22/2003 3:3 1 PM

Form ES-301-2 ES-301 Control Room/ln-Plant Systems T- *.: :$he System / JPM Title Facility:

James A. FitzPatrick Date of Examination:

21-25 July, 2003 Exam Level (circle one): W/ SRO(I)

Operating Test No.:

a) 20601005. Manually initiate HPCl in pressure control. Modify to require alternate paths of turbine trip reset and injection for level control. Plant conditions shutdown with MSIV's closed.

b) 23901 003A. Open MSlVs with RPV pressurized. Plant conditions shutdown with M S N s closed.

c) 20101007 Conduct emergency rod in control rod insertion. Plant condition shutdown.

N d) 20004240A Reset PClS Group I Isolation. Plant conditions shutdown with MSIV's closed It e)

"NEW" VerQ SGT "A" train initiation ("B" failed to initiate). Rx Bldg DIP will require startup of "6" train. Plant conditions any.

9 20202001. Perform Jet Pump Operability Test (ST-23C) with Jet Pump Failure malfunction inserted. Plant conditions at power with 2 recirculation loops.

~

~~

9) 21201009F. Reset RPS scram with scram valve fail to close. Plant conditions scrammed from full power.

/h)

ROONLY TY Pe Code*

D, A, S, L Safety Function 2

206000 A4.05 4.4 3

239001 A4.04 3.7 1

201002 A4.02 3.5 5

223002 A4.03 3.5 9

261000 A 4.06 3.6 4

202001 K5.02 3.2 7

21 2000 A4.14 3.8 Page 3 of 8 Created on 4/17/2003 1 :3 1 PM

Form ES-301-2 ES-301 Control Room/ln-Plant Systems W O u t I i ne Facility:

James A. FitzPatrick Date of Examination:

21-25 July, 2003 Exam Level (circle one): I&&=/

SRO(I) AWQ(=U+

Operating Test No.:

E.2 F v

in-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i)

20004234A EOP isolationlinterlock override of Main Turbine Bypass Valves.

Actions performed in Relay Room j) 20101014 Electrically disarm a control rod drive. Actions conducted in Rx Bldg on 272 elevation k) 20004233A Close an SRV remotely by removing fuses. Actions conducted in Relay Room.

D D. R 0

4 295037 EK3.06 4.1 1

201003 A2.02 3.8 3

239002 A2.03 4.2

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Page 4 of 8 Created on 4/17/2003 1 :3 1 PM

RO JPM MATRIX Page 5 of 8 Created on 4/17/2003 1 :3 1 PM

ES-301 Control Roordln-Plant Systems F O ~ I ES301:J b W O u t l i n e Describe activity to be performed 2

2 Conduct weekly alarm test per OP-63 Perform in Simulator WA 2.1.I6 IR 2.9 Facility:

James A. FitzPatrick Date of Examination:

21-25 July, 2003 Examination Level (circle one): RO S R Q Operating Test Number:

Administrative Topic -

(see Note)

M Conduct of Operations Conduct of Operations 442 Equipment Control A4 Emergency Plan retaking only the administrative topics, when 5 are required.

~~

Perform Core Performance Daily Surveillance (ST-5E) and APRM AGAF adjustments (ST-5D)

Perform in Simulator KIA 2.1.7 IR 3.7 Given surveillance test results, evaluate the level I and level II acceptance criteria.

KIA 2.2.12 IR 3.0 2.4.43139 NEW IR=2.8/3.3 As the Emergency Communications Aid, activate the ERO per EAP-17 Attachment 4 Page 6 of 8 Created on 4/17/2003 1 :3 1 PM

Form ES-301-2 ES-30 1 Control Room/ln-Plant Systems Type Code*

System / JPM Title

-Outline Safety Function Facility:

James A. FitzPatrick Date of Examination:

21-25 July, 2003 Exam Level (circle one): RO / p)

Operating Test No.:

W Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) b) 23901003A. Open MSIV's with RPV pressurized. Plant conditions shutdown with MSlVs closed.

c) 20101007 Conduct emergency rod in control rod insertion. Plant condition shutdown.

D, S, L 3

239001 A4.04 3.8 D, A, S, L 1

201002 A4.02 3.5 a) 20601005. Manually initiate HPCI in pressure control. Modify to require alternate paths of turbine trip reset and injection for level control. Plant conditions shutdown with MSlV's closed.

d) 20004240A Reset PClS Group I Isolation. Plant conditions shutdown with MSIV's closed I

2 D, S, L 206000 A4.05 1

4.4 e)

"NEW" Verify SGT 'A" train initiation ("B" failed to initiate). Rx Bldg DIP will require startup of "B" train. Plant conditions any.

N, A, S 9

261 000 A 4.06 3.3 g) 21201009F. Reset RPS scram with scram valve fail to close. Plant conditions scrammed from full power.

5 223002 A4.03 3.6 D, A, S, L h)

RO ONLY. 26402003B EDG shutdown from load testing. Plant condition any I/

I I

0, S 6

264000 A4.04 3.7 119 20202001. Perform Jet Pump Operability Test (ST-23C) with Jet Pump Failure 1 D, A, S 4

malfunction inserted. Plant conditions at power with 2 recirculation loops.

1 202001 K5.02 3.1 7

212000 A4.14 3.8 Page 7 of 8 Created on 4/17/2003 1 :3 1 PM

D Form ES-301-2 ES-301 Control Rootdin-Plant Systems 3

239002 A2.03 4.1 M O u t l i n e Facility:

James A. FitzPatrick Date of Examination:

21-25 July, 2003 Exam Level (circle one): RO / p)

Operating Test No.:

in-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i)

20004234A EOP isolationlinterlock override of Main Turbine Bypass Valves.

Actions performed in Relay Room j) 201 01 014 Electrically disarm a control rod drive. Actions conducted in Rx Bldg on 272' elevation k) 20004233A Close an SRV remotely by removing fuses. Actions conducted in Relay Room.

D I

4 I

295037 3.8 EK3.06 D. R 1

201003 A2.02 3.7

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Page 8 of 8 Created on 4/17/2003 1 :3 1 PM

Instructions: (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

Section C.2.a of Appendix D. *Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

(3)

Whenever ractical, both instrument and component malfunctions should to the applicants competence count toward the minimum requirement.

(2)

Reactivit manipulations may be conducted under normal or controlled abnorma r conditions (refer to Section D.45.d) but must be significant per be include t

only those that require verifiable actions that provide insight Author

Richard W. DeVercelly Page 1 of 10 Created on 4/15/2003 2:48 PM

TRANSIENT AND EVENT CREDIT MATRIX RUN 1 RUN 2 RUN 3 DAY I Control Room Supervisor SROI-I SROI-2 SROI-3 SNO-1 Reactor Controls Operator SROI-4 SROI-5 SROI-6 SROI-6 SCENARIO 2 SNO-2 BOP Operator SROI-I SROI-2 SROI-3 SURROGATE DAY 2 SURROGATE SCENARIO 1 SNO-2 BOP Operator RO-1 RO-2 Control Room Supervisor SROI-4 SNO-1 Reactor Controls Operator RO-1 RO-2 SROI-5 Page 2 of 10 Created on 4/15/2003 2:48 PM

Appendix D Scenario Outline Form ES-D-1 James A. Fiteatrick Scenario No.:

Operators:

SRO SROI-1 RO SROI-4 BOP RO-1 Reactor startup in progress, 10% CTP, RMS in STARTUP, ready to go to RUN Initial Conditions:

Reactor startup in progress, 10% CTP, RMS in STARTUP, ready to go to RUN. Reactor Engineer startup guidance. Maintenance standing by to swap running CBPs.

Event (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Anticipated EAL SAE-4.1.1 or SAE 3.4.1 Page 3 of 10 Created on 4/15/2003 2:48 PM

Form ES-D-1 Appendix D Scenario Outline Facility:

James A. FitzPatrick Scenario No.:

1-2 Op-TSt NO.:

21-25 July, 2003 Examiners:

Operators:

SRO SROI-2 RO SROI-5 BOP RO-2 Reactor startup in progress, 10% CTP, RMS in STARTUP, ready to go to RUN Initial Conditions:

(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Page 4 of 10 Created on 4/15/2003 2:48 PM

Scenario Outline Form ES-D-1 Appendix D Operators:

SRO SROI-3 RO SROI-6 BOP SURROGATE Reactor startup in progress, 10% CTP, RMS in STARTUP, ready to go to RUN Initial Conditions:

(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Page 5 of 10 Created on 4/15/2003 2:48 PM

Scenario Outline Form ES-D-1 Appendix D Facility:

James A. FitzPatrick Scenario No.:

2-1 Op-TSt NO. : 2 1-25 July, 2003 Examiners :

Operators:

SRO SROI-4 RO RO-1 BOP SROI-I

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using Initial Conditions:

recirculation flow

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using recirculation Turnover:

flow I

I I Notes I

I 3

(N)ormal, (R)eactivity Event Description I

FWLC Controlling Instrument Upscale Failure (slow ramp)

(Trigger for BOP-Operator initiai action)

Swap level instrument input and return to Automatic FWLC Step change in Turbine Vibration, AOP-66 Slow loss of condenser vacuum, AOP-31 AOP-31 power reduction with recirculation flow AOP-31 power reduction with rod insertion Manual Scram with partial ATWS (SDV Hydraulic Lock) at > 2.5%

CTP. RMCS success path. Loss of Maincondenser (HPCI and SRVs for pressure/level control)

SDlV Vent or Drain Fails Open (Preset)

ATWS is an IPE dominant accident sequence HPCI is an IPE risk reduction system SLC initiation is an IPE key operator action (I)nstrument, (C)omponent, (M)ajor Anticipated EAL SAE-2.2.2 Page 6 of 10 Created on 4/15/2003 2:48 PM

Appendix D Scenario Outline Form ES-D-I Facility:

James A. Fitsatrick Scenario No.:

2-2 Op-Test No.:

21-25 July, 2003 Examiners :

Operators:

SRO SROI-5 RO RO-2 BOP SROI-2

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using Initial Conditions:

I recirculation flow 1

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using recirculation Event Event No.

Malf. No.

1 Type* 1 Event Description I

I I

I I

SEE SCENARIO 2-1 (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Page 7 of 10 Created on 4/15/2003 2:48 PM

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

Facility:

James A. FitzPatrick Scenario No.:

2-3 Op-Test No. :

2 1-25 July, 2003 Examiners :

Operators:

SRO SROI-6 RO SURROGATE BOP SROI-3 Malf. No.

Type*

Description SEE SCENARIO 2-1

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using Initial Conditions:

recirculation flow

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using recirculation Turnover:

flow (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Page 8 of 10 Created on 4/15/2003 2:48 PM

Appendix D Scenario Outline Form ES-D-1 Facility:

James A. FitzPatrick Scenario No.:

3 Op-Test No.:

21-25 July, 2003 Examiners:

Operators:

SRO RO BOP 100% CTP Initial Conditions:

Maintenance standing by to observe RB (TB or SW) pump swap Turnover:

(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)aj or Anticipated EAL NUE 8.2.1 and Alert 3.1.1 Page 9 of 10 Created on 4/15/2003 2:48 PM

Scenario Outline Form ES-D-1 Appendix D James A. FitzPatrick Scenario No.:

4 Operators:

SRO RO BOP 75% CTP Initial Conditions:

Return to 100% CTP Turnover:

Event Event Event No.

Malf. No.

Type*

Description 1

MFXX I/C Seismic Event (Crvwolf RFPT vibration alarm)

(N)ormal, (M)ajor Anticipated EAL Alert 8.4.4 and SAE 3.4.1 Page 10 of 10 Created on 4/15/2003 2:48 PM