ML032461297

From kanterella
Jump to navigation Jump to search
Facility Ltr. Dtd 05/20/03 Draft/Final - Outlines
ML032461297
Person / Time
Site: FitzPatrick Constellation icon.png
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)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations. Inc.

James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel315 349 6024 Fax 315 349 6480 T.A. Sullivan Vice President, Operations-JAF May 2 0 , 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- 1021 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: U S . 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)

RMS - JAF JAFP File JTRG File

SAMPLE PLAN CHANGES 5/20/03 RO Emergency Plan JPM 0 Originally to perform an EAP-1.1 off site notification communicator h c t i o n .

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 NIA 5 6 111 2.1.7 ST-SDIE RO Admin JPM NIA RO Admin JPM NIA 2.4.43

ES-401 BWR SI33 Examination Outline Form ES-401-1 1 Facilitv: I James A FitzPatrick Date of Exam: 7/21-2513 mn-h&

I I I RO WA Category Points 1 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.
3. 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.

It 4.

5.

Systemdevolutionswithin each group are identified on the associated outline.

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

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 55.43or 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 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.
8. For Tier 3,enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401,Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

Page 1 of27 Created on 5/7/2003 11:24 AM

ES-401 BWR S4-Q Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions- Tier l/GrouD. 1 Cae

. / SROf 10CRF-55.43b related topica ElAPE # / Name / Safety Function K K/A Topic(s) 1 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 295016 Control Room Abandonment I 7 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) 295019 Partial or Total Loss of Inst. Air I 8 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 295025 High Reactor Pressure I 3 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 11:24 AM

ES-401 B W R SRQ Examination Outline Form ES401-1 Emergency and Abnormal Plant Evolutions - Tier 1IGroup 1 (RQ I SRO) 10CRF55.43 b related topics EIAPE # I Name I Safety Function WA Topic@) IR 295030 Low Suppression Pool Wtr Lvl I 5 Ability to determine and/or interpret the 3.7 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 295037 SCRAM Condition Present and Ability to determine and/or interpret the 4.3 Power Above APRM Downscale or following as they apply to SCRAM Unknown I 1 CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR 41.10 143.5 / 45.13)

EA2.05Control 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 10CFR-55.43@)(2)

WA Category Totals: 1 2 Page 3 of 27 Created on 5/7/2003 1 1:24 AM

ES-401 BWR Scua Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions Tier 1IGroup 2 fae 1 SRO) 10CRF-55.43 b related topics EIAPE # I Name ISafety Function KIA Topic@)

295014 Inadvertent Reactivity Addition I1 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) 295022 Loss of CRD Pumps I 1 Ability to determine and/or interpret the 3.4 following as they apply to LOSS OF CRD PUMPS :(CFR 41.10 /43.5 145.13)

AA2.02 C m svstem status 295035 Secondary Containment High 3.4 Differential Pressure I 5 performing a containment puEe. - -

(CFR 43 / ; . 45.10) -

295036 Secondary Containment High Ability to determine and/or interpret the 3.2 SumpIArea Water Level I 5 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 1(0o(0 211 Group Point Total:

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

BWR SRQ Examination Outline Form ES-401-1 IS-401 10CRF-55.43 b related topics Plant Systems -Tier 2lGroup W / SRO)

System # I Name WA Topic@)

21 1000 SLC 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) 215005 APRM I LPRM 2.1.34Ability to maintain primary and secondary plant chemistry within allowable limits.

(CFR 41.10 / 43.5/45.12) 217000 RCIC Knowledge of electrical power 2.6 S56 supplies to the following:

(CFR: 41.7)

K2.04 Gland seal compressor (vacuum pump)

Link to 10CFR-55.43@)(2) - -

?4JBmms NOT RANDOMLY SELECTED 223002 PClSlNuclear Steam Knowledge of electrical power Supply Shutoff supplies to the following:

(CFR 41.7)

K2.01 Logic power supplies Link to 10CFR-55.43@)(5)

Page 5 of 27 Created on 5/7/20031 1 :24AM

Page 6 of 27 Created on 5/7/2003 11:24 AM BWR SRQ Examination Outline

s-401 Plant Systems -Tier 2IGroup 2 (+?Q/ SRO) 10CRF-55.43 brelated topics I

I I

~~

jystem # I Name K/A Topic@)

239001 Main and Reheat Steam 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 Page 7 of 27 Created on 5/7/2003 11:24 AM

ES-401 BWR SW Examination Outline Form ES-401-I Plant Systems -Tier 2lGro 10CRF55.43 b related topics System # I Name K/A Topic@)

271000 Offgas associated with operating the OFFGAS SYSTEM controls including: (CFR: 41.5 / 45.5)

WA Category Point Totals Page 8 of 27 Created on 5/7/2003 11:24 AM

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-53 SRO Only 1OCRF-55.43 b related topics Facility: James A FitzPatrick Date of Exam: 7/21-25/03 Category WA# I Topic RO I SRC 3nly 1.

Conduct of Operations Subtotal 0 2.2.17 2.2.6 S70

2. 2.2.32 S72 Equipment Control (CFR: 43.6)

I l l 2.2.

2.2.

2.2.

2 s74 and contamination control / including permissible levels in excess of those authorized. (CFR: 43.4 / 45.10) 2.3.6 S76

3. reviewing and approving release permits.

Radiation (CFR: 43.4 / 45.10)

Control Subtotal I I I 2 Page 9 of 27 Created on 5/7/2003 11:24 AM

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES401-53 SRO Only 1OCRF-55.43 b related topics Facility: James A FitzPatrick Date of Exam: 7/21-25/03 WA # -Only 2.4.47 2.4.16 s94 hierarchy and coordination with other support procedures. (CFR: 41.10 / 43.5/

2.4.30 45113)

Knowledge of which events related to I l Il I I I 3.6 S96 system operations/status should be reported to outside agencies.

(CFR: 43.5 / 45.1 1) 2.4.22 S I 00 (CFR: 43.5 / 45.12)

I l l 2.4.

2.4.

3 Page 10of27 Created on 5/7/2003 11:24 AM

Tier I Randomly Selected Reason for Rejection Group WA See Notes Below No JAF procedural direction to operate D w e l l Recirculation 111-2 500000 EA1.04 (Cooling) Fans to control containment hykogen. Note 1 I12 1 295019 AKI .XX No WASexist under AKI. Note 1 214 2 226001 K5.01 Importance rating at 2.2 (<2.5) and no plant priority to justify.

Note 1 2112 290001 K1.06 NIA JAF BWR-6 only. Note 1 212 201001 K2.07 Importance rating at 2.1 (~2.5)and no plant priority to justify.

Note 1 212 271000 K2.01 Importance rating at 1.5 (~2.5)and no plant priority to justify.

Note 1 213 2 215001 K2.01 Importance rating at 2.1 (<2.5) and no plant priority to justify.

Note 1 213 2 215001 A2.04 Importance rating at 2.0 (~2.5)and no plant priority to justify.

Note I 212 271000 A1.04 Importance rating at 2.4 (<2.5) and no plant priority to justify.

Note 2 Note 1: Rejected during generation of rbvision 8 outline. Strike out indicates change in tiedgroup from rev 8 to rev 9.

Note 2: Rejected during conversion from rev 8 to pilot rev 9 outline.

Tiedgroup is as described in rev 9.

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

BWR SR0 Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier IlGroup 1 (RO I SRO)

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

295001 Partial or Complete Loss of Forced 2.3.2 Knowledge of facility 23 2 . 9 112 Core Flow Circulation I 1 & 4 ALARA program.

(CFR: 41.12 / 43.4 / 45.9 / 45.10)

~

295003 Partial or Complete Loss of AC I 6 Ability to determine and/or interpret 3.413.7 213 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 295004 Partial or Total Loss of DC Pwr I 6 Knowledge of the interrelations 3.113.1 314 between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following: (CFR: 41.7 / 45.8)

AK2.01 Battery charger 295005 Main Turbine Generator Trip I 3 Knowledge of the interrelations 3.613.7 415 between MAIN TURBINE GENERATOR TRIP and the following: (CFR: 41.7 / 45.8)

AK2.07 Reactor pressure control 1 295006 SCRAM I 1 Knowledge of the operational implications of the following concepts 3.714.0 516 as they apply to SCRAM :

(CFR: 41.8 to 41.10)

AK 1.03 Reactivity control 295016 Control Room Abandonment I 7 Knowledge of the interrelations 2.913.1 6ff between CONTROL ROOM ABANDONMENT and the following:

(CFR: 41.7 / 45.8)

AK2.03 Control room HVAC 295018 Partial or Total Loss of CCW I 8 Knowledge of the operational 3.513.6 718 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 295019 Partial or Total Loss of Inst. Air I 8 2.2.26 Knowledge of refueling 2.513.7 819 administrative requirements.

(CFR 43.5 / 45.13)

Page 12 of 27 Created on 5/7/2003 11:24 AM

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

EIAPE # I Name ISafety Function K A KIA Topic@) IR #!

3 1 295021 Loss of Shutdown Cooling I 4 1 Ability to operate and/or monitor the 3.713.7 9110 following as they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.7 / 45.6)

AA 1.04 Alternate heat removal methods 295023 Refueling Acc Cooling Mode I 8 1 Knowledge of the reasons for the 3.413.8 10111 following responses as they apply to REFUELING ACCIDENTS :

(CFR: 41.5 / 45.6)

AK3.02 Interlocks associated with fuel handling equipment 295024 High Drywell Pressure I 5 Knowledge of the operational 4.114.2 11112 implications of the following concepts as they apply to HIGH DRYWELL PRESSURE : (CFR: 41.8 to 41.10)

EK1.01 Drywell integrity: Plant-Specific 1 Ability to operate and/or monitor the 4.114.1 12113 following as they apply to HIGH REACTOR PRESSURE:

(CFR: 41.7 / 45.6)

EA1.07 ARI/RPT/ATWS: Plant-Specific Ability to determine andlor interpret 3.713.8 13116 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 3.013.4 14117 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 295028 High Drywell Temperature I 5 Ability to determine and/or interpret 4.014.1 15118 the following as they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13)

EA2.01 Drywell temperature Page 13 of 27 Created on 5/7/2003 11:24 AM

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

EIAPE # I Name I Safety Function KIA Topic@) IR #

295030 Low Suppression Pool Wtr Lvl I 5 2.4.48 Ability to interpret 3.513.8 16/19 control room indications to verify the status and operation of system / and understand how operator actions and directives affect plant and system conditions.

r (CFR 43.5 / 45.12) 295031 Reactor Low Water Level I 2 Knowledge of the reasons for the 3.914.2 17120 following responses as they apply to REACTOR LOW WATER LEVEL :

(CFR 41.5 / 45.6)

EK3.01 Automatic depressurization system actuation 11 295037 SCRAM Condition Present and Ability to determine and/or interpret 4.114.2 18/21 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 295038 High Off-site Release Rate I9 Knowledge of the interrelations 3.613.8 19122 between HIGH OFF-SITE RELEASE RATE and the following:

(CFR: 41.7 / 45.8)

EK2.02 Offgas system 600000 Plant Fire On Site / 8 Ability to operate and / or monitor the 3.013.0 20123 Note 1 following as they apply to PLANT FIRE ON SITE:

AAI .06 Fire alarm l Note 1: Randomly selected during conversion from rev 8 to pilot rev 9 outline Page 14 of 27 Created on 5/7/2003 11:24 AM

BWR S F S Examination Outline Form ES-401-1

. 2 (RO Emergency and Abnormal Plant Evolutions -Tier IIGrouD . I SRO)

E/APE # I Name I Safety Function WA Topic(s) IR #

295002 Loss of Main Condenser Vac I3 Ability to determine andor interpret 2.913.1 21/24 the following as they apply to LOSS OF MAIN CONDENSER VACUUM :

(CFR: 41.10 143.5 145.1 3) 1 AA2.0 1 Condenser vacuum/absolute pressure 295007 High Reactor Pressure I3 Knowledge of the interrelations 3.213.3 22125 between HIGH REACTOR PRESSURE and the following:

(CFR 41.7 / 45.8)

AK2.04 LPCS 295014 Inadvertent Reactivity Addition I 1 Knowledge of the interrelations 23/26 between INADVERTENT REACTIVITY ADDITION and the following: (CFR: 41.7 / 45.8) 2.3.10 Ability to perform 2.913.3 24/28 procedures to reduce excessive levels of radiation and guard against personnel exposure.

(CFR: 43.4 / 45.10)

Page 15 of 27 Created on 5/7/2003 1 1:24 AM

ES-401 BWR Si40 Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions- Tier l1GrouP

. 2 (RO

. / SRO)

EIAPE # I Name I Safety Function K WA Topic@) IR #

1 295033 High Secondary Containment Ability to operate and/or monitor the 3.914.0 25/29 Area Radiation Levels I 9 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 295036 Secondary Containment High Knowledge of the reasons for the 2.612.8 26/31 SumpIArea Water Level I 5 following responses as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL

(CFR 41.5 / 45.6)

EK3.01 Emergency depressurization 500000 High CTMT Hydrogen Conc. I 5 Ability to operate and monitor the 3.313.4 27/32 following as they apply to HIGH CONTAINMENT HYDROGEN CONTROL: (CFR: 41.7 / 45.6)

EA 1.06 Drywell sprays WA Category Point Totals 0 Group Point Total: 714 Page 16 of 27 Created on 5/7/2003 1 1:24 AM

ES-401 BWR S R 0 Examination Outline Form ES-401-1 Plant Systems -Tier 2lGroup 1 (RO / SRO)

System # I Name KIA Topic(s) IR #

203000 RHRILPCI: Injection Ability to predict and/or 3.813.7 28/33 Mode monitor changes in parameters associated with operating the RHWLPCI:

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

AI -05 SUDD~eSSiOIlDO01 level Ability to manually operate 3.713.5 29/36 and/or monitor in the control room:

(CFR 41.7 / 45.5to 45.8)

A4.11 Indicating lights and alarms 205000 Shutdown Cooling Knowledge of the effect that a 3.713.7 30137 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 206000 HPCl 2.3.1 Knowledge of 10 2.613.0 31/39 CFR: 20 and related facility radiation control requirements. (CFR.

41.12 / 43.4. 45.9 / 45.10)

Knowledge of the physical 32144 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 209001 LPCS 2.2.13 Knowledge of 33/45 tagging and clearance procedures.

(CFR: 41.10 / 45.13)

Page 17 of 27 Created on 5/7/2003 11:24 AM

ES-401 BWR SR0 Examination Outline

- ~

Form ES-401-1 Plant Systems -Tier ZlGroup 1 (RO I SRO)

KIA Topic@) IR #

Knowledge of the effect that a 34146 loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following: (CFR: 4 1.7 / 45.4)

K3.02 ADS logic N/A JAF. NO HIGH PRESSURE CORE SPRAY SYSTEM 2.1.9 Ability to direct 2.514.0 35/47 personnel activities inside the control room.

(CFR: 45.5 / 45.12 / 45.13)

Knowledge of the operational 3.313.4 36\48 implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM :(CFR: 41.5 145.3)

K5.02 Specific logic arrangements 1 Ability to monitor automatic 3.513.5 37/49 operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including: (CFR 41.7 / 45.7)

- A3.04 Control rod block status 1 Ability to monitor automatic 3.613.6 38/50 operations of the SOURCE RANGE MONITOR (SRM)

SYSTEM including:

(CFR 41.7 / 45.7)

- A3.04 Control rod block status 1 Ability to monitor automatic 3.513.5 39/51 operations of the AVERAGE POWER RANGE MONITORLOCAL POWER RANGE MONITOR SYSTEM including: (CFR: 41.7 / 45.7)

- A3.02 Full core display 1 Knowledge of the effect that a 3.713.7 40153 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 Page 18 of 27 Created on 5/7/2003 11:24 AM

BWR SiW Examination Outline Form ES-401-1 Plant Systems -Tier 2IGroup 1 (RO I SRO WA Topic(s) R #

Ability to monitor automatic 3.513.4 41/54 operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: (CFR 41.7 / 45.7)

A3.06 Lights and alarms Knowledge of the physical 3.913.9 42157 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 2.913.2 43/58 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 2.713.9 44/60 conditions and limitations in the facility license.(CFR: 43.1 / 45.13)

Knowledge of the physical 3.813.9 45/62 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 Page 19 of 27 Created on 5/7/2003 11:24 AM

BWR SRQ Examination Outline Form ES-401-1 Plant Systems -Tier 2lGroup 1 (ROI SRO)

KIA Topic(s) IR U Knowledge of the physical 3.213.2 46/63 connections a n d o r 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 3.213.5 47/64 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 3.313.6 48/65 supplies to the following:

(CFR 4 1.7)

K2.0 1 Off-site sources of power 2.2.13 Knowledge of 3.613.8 49/66 tagging and clearance procedures.

(CFR: 41.10 / 45.13)

Ability to (a) predict the 2.813.2 50168 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 3.613.6 51/69 loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET) :

(CFR: 41.7 / 45.7)

K6.02 Fuel oil pumps Page 20 of 27 Created on 5/7/2003 11:24 AM

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

System # I Name K K K K A A K/A Topic(s) IR #

2 3 4 5 3 4 300000 Instrument Air Knowledge of the connections 3.113.2 52171 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 400000 Component Cooling 1 Knowledge of electrical power 2.9/3.0 53/73 Water supplies to the following:

(CFR 41.7)

K2.01 CCW pumps WA Category Point Totals Group Point Total: 2644 Page 21 of 27 Created on 5/7/2003 11 :24 AM

ES-401 BWR SR0 Examination Outline Plant Systems -Tier 2/Group 2 (RO/ SRC KIA Topic(s) R U Knowledge of electrical 5.513.6 54/75 201001 CRD Hydraulic 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 3.413.6 55/77 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 3.213.2 56/78 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 2.912.9 57/79 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 cornponent s Ability to monitor automatic 3.213.1 58/80 operations of the ROD POSITION INFORMATION SYSTEM including: (CFR 41.7 / 45.7)

A3.02 Alarm and indicating lights Page 22 of 27 Created on 5/7/2003 11:24 AM

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

System # I Name K/A Topicis) IR #

NOT RANDOMLY SELECTED 215002 RBM Ability to predict andlor 2.712.8 59/81 monitor changes in parameters associated with operating the ROD BLOCK MONITOR SYSTEM controls including:

(CFR: 41.5 / 45.5)

A1.O1 Trip reference: BWR-334s 216000 Nuclear Boiler Inst. Knowledge of the effect that 3.113.3 60182 a loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION :

(CFR 41.7 / 45.7)

K6.01 A.C. electrical 226001 RHRILPCI: CTMT Spray Knowledge of the physical 3.013.0 61183 Mode 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 230000 RHWLPCI: ToruslPool Ability to manually operate 3.813.6 62/84 Spray Mode and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.02 Spray valves 233000 Fuel Pool CoolinglCleanup Knowledge of FUEL POOL 2.W3.1 63185 COOLING AND CLEAN-UP design feature(s) andlor interlocks which provide for the following:

(CFR: 41.7)

K4.03 Maintenance of adequate pool temperature Page 23 of 27 Created on 5/7/2003 11:24 AM

I l 4 O l BWR Si4-Q Examination Outline 0 / SRO)

A A G WA Topic@) IR Form ES-401-1 3 4 64/86 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 65/87 a loss or malfunction of the SECONDARY CONTAINMENT will have on following:

(CFR 41.7 / 45.4)

K3.01 ?Off-site radioactive

=

WA Category Point Totals 1 1 1 2 1 1 1 1 1a2 Page 24 of 27 Created on 5/7/2003 11:24 AM

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES401-53 1 Facility: JamesA. FitzPatrick Date of Exam: 7/21-25103 Category Topic RO SRO-Only IR # IR #

2.1.32 Ability to explain and apply system limits 3.4 66 3.8 88 and precautions. (CFR: 41.10 / 43.2 / 45.12) 2.1.29 Knowledge of how to conduct and verify 3.4 67 3.3 89 1.

Conduct of Operations 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) 2.2.12 Knowledge of surveillance procedures.

(CFR 41.10 / 45.13) 2.

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

(CFR 43.4 / 45110)-

2.3.1 Knowledge of 10 CFR: 20 and related facility

3. I radiation control requirements.

Radiation Control Subtotal Page 25 of 27 Created on 5/7/2003 11:24 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 SRO-Only 2.4.15 Knowledge of communications 3.0 73 3.5 97 procedures associated with EOP implementation.

(CFR 41.10 / 45.13) 2.4.26 Knowledge of facility protection 2.9 74 3.3 98 requirements including fire brigade and

4. portable fire fighting equipment usage.

Emergency (CFR 43.5 / 45.12)

Procedures 2.4.39 Knowledge of the RO's responsibilities in 3.3 75 3.1 99 I Plan emergency plan implementation.

Subtotal 5 4310 $

Page 26 of 27 Created on 5/7/2003 11:24 AM

Tier I Randomly Selected Reason for Rejection Group WA See Note Below Importance rating at 2.3 (~2.5) and no plant priority to justify 1 3 2.2.18 1 Rejected during outline review due to oversampling 1 3 1 2.3.4 I Rejected during outline review due to oversampling Note 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 11 :24 AM

SROI JPM MATRIX CONTROL ROOM SYSTEMS IN PLANT SYSTEMS ADMIN TOPICS (7 JPM's) (3 JPMs) (5 JPMs)

JPM ID 7 DIFFERENT SECTION 1.9 SAFETY FUNCTIONS 3 DIFFERENT SECTION 1.9 JPM NUMBER JPM BRIEF DESCRIPTION SAFETY FUNCTION SIMULATOR DUPLICATION DIRECT FROM BANK (< 80%)

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

hl OR LOW POWER (21)

ALT. PATH (4-6)

EOPlAOP ACTION (2 1)

RCA ENTRY

(> 1)

LINKED TO SIM EXAM Page 1 of8 Created on 4/17/2003 1:3 1 PM

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 Describe activity to be performed 4%sw@m- (see Note) ..

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 Conduct of Operations WA 2.1 .12 IR 4.0 Given plant conditions of a fire assess the need for control room evacuation and direct the appropriate actions of AOP-43 Conduct of Operations WA 2.1.20 IR 4.2 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 Equipment Control WA 2.2.12 IR 3.4 Given a partially completed worksheet, complete a Radwaste liquid release approval per OP-49.

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

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.

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

ES-301 Control Room/ln-Plant Systems Form ES-301-2 T- *.::$he Facility: James A. FitzPatrick Date of Examination: 21-25 July, 2003 Exam Level (circle one): W/SRO(I) Operating Test No.:

TYPe Safety System / JPM Title Function Code*

a) 20601005. Manually initiate HPCl in pressure control. Modify to require 2 alternate paths of turbine trip reset and injection for level control. Plant 206000 A4.05 conditions shutdown with MSIV's closed. 4.4 b) 23901003A. Open MSlVs with RPV pressurized. Plant conditions shutdown 3 with M S N s closed. 239001 A4.04 3.7 c) 20101007 Conduct emergency rod in control rod insertion. Plant condition D, A, S, L 1 shutdown. 201002 A4.02 3.5 N d) 20004240A Reset PClS Group I Isolation. Plant conditions shutdown with 5 MSIV's closed 223002 A4.03 3.5 Ite) "NEW" VerQ SGT "A"train initiation ("B"failed to initiate). Rx Bldg DIP will 9 require startup of "6"train. Plant conditions any. 261000 A 4.06 3.6 9 20202001. Perform Jet Pump Operability Test (ST-23C) with Jet Pump Failure 4 malfunction inserted. Plant conditions at power with 2 recirculation loops. 202001 K5.02 3.2

~ ~~

9) 21201009F. Reset RPS scram with scram valve fail to close. Plant conditions 7 scrammed from full power. 212000 A4.14 3.8

/h) ROONLY Page 3 of 8 Created on 4/17/2003 1:3 1 PM

ES-301 Control Room/ln-Plant Systems Form ES-301-2 W O u tIine 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 isolationlinterlockoverride of Main Turbine Bypass Valves. D 4 Actions performed in Relay Room 295037 EK3.06 4.1 j) 20101014 Electrically disarm a control rod drive. Actions conducted in Rx Bldg D. R 1 on 272 elevation 201003 A2.02 3.8 k) 20004233A Close an SRV remotely by removing fuses. Actions conducted in 0 3 Relay Room. 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 :31 PM

ES-301 Control Roordln-Plant Systems WOutline

.. F O ~ES301:J I b Facility: James A. FitzPatrick Date of Examination: 21-25 July, 2003 Examination Level (circle one): RO S R Q Operating Test Number:

Administrative Topic Describe activity to be performed (see Note) ..

2 2 M Conduct weekly alarm test per OP-63 Perform in Simulator Conduct of Operations WA 2.1.I6 IR 2.9

~~

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

Conduct of Operations Perform in Simulator KIA 2.1.7 IR 3.7 442 Given surveillance test results, evaluate the level I and level II acceptance criteria.

Equipment Control KIA 2.2.12 IR 3.0 A4 2.4.43139 NEW IR=2.8/3.3 As the Emergency Communications Aid, activate the ERO per Emergency Plan EAP-17 Attachment 4 retaking only the administrative topics, when 5 are required.

Page 6 of 8 Created on 4/17/2003 1:3 1 PM

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

-Outline Facility: James A. FitzPatrick Date of Examination: 21-25 July, 2003 Exam Level (circle one): RO / p ) Operating Test No.:

W Control Room Systems (8for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Type Safety System / JPM Title Code* Function I

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. 1 2 206000 A4.05 4.4 b) 23901003A. Open MSIV's with RPV pressurized. Plant conditions shutdown D, S, L 3 with MSlVs closed. 239001 A4.04 3.8 c) 20101007 Conduct emergency rod in control rod insertion. Plant condition D, A, S , L 1 shutdown. 201002 A4.02 3.5 d) 20004240A Reset PClS Group I Isolation. Plant conditions shutdown with D,S , L 5 MSIV's closed 223002 A4.03 3.6 e) "NEW" Verify SGT 'A" train initiation ("B" failed to initiate). Rx Bldg DIP will N, A, S 9 require startup of "B" train. Plant conditions any. 261000 A 4.06 3.3 I

I/ 1 I 119 20202001. Perform Jet Pump Operability Test (ST-23C) with Jet Pump Failure malfunction inserted. Plant conditions at power with 2 recirculation loops.

D, A, S 1 4 202001 K5.02 3.1 g) 21201009F. Reset RPS scram with scram valve fail to close. Plant conditions D, A, S,L 7 scrammed from full power. 212000 A4.14 3.8 h) RO ONLY. 26402003B EDG shutdown from load testing. Plant condition any 0, S 6 264000 A4.04 3.7 Page 7 of 8 Created on 4/17/2003 1:3 1 PM

ES-301 Control Rootdin-Plant Systems Form ES-301-2 MOutline 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. D I 4 Actions performed in Relay Room I 295037 3.8EK3.06 j) 201 01014 Electrically disarm a control rod drive. Actions conducted in Rx Bldg D. R 1 on 272' elevation 201003 A2.02 3.7 k) 20004233A Close an SRV remotely by removing fuses. Actions conducted in D 3 Relay Room. 239002 A2.03 4.1

  • 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.

(2) r Reactivit manipulations may be conducted under normal or controlled abnorma conditions (refer to Section D.45.d) but must be significant per 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) t Whenever ractical, both instrument and component malfunctions should be include ; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirement.

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-1Reactor Controls Operator SROI-4 SROI-5 SROI-6 SCENARIO 1 SNO-2 BOP Operator RO-1 RO-2 SURROGATE DAY 2 Control Room Supervisor SROI-4 SROI-5 SROI-6 SURROGATE SNO-1Reactor Controls Operator RO-1 RO-2 SCENARIO 2 SNO-2 BOP Operator SROI-I SROI-2 SROI-3 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

Appendix D Scenario Outline Form ES-D- 1 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

Appendix D Scenario Outline Form ES-D- 1 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

Appendix D Scenario Outline Form ES-D-1 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 Initial Conditions:

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

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using recirculation flow 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 (SDVHydraulic 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)

I I

I Notes ATWS is an IPE dominant accident sequence HPCI is an IPE risk reduction system I I 3 SLC initiation is an IPE key operator action

  • (N)ormal, (R)eactivity (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 I Initial Conditions:

recirculation flow 1

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using recirculation Event No. Malf. No. 1 I

Event Type* 1 I

Event Description 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

Appendix D Scenario Outline Form ES-D-1 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 Initial Conditions:

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

- 90% CTP, Rod pattern exchange just completed. Return to 100% CTP using recirculation flow No. Malf. No. Type* Description SEE SCENARIO 2-1

  • (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)ajor Anticipated EAL NUE 8.2.1 and Alert 3.1.1 Page 9 of 10 Created on 4/15/2003 2:48 PM

Appendix D Scenario Outline Form ES-D-1 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
Retrieved from "https://kanterella.com/w/index.php?title=ML032461297&oldid=2646311"