ML081190547
| ML081190547 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/25/2008 |
| From: | Hironori Peterson Operations Branch III |
| To: | Jennifer Davis Detroit Edison |
| Shared Package | |
| ML080860174 | List: |
| References | |
| 50-341/08-301 | |
| Download: ML081190547 (36) | |
Text
EXAMINATION OUTLINE SUBMITTAL AND COMMENTS FOR THE FERMI INITIAL EXAMINATION -JANUARY 2008
DTE Energy October 16,2007 NRC-07-0054 Mr. Hironori Peterson Chief, Operations Branch Division of Reactor Safety U. S. Nuclear Regulatory Commission Region III Suite 210 2443 Warrenville Road Lisle, Illinois 60532-4352
Dear Mr. Peterson:
Enclosed please find the proposed examination outline submitted to the NRC in preparation for the upcoming Fermi 2 Initial License Examination scheduled during the week of January 28,2008:
. Examination Outline Quality Checklist (Form ES-201-2)
. Photocopies of Examination Security Agreements (Form ES-201-3)
. RO Administrative Topics Outline(s) (Form ES-301-1)
. SRO Administrative Topics Outline(s) (Form ES-301-1)
. RO Control Room / In-Plant Systems Outline (Form ES-301-2)
. SRO Upgrade Control Room / In-Plant Systems Outline (Form ES-301-2)
. SRO Instant Control Room/In-Plant Systems Outline (Form ES-301-2)
. Transient and Event Checklist (Form ES-301-5)
. Scenario Outlines (Form ES-D-I)
. RO BWR Examination Outline (Form ES-401-1)
. SRO BWR Examination Outline (Form ES-401-1)
. Generic WA Outline (Form ES-401-3)
Record of Rejected WAS (Form ES-401-4)
Hironori Peterson Chief, Operations Branch NRC-07-0054 October 16,2007 Page 2 The examination outline was developed using the appropriate guidance contained in Revision 9, NUREG 1021, Supplement 1. These materials shall be withheld from public disclosure until after the examinations are complete.
We look forward to working with you and your examination team during the examination development and administration process. If you have any questions or comments regarding the contents of the items listed above, please contact Mr. Timothy P. Horan. General Supervisor, Operations Training at (734) 586-4961.
Sincerely, Enclosure cc: Chief, Reactor Operations Branch NRC Resident Office Document Control Desk Washington D. C.
ES-201 Examination Outline Quality Chacklist ES-201-2 F~rm Fadmy: Date of Dramination:
of m a l evolutions. instwmenl and component failures. teCmicBl specibtions.
and quantiIativ8 cMecia spe4tied on Form ES-3014 and dewbed in Appendix D.
ES-201,Page 26 of 28
ES-301 Administrative ToDics Outline Form ES-301-1 Iacility: Fermi 2 Date of Examination: 01/28/2006 Ixamination Level: RO SRO 0 Operating Test Number:2008-1 Administrative Topic Type Describe activity to be performed (See Note) Code" Perform Thermal Limit Verification (MAPRAT) 293009 Core Thermal Limits GENERIC 2.1.7 -Ability to evaluate plant Conduct of Operations performance and make operational judgments based on operating characteristics / reactor behavior I and instrument interpretation. RO 4.4 ISRO 4.7 Complete and Communicate a Nuclear Plant Technical Data Form (Alert)
Conduct of Operations GENERIC 2.4.39 - Knowledge of the ROs responsibilities in emergency plan implementation.
RO 3.91SRO 3.8 Perform 24.202.03, "HPCI System Piping Filled And Valve Position Verification" Equipment Control 206000 High Pressure Coolant Injection System GENERIC 2.2.12 - Knowledge of surveillance procedures. RO 3.7 ISRO 4.1 Determine Dose Limit Will Be Exceeded and Initiate a Dose Extension.
GENERIC 2.3.4 - Knowledge of radiation exposure Radiation Control limits and contamination control / including permissible levels in excess of those authorized.
RO 3.21SRO 3.7 Emergency Plan 4OTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrativetopics, when 5 are required.
' Type Codes & Criteria: (C)ontrol room, (S)imulator,or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odifiedfrom bank (> 1)
(P)revious2 exams (51; randomly selected)
ES 301, Page 22 of 27
ES-301 Administrative Tooics Outline F o r m ES-301-1
-acility: Fermi 2 Date of Examination: 1/28/2008 IxaminationLevel: RO 0 SRO [XI Operating Test Number: 2008-1 Administrative Topic Describe activity to be performed (See Note) Code Perform Thermal Limit Verification (MAPRAT) 293009 Core Thermal Limits GENERIC 2.1.7 -Ability to evaluate plant Conduct of Operations performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation. RO 4.4 ISRO 4.7 Knowledge of Shift Staffing Requirements GENERIC 2.1.4 - Knowledge of individual licensed operator responsibilities related to shift staffing, such Conduct of Operations C,R,S.P as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
RO 3.31SRO 3.8 Perform 24.202.03, HPCI System Piping Filled And Valve Position Verification Equipment Control SD 206000 High Pressure Coolant Injection System GENERIC 2.2.12 - Knowledge of surveillance procedures. RO 3.7 SRO 4.1 Determine Dose Limit and Complete a Dose Extension Radiation Control GENERIC 2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.
RO 3.21SRO 3.7 Perform On-Site Protective Actions and Classification for Security Event (Alert)
Emergency Plan GENERIC 2.4.40 - Knowledge of the SROs responsibilities in emergency plan implementation RO 2.7 SRO 4.5 rlOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrativetopics, when 5 are required.
Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odifiedfrom bank (z 1)
(P)revious 2 exams (5 1; randomly selected)
ES 301, Page 22 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Fermi 2 Date of Examination: 1/28/2008 Exam Level: RO [XI SRO-l 0 SRO-U 0 Operating Test Number: 2008-1 Control Room Systems' (8 for RO); (7for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety System / JPM Title Type Code' Function
- a. Shift Operating CRD Pumps DS 1 201001 Control Rod Drive Hydraulic System A4. Ability to manually operate andlor monitor in the control room:
A4.01 CRD DUmDS RO 3.1 I SRO 3.1
- b. Manually Start the RClC System D.S 2 217000 Reactor Core lsolatlon Cooling System A4. Ability to manually operate andlor monitor in the control room:
A4.04 Manually initiated controls RO 3.6 I SRO 3.6
- c. Manually Initiate Low Low Set (No Fault) 3 239002 RellefISafety Valves A4. Ability to manually operate and/or monitor in the control room:
- d. SOP Run of Core Spray System in Test Mode P,EN,D,A,S 4 209001 Low Pressure Core Spray System A2. Ability to (a) predict the 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 operations:
AZ.06 Inadequate system flow RO 3.2 I SRO 3.2
- e. Restore a RWCU Pump After Oil Sample (Plant Hot) With System Leak N.S 5 and Failure to Isolate 223002 Primary Containment Isolation System /Nuclear Steam Supply Shut-Off A2. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR 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:
A2.03 System logic failures RO 3.0 I SRO 3.3
- f. Respond to Multiple Rod Drifts and RPS Failure DAS 7 212000 Reactor Protection System A2. Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.16 Chanaina mode switch Dosition RO 4.0 I SRO 4.1
- g. Respond to Refuel Floor High Radiation PS?A,L,S 9 272000 Radiation Monitoring - System A2. Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.12 Refuel floor handling accidentsloperations RO 3.3 I SRO 4.0
- h. Manually Initiate Div 1 Emergency Equipment Cooling Water 0 400000 Component Cooling Water Systems (CCWS)
A4. Ability to manually operate and I or monitor in the control room:
A4.01 CCW indications and control .RO 3.1 I SRO 3.0 Implant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Shin In Service IAS Dryers D.R 0 300000: Instrument Air System A2. Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
A2.01 Air dryer and filter malfunctions RO 2.9 I SRO 2.8
- j. Defeat ARI Logic Trips 7 216000: Nuclear Boiler Instrumentation Generic 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications. RO 4.2 I SRO 4.1
- k. Place ESF Battery Charger in Service 6 263000: DC Electrical Distribution Generic 2.1.30 Ability to locate and operate components, including local controls. RO 4.4 I SRO 4.0 K I . Knowledge of the physical connections andlor cause effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following:
K1.02 Battery charger and battery RO 3.2 I SRO 3.3
'Type Codes Criteria for RO / SRO-I I SRO-U (C)ontrol room (D)irect from bank -
<91 (0 154
> l I '1 1'1 (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown -
I ' 1 (control room system)
> l I )1 1 2 1 (N)ew or (M)odified from bank including 1(A) -
> 2 1 '2 1'1 (P)revious 2 exams < 3 I ( 3 I 5 2 (randomly selected)
WCA -
> l I'1 1'1 (S)imulator ES-301, Page 23 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Fermi-2 Date of Examination: 01/28/2008 Exam Level: RO 0 SRO-I SRO-U 0 Operating Test Number: 2008-1 Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety System / JPM Title Type Code' Function
- a. Manually Start the RClC System D.S 2 217000 Reactor Core Isolation Cooling System A4. Ability to manually operate and/or monitor in the control room:
A4.04 Manuallv initiated controls RO 3.6 I SRO 3.6
- b. Manually Initiate Low Low Set (No Fault) D,S 239002 ReliefISafety Valves A4. Ability to manually operate andlor monitor in the control room:
- c. SOP Run of Core Spray System in Test Mode P,EN,D,A,S 209001 Low Pressure Core Spray System AZ. Ability to (a) predict the 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 operations:
AZ.06 Inadequate system flow RO 3.2 I SRO 3.2
- d. Restore a RWCU Pump After Oil Sample (Plant Hot) With System Leak N.S 5 and Failure to Isolate 223002 Primary Containment Isolation System /Nuclear Steam Supply Shut-Off AZ. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR 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:
A2.03 Svstem logic failures RO 3.0 I SRO 3.3
- e. Respond to Multiple Rod Drifts and RPS Failure 7 212000 Reactor Protection System A2. Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.16 Chanaina mode switch Dosition RO 4.0 I SRO 4.1
- f. Respond to Refuel Floor High Radiation 9 272000 Radiation Monitoring System A2. Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.12 Refuel floor handling accidents/operations RO 3.3 ISRO 4.0
- g. Manually Initiate Div 1 Emergency Equipment Cooling Water 8 400000 Component Cooling Water Systems (CCWS)
A4. Ability to manually operate and Ior monitor in the control room:
A4.01 CCW indications and control .RO 3.1 ISRO 3.0 h.
In-Plant Systems" (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Shift In Service IAS Dryers D.R 8 300000: instrument Air System A2. Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
A2.01 Air drver and filter malfunctions RO 2.9 ISRO 2.8
- j. Defeat ARI Logic Trips 7 216000: Nuclear Boiler Instrumentation Generic 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications. RO 4.2 ISRO 4.1
- k. Place ESF Battery Charger in Service 6 263000: DC Electrical Distribution Generic 2.1.30 Ability to locate and operate components, including local controls. RO 4.4 ISRO 4.0 K1. Knowledge of the physical connections and/or cause effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following:
K1.02 Battery charger and battery RO 3.2 ISRO 3.3
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
'Type Codes I Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -
<9/ 58 1 5 4 (E)mergency or abnormal in-plant -
> 1 1 ?I1 > 1 (EN)gineered safety feature - I - / > 1 (control room system)
(L)ow-Power I Shutdown -
>1/ 21 1>1 (N)ew or (M)odified from bank including 1(A) -
> 2 1 22 1 > 1 (P)revious 2 exams -
< 3 15 3 I 5 2 (randomly selected)
(RFA -
> l I >1 / > 1 ES-301, Page 23 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Fermi-2 Date of Examination: 01/28/2008 Exam Level: RO 0 SRO-I 0 SRO-U Operating Test Number: 2008-1 Control Room Systems' (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety System / JPM Title Type Code' Function
- a. Temporary Removal and Restoration of SDC for I&C Surveillances N,EN,A,S 4 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)
A4. Ability to manually operate andlor monitor in the control room:
A4.01 SDClRHR pumps RO 3.7 / SRO 3.7 A4.03 SDClRHR discharge valves RO 3.6 / SRO 3.5 A4.05 Minimum flow valves RO 3.2 I SRO 3.2
- b. Respond to Refuel Floor High Radiation 9 272000 Radiation Monitorlng System A2. Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.12 Refuel floor handling accidentdoperations RO 3.3 I SRO 4.0
- c. Manually Start the RClC System D.S 2 217000 Reactor Core Isolation Cooling System A4. Ability to manually operate and/or monitor in the control room:
A4.04 Manually initiated controls RO 3.6 I SRO 3.6 Implant Systems" (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Place ESF Battery Charger in Service D.R 6 263000: DC Electrical Distribution Generic 2.1.30 Ability to locate and operate components, including local controls. RO 4.4 I SRO 4.0 K I . Knowledge of the physical connections and/or cause effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following:
KI.02 Battery charger and battery RO 3.2 I SRO 3.3
- j. Defeat ARI Logic Trips 7 216000: Nuclear Boiler Instrumentation Generic 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system imDlications. RO 4.2 I SRO 4.1
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
I T y p e Codes I Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -e 9 1 (a 1 5 4 (E)mergency or abnormal in-plant -
> I / 21 / > I (EN)gineered safety feature I 2 1 (control room system)
(L)ow-Power I Shutdown -
> I 1 21 / > I (N)ew or (M)odified from bank including 1(A) -
>2/ 22 121 (P)revious 2 exams - 3 15 3 I 5 2 (randomly selected)
(RFA -> I 1 >I1 2 1 jS)imulator ES-301, Page 23 of 27
ES-401 BWR Examination Outline Form ES-401-I iacility: Fermi 2 Date of Exam: I/28/2008 qote: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each KIA category shall not he less than two).
- 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 i l from 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. Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401. for guidance regarding elimination of inappropriate WA statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall he selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers I and 2 from the shaded systems and WA categories.
- 7. The generic (G) WAS in Tiers I and 2 shall be selected from Section 2 of the WA Catalog, but the topics must he relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable WAs
- 8. 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. If fuel handling equipment is sampled in other than Category A2 or G on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # Idoes not apply).
Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3. select tooics from Section 2 of the WA Cataloe. and enter the KIA numbers. descriotions., IRs., and point totals (#)on Fbrm ES-401-3. Limit SRO selections;o WASthat are linked to IOCFR55.i3
ES-401 2 Form ES-401-1 I ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier I/Group 1 (RO / SRO)
Form ES401-1 I
I E/APE # / Name I Safety Function I K I 2WOOJ Partiid or Tutal l m s oCIX Pwrlb I
?9501b Control Room Abnndoninent I 295025 Iligli Rcuctur Pressure 1 3 29?030 Low Suppression Pnnl Water L.crcl i s I 295038 High OW-sttc Rclcax Kate I 9 followingresponses as they apply 10 PARTIAL 295001 Panial or Complete Loss of OR COMPLETE LOSS OF FORCED CORE Forced Core Flow Circulation I 1 & 4 FLOW CIRCULATION : Reduced Imp I 295003 Panial or Complete Loss of ACl6 COMPLETE LOSS OF A.C. POWER : Bane I 295004 Panial or Total Loss of E Pwr 16 I
l3295005 Main Turbine Generator Trip I 295006 SCRAM I I I
i power AK2 07 - Knowledae of the interrelations 295016 Control Room Abandonment I following responses as they apply to 295018PartialorTotal LassofCCW / PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :
Increasing cooling water flow to heat 295019 Panial or Total Loss of Inst.
PARTIAL OR COMPLETE LOSS OF Air I 8 INSTRUMENT AIR : Instrument air system ressure I 295021 Loss ofShutdown Cooling1 4 between LOSS OF SHUTDOWN COOLING and the fo owing Reactor rec rculation
ES-401 2 Form ES-401-1 ES401 BWR Examination Outline Form ES401-1 Emergency and Abnormal Plant Evolutions -Tier 11Group 1 (RO I SRO)
EIAPE # I Name I Safety Function IR 295023 Refueling Accidents I 8 3.6 295024 High Drywell Pressure / 5 3.9 impiications of the following concepts as 295025 High Reactor Pressure13 3.6 295026 SuppressionPool High Water 3.5 Temp. I 5 29503 I Reactor Low Water Level / 2 4.2 295028 High Drywell Temperature / 5 3.8 295030 Low Suppression Pool Water 3.4 Level I 5 295037 SCRAM Condition Present and Power Above APRM Downscale 3.9 or UnknownI I -
295038 High Off-site Release Rate 1 9 3.8 600000 Plant Fire On-site I 8 2.8 700000 Generator Voltage and Electric D ELECTRIC 3.8 3 i d Disturbances WA Category Totals:
ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-Emergency and Abnormal Plant Evolutions- Tier 1IGroup 2 (ROI SRO)
EIAPE # I Name ISafety Function K K KIA Topic@)
1 2 Z95008 I ligh Reaclar Wslrr Lcvrl 1 2 295012 High Ikywell 'Tcmpcraturc I5 295033 High Secondary COW.iinmeni the Followingas they apply > f I(?>
Area Iladiation Lcvcis 1 9 295007 High Reactor Pressure 13 X 295010 High Drywell Pressure IS 295012 High Drywell Temperature I S 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels 1 9 295036 Secondary Containment High X
SumplArea Water Level I 5 KIA Category Totals: 1 1 1 '
ES-401 4 Form ES-401-1 is401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier Z/Group 1 (RO / SRO)
System # / Name H U K/A Topic@)
4 5 223002 ITlSRjuclear Stcain
$upply SllUtOtT 21 8000 ADS the cmseqecnccs of those ohnormal conditions or opcrations: ADS initiation 215003 IRM POWFR RANGII MONI'IORII.OCAI.
POWER RANGF MONITOR SYSTI'M ;
215005 APRM/I.I'KM and (h) b i w d on ~hosc.predictions. ~ise procedur~.~ 10 correct. conlid, or rnitigitlc use plant cmnputers to cvaluatc system or connections andlar cause- effect 203000 RHRLPCI: Injection relationshipsbetween RHRLPCI:
Uode INJECTION MODE (PLANT SPECIFIC) and the following: Condensate storage and chanaes in Darametem associated with operitmg t i e SHUTDOWN COOLING 205000 Shutdown Cooling SYSTEM (RHR SHUTDOWN COOLING MODE) controls including 206000 HPCI predictions. use procedures to correct.
control or mitiaate the conseauences of those abnorkal cond t ons or operations A C fat ares BWR-2 3.4 1 1 K3 03 - Knowledae of the eflentnat a loss or malfunction of the LOW 209001 LPCS PRESSURE CORE SPRAY SYSTEM will have on following: Emergency 21 1000SLC 212000 RPS
\
ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)
System # / Name < KIA Topic@) IR #
I I I 2 4 31 Knowledge of annunciator 215003 IRM X alarms, indications, or response 4.2 7 I I procedures I K2 01 - Knowledae of electrical Dower 2 I5003 IRM supplies to the foilowing: IRM 2.5 8 channelddetectors RANGE MONITOR (SRM) SYSTEM 215004 Source Range Monitor design feature@)andlor interlocks 3.7 9 which provide for the following: Rod withdrawal blocks implications of the following MnCepts as they apply to AVERAGE POWER 215005 APRM / LPRM 2.9 IO RANGE MONITOWLOCAL POWER RANGE MONITOR SYSTEM LPRM I I detector location and core symmetry I 2 2 44 -Equipment Control Ability l o I
interpret wntrol room indications to verify the status and operation of a 217000 RClC 4.2 II X I svstem and understand how oDerator ahions and directives affect plant and system conditions I I K6 04 - Knowledae of the effect that a loss or malfunction of the following will 218000ADS have on the AUTOMATIC 3.6 12 DEPRESSURIZATIONSYSTEM : Air 223002 PClSMuclear Steam andlor monitor in the control room: 3.6 13 Supply Shutoff loss or malfLnction of tne IOIOW ng w 239002 SRVs 3.0 14 have on the RELIEFSAFETY VALVES I I : Discharge line vacuum breaker I K5 04 - Knowledae of the ODerational mplications of tne fol owing wncepts 239002 SRVs as they apply l o RELlEFlSAFETY 3.3 I5 VALVES Tail pipe temperature montlor n ofthe following on the REACTOR WATER LEVEL CONTROL SYSTEM 259002 Reactor Water Level ana (b) Dased on those preoicbons 3.2 16 Control use proceoures to correct. control or m mate the consea.ences of tnose abnormal conditions or operations loss or malfunction ofthe STANDBY 261000 SGTS 3.0 17 261000 SGTS 3.2 18
ES-401 4 Form ES-401-1 I ES401 Plant Systems 1Tier ZGroup 1 (RO / SRO) 91 1 2 3 4 KIA Topic@)
I IR Major breakers and control power I
2 4 35 - Emergency Procedures IPlan Knowledge of local auxiliaty operator 9 0 I I I I I tasks during emergency and the I ' O I I I I I resutantoperatioialetiects I K4 06 -Know edge of EMERGENCY GENERATORS (DIESEUJET) design II II II II II feature@)andlor interlocks which Drovide for the followina Governor bontrol II 26 K4 03 - Knowledge of (INSTRUMENT AIR SYSTEM) desian featureb) and or curing of IAS upon loss of I I I I SYSTEM ml,d.ng Air temperature I I K2 01 - Know edge of e enrica power I _I ,,
I,,,I I I I supplies tothe following CCW pumps I 2 6 2 2 6 Group Poinl Total
ES-401 5 Form ES-401-1 I BWR Examination Outline Plant Systems -Tier 2/Group 2 (RO / SRO)
Form ES-40 I System # / Name Kl Kl 5 6 1 2 A3 I 4/
A KIA Topic@)
271000 ow-ga5 201002 RMCS 204000 RWCU 215002 REiM 234000 Fuel Handling Equipment 201001 Control Rod Drive 245000 Main Turbine Gen. I Aux.
I 256000 Reactor Condensate I 271000 Off-gas
ES-401 5 Form ES-401-1 I ES-401 BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO / SRO)
Form ES-401 1
ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3
'acility: Fermi-2 Date of Exam: 1/28/2008 RO SRO-Onlv Category Topic IR
- 2. I .43 Ability to use procedures to determine the effects on reactivity of plant changes. such as KCS temperature.
secondary plant, fuel depletion, etc.
4.3 I 94
- onduct 2.1.41 Knowledge of the refueling process.
if Operations Ability to use procedures related to shift staffing, 2.1.5 such as minimum crew complement, overtime limitations, etc.
-t hbtotal Knowledge ofthe process for controlling equipment Ability to determine Technical Specification Mode of Knowledge of the process used to track inoperable 2.2.43 3.0
- quipment alarms.
- ontrol Ability to determine the expected plant configuration using design and configuration control 2.2.15 documentation, such as drawings, line-ups, tag-outs, 3.9 etc.
2.2.40 Abilitv to amlv technical specifications for a system. 3.4
,.>,I j ubt ot a I ,,
,, 2 Ability to use radiation monitoring systems, such as 2.3.5 fixed radiation monitors and alarms, portable survey 29 97 instruments, personnel monitoring equipment, etc.
., 1 1.3.4 Knowledze - of radiation exposure limits under normal or cmergency conditions.
37 98 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as Ladiation response to radiation monitor alarms, containment
- ontrol 2'3'13 3.4 entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.
Knowledge of radiation monitoring systems, such as 2.3.15 fixed radiation monitors and alarms, portable survey 2.9 instruments, personnel monitoring equipment, etc.
Subtotal 2
ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 7 Category Topic Cate gory t
I I Y 2.4.20 Knowledgc of opcrational implications of EOP
~orniiigr.caJiioiis. and iiol~>.
Kiior Idg: uI'iIic basus for prioritizing cmqenc)
I -1..
4.3 2.4.23 proccdureimplementation during emergency 4.4 operations. __
1.
-Emergency I Knowledge of EOP entry conditions and immediate
'rocedures 4,6 73 action steps.
'Ian Knowledge of "fire in the plant" procedures. 3.4 74 Knowledge of emergency communications systems 2.4.43 3,2 75 and techniques.
Appendix D Scenario Outline FOITII ES-D-1 Facility: Fermi 2 Scenario No. 1 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Palaqi Initial Conditions: IC-18, MOL, 75% Rx. Power Turnover: The plant has been operatinq for 103 davs. Reactor Power is currently 75% of Rated Thermal Power with Control Rods at the 86% Rod Line followino rod pattern adiustment.
Seneral Service Water Pump #4 is out of service for motor replacement with an expected return
- o service in 2 davs. This shin will start the East Heater Feed Pump and raise Reactor Power to 35% of rated with Recirculation flow. Reactor Enoineerina will be readv in one hour to pull rods for another rod pattern adiustment. GOP 22.000.03, "Plant Operation 25% to 100% to 25%"
[Rev 73) actions for power increase are complete throunh Step 4.2.17.1.
NOTE: The crew's Pre-job Briefing for the reactor power increase is to be conducted prior to Event entering- the simulator. (SI gested time 30 minutes prior to beginning the scenario.)
Malf. No. I Event Event No. Description
- 2. NIA R (ATC) Increase Reactor Power With Recirculation Flow per GOP R (SRO) 22.000.03,"Power Operation 25% To 100% To 25%".
- 3. 831RFOOl5 C (ATC) RRMG " B Walkaway C (SRO) Uncontrolled RRMG " B Speed Change (>IO%). crew trips the affected RRMG (Immediate Action per AOP 20.138.03, "Uncontrolled Recirc Flow Change"). Crew enters AOP 20.138.01, "Recirc Pump Trip", Condition C & D.
CRS directs increased core monitoring for instability. He also directs increasing speed on the operating RRMG to raise core flow (>43%) and exit the ScramlExit Region of the Power to Flow Map.
CRS reviews TS 3.4.1.A, Recirc Loops Operating, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to declare loop inop and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to adjust RPS trip setpoints to single loop values.
- 4. E51MF0009 C (BOP) Spurious RClC Initiation C (SRO) Spurious start of RCIC, BOP verifies no valid actuation signal and trips RClC when directed. CRS reviews TS 3.5.3.A, RClC System, (Immediately verify HPCl operable I
and 14 day LCO).
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39
Appendix D Scenario Outline F o ES-D-1
~
Facility: Fermi 2 Scenario No. 1 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Palaai Initial Conditions: IC-18, MOL, 75% Rx. Power.
NOTE: Continued from age 1 Event Malf. No. Event I Event No. Type* I Description
- 5. R11MFOOOl M (All) Loss of Div 2 Offsite Power / EDGs start / Loss of all Heater Feed Pumps, and Reactor Feed Pumps.
N20MF0023 Loss of all Div 2 Buses. EDGs 13 & 14 auto start and re-energize ESF buses only. CRS enters AOP 20.300.345kV, Mode Switch in SHUTDOWN, and performs AOP 20.000.21, "Reactor Scram". CRS enters EOP 29.100.01, "RPV
- 6. E41MF0009 C (BOP)
-Control", Sheet 1 (Level 3).
HPCl Auto Start Failure E41MF0005 C (SRO) HPCl fails to start on Level 2. The crew will identify and manually start HPCl using SOP 23.202, "HPCI System",
Encl C. (Hard Card), but HPCl will isolate after about 1 min of oDeration.
- 7. N21MF0031 C (BOP) SBFW Fool Fails As Is N21RF0019 c (SRO) BOP will start SBFW Pump A, for level control, and identify a Fool failure to open. When he depresses the valve's Open pushbutton the valve will lose power. The BOP will direct an operator to investigate and restore. NOTE: SBFW Pump A is the only available pump.
8a. B31MF0066 M (All) Recirc Loop A Rupture LOCA - A Recirculation leak will cause High Drywell Pressure and level to decrease. EOP 29.100.01, RPV Control, Sheet 1 re-entry on high Drywell Pressure and EOP Primary Containment Control, Sheet 2 entry on High Drywell Pressure.
The crew will start all available high pressure injection systems. (SLC and re-starts RCIC by resetting the Trip Throttle Valve due to spurious initiation still in 23.206, RCIC, Sect 7.1 or Encl B Hard Card)
At -100 RPV Water Level BOP reports water level cannot be maintained =. TAF.
I CRS briefs crew for Emergency Depressurization.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39
Appendix D Scenario Outline F o ES-D-1
~
Facility: Fermi 2 Scenario No. 1 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Pilaaai Initial Conditions: IC-18, MOL, 75% Rx. Power.
NOTE: Continued fron age 2 Event Malf. No Event Event
- No. Type' - Description 8b.. NIA M (ALL) AT TAF Emergency Depressurizes (EOP C-2) EOP 29.100.01, RFIEDISC, Sheet 3 (CT). BOP opens 5 SRVs ADS preferred.
Crew restores water level 173 - 2 1 4 with available High Pressure and Low Pressure ECCS Svstems. (CT)
I (SRO) ATC verifies EECW actuation and isolation to the Drywell.
Determines Div 2 EECW is not isolated, and isolates by closina the P4400-F606B. He then restores coolina to CRD.
N (SRO) Encl A. (Hard Card)
Crew sprays the Drywell using SOP 23.205, "RHR System",
Encl A. (Hard Card) (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39
Awendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 2 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Palaai Initial Conditions: IC-20, MOL, 100% Rx. Power Turnover: The plant has been operatina for 23 davs. Reactor Power is 100% of Rated Thermal Power. The South RBCCW Pump is out of service for motor replacement. It is scheduled to be restored tomorrow. Plans are to shift from Division 1 CCHVAC to Division 2 to collect routine vibration data on Division 2 CCHVAC eauipment.
NOTE: The Pre-iob Briefing for the CCHVAC shift is to be conducted Drior to enterino the sirnulato;. (sug IsTed time 30 minutes prior to beginning the scenario.)
Event No.
I Malf. No. Event Type*
Event Description I__
1.
N (SRO)
Crew shifts from Division 1 CCHVAC to Division 2 CCHVAC C11MF0445 C97MF1087 MF EBAORL TCTVSP 1
- 4. N61MF0003 M (ALL) East Condenser Air Leak CRS enters AOP 20.125.01, "Loss of Condenser Vacuum".
c (ATC) BOP starts an additional SJAE and OG Ring Water C (SRO) Pump.
I R (ATC) ATC attempts Rapid Power Reduction, per SOP R (SRO) 23.623, Reactor Manual Control System, Section 9.7, and determines failure of Manual Runback. ATC takes individual manual control to reduce recirc speeds to 55-60% core flow.
- (N)ormal, (R)eactir P
Appendix D, 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 2 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore 6.Palaai Initial Conditions: IC-20, MOL, 100% Rx. Power.
NOTE: Continued from page 1.
Event No.
I Malf. No, Event Type' Event Description M (ALL) Reactor Scram Performs override action 20.125.01 and places Mode Switch in SHUTDOWN 5 2.5 psia.
After Scram Reports, CRS enters EOP 29.100.01 RPV Control, Sheet 1 (Level 3) and directs entry into AOP 20.000.21, Reactor Scram.
BOP controls water level 173 - 214 inches.
C97MF1087 M (ALL) Aftershock Seismic Event / Event Trouble Alarm (6D69)
B21MF0059 I (ALL) Loss of all level indication. Div 1 and Div 2 Level 821MF0060 Instrument Reference Leg Ruptures. Flood up Level Indication fails upscale high. (Level 8 trip on Main 621MF0073 Turbine, RFPs, HPCI, RCIC, and SBFW.)
CRS enters (EOP C-4) EOP RPV Flooding, 29.100.01, Sheet 3. (Level cannot be determined)
CRS enters EOP 29.100.01, Primary Containment Control, Sheet 2. (High Drywell Pressure) 621MF0037 C (BOP) When BOP is directed to open 5 SRVs, SRV " R fails to C (SRO) open. BOP will select and open another SRV and report this to the CRS. (CT)
I I ALL The crew floods to the Main Steam Lines using Feedwater, SBFW, and Low Pressure ECCS Systems.
(CT)
(N)ormal. (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39
Appendix D Scenario Outline IW IOF ES-D-1 Facility: Fermi 2 Scenario No. 3 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Palaai Initial Conditions: IC-19, EOL. 100% Rx. Power Turnover:
The plant has been operating for 403 davs. Reactor Power is currentlv 100% of Rated Thermal Power with Control Rods at the 86% Rod Line followina rod pattern adiustment. The N. Turbine Lube Oil Vapor Extractor is out of service for motor replacement. APRM # I is bypassed due to a power SUDD~Vfailure and a trackina LCO is written for it. The plan for the shift is to remove the North TBCCW Pump from service for lubrication and outboard motor bearing replacement. The shift is also to perform 27.109.01, "Turbine Steam Valves Test. The crew will beain with the LPSV and LPCV portion of the test because I&C support will not be available to perform the on-line valve position calibration on # I LPlV later in the shift.
NOTE: The crew's Pre-job Briefing for the reactor power decrease and "Turbine Steam Valves Test" is to be conducted prior to entering the simulator. (Suggested time 30 minutes xior to beainnina the scenario.)
Event Malf. Event Event 1.
No. No.
-Type' Description N (BOP Crew shifts TBCCW Pumps due to scheduled maintenance N (SRO on North TBCCW Pump.
- 2. NIA R (ATC: Lower reactor power to 93% with Recirculation Flow per R (SRO GOP 22.000.03, "Power Operation 25% to 100% to 25%", in preparation to perform 27.109.01, Turbine Steam Valves Test.
- 3. N30MF0036 C (BOP Crew performs section 5.7 of 27.109.01. Tests LPSV # I C (SRO and closes LPlV # I for on-line valve position calibration.
When I&C reports complete BOP determines, # I LPlV fails to re-open. Crew stops test, informs Ops Management, and System Engineer of problem.
C51MF0002 I (SRO) When directed, ATC removes APRM #I from bypass and bypasses #2 APRM per 23.605, "Average Power Range Monitoring (APRM) System", Sect 6.4. (APRM #1 downscale and rod block in alarm.)
SROreviewsTS3.3.1.1.F(Mode2-6 hrs).
- (N)ormal. (R)eact :v. (l)nstrument, (C)omponent. (M)aior Appendix D, 38 of 39
Aooendix D Scenario Outline I I IF O
I ES-D-1 Facility: Fermi 2 Scenario No. 3 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Palaai Initial Conditions: IC-19, EOL. 100% Rx. Power.
-NOTE: Continued from age 1 Event 7
Malf. Event Event
-5.
No. No.
821MF0029 Type*
Description C (SRO) BOP takes immediate actions per AOP 20.000.25, Failed Safety Relief Valve (SRV), by depressing the open and closed pushbuttons repeatedly. The SRV will close.
The CRS reviews TS 3.4.3.A, SRVs (tracking LCO), TS 3.6.1.6.A, Low - Low Set Valves (14 day LCO), and TS 3.6.1.8, Suppression Chamber-to-Drywell Vacuum Breakers (SR 3.6.1B.2, 12 hrs to perform the vacuum breaker test after a SRV discharge to Torus).
May direct removing fuses to prevent re-occurance per AOP 20.000.25, Enclosure A.
-B087-1 C (SRO) ATC observes and reports. SRO enters AOP 20.106.03, CRD Flow Control Valve Failure, Condition A. ATC takes manual control, opens, and adjusts CRD Pressure.
- 7. N30MF0044 M (ALL) Turbine Trips I Failure to Scram (ATWS)
C71MF0006 C (ATC) Failure to scram is reported and the crew enters the EOPs CIIMF0001 C (SRO) on Scram Condition with power > 3%. CRS directs actions from 29.100.01 Sheet IA, RPV Control-ATWS. ATC performs FSQ 1-8 actions (unsuccessful) and BOP performs inhibit ADS, bypasses Drywell Pneumatics, and directs 29.ESP.11.
- ~~
C41MF0004 C (SRO) When ATC is ordered to inject SLC. He informs CRS and starts second SLC Pump. SLC is successfully injected. (CT) 9 NIA M (ALL) BOP lowers water level and maintains 0 - 5 0 wr (EOP C-5, Level I Power Control)
ATC performs manual rod insertion (CT). When 29.ESP.10 (Defeat of ARI Logic Trips) is complete and ARI Trip Logic is reset, the scram discharge volume will drain (3D94 Clear).
The ATC will perform the Scram-Reset-Scram section of 29.ESP.03, Alternate Control Rod Insertion, which will insert all rods.
-* (N)ormal. (R)eactivity, (I)nstrument, (C)omponent. (M)ajor Appendix D, 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 4 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Palaai Initial Conditions: IC-20, MOL, 100% Rx. Power Turnover: The plant has been operatina at 100% power for 400 davs. Reactor Power is currentlv 100% of Rated Thermal Power with Control Rods at the 86% Rod Line followina rod pattern adjustment. The plan for the shift is to shift RBCCW Pumps for scheduled maintenanc on the center pump.
NOTE: The crew's Pre-job Briefing for the reactor power increase is to be conducted prior to entering the simulator. (Suggestedtime 30 minutes prior to beginning the scenario.)
I 3_
Event Malf. No. Event Event NO.
- Type' N (BOP)
Description Shift RBCCW Pumps in accordance with SOP 23.127,
- 1. N/A N (SRO) Section 6.1
- 2. 821MF0044 C (ATC) Jet Pump 5/6 Failure c (SRO) ATC observes Recirc Loop Flow changes and diagnoses Jet Pump failure. The crew enters AOP 20.138.02, "Jet Pump Failure". The SRO evaluates TS 3.3.1.1.C (1 hr LCO), TS 3.3.1.1.F(6hrstoMode2),TS3.4.1.A(2 hrLCO),andTS 3.4.2.A (12 hrs to Mode 3). The CRS declares JP #5 inoperable and directs the ATC to monitor for thermal hydraulic instabilities.
- 3. N21MF0029 R (ATC) Spurious N. RFP Trip / RRS Runback / Loss of Heater R (SRO) Drains C (BOP) Crew enters AOP 20.107.01, "Loss of Feedwater or C (SRO) Feedwater Control". The crew verifies RR runs back, starts SBFW and injects at 1200 gpm, and inserts the Cram Array to lower reactor power to 5 65%. (-15% reactivity change)
- 4. C51MFOI 98 I (ATC) RBM B Fails High I (SRO) The crew bypasses RBM B per 23.607. "Rod Block Monitoring System", Section 5.1. The CRS declares RBM B inoperable and enters TS 3.3.2.1.A (24 hr LCO).
5a. E41MF0007 C (BOP) HPCl Steam Leak & E4150-F002 Failure to Auto Isolate I EOPRF0022 C (SRO) E4150-F600 Thermal Overload E41MF0001 Fire Alarm in the HPCl Quad, the crew may enter AOP E41MF0008 20.000.22, "Plant Fires". When 3D34, SEC CONTM TEMP HIGH - HIGH EOP ENTRY alarms the crew will enter EOP 29.100.01, SC/RR, Sheet 5 due to HPCl Area temperature greater than Max Normal Operating (MNO) 148 OF..
- (N)ormal, (R)eactivity, (1)nstrument. (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Appendix D, 38 of 39
Facility: Fermi 2 Scenario No. 4 Op-Test No: 2008-1 Examiners: M. Bielbv Operators:
C. Moore B. Palaqi Initial Conditions:
NOTE: Continued from page 1 Event Event
- No. Description 5b. NOTE: 1D66, STEAM LEAK DETECTION AMBIENT TEMP HIGH alarms at 2 154 OF in HPCl area and an isolation signal is generated.
When BOP attempts to isolate and E4150-F002 will not close (failed as is) and when E4150-F600 valve close pushbutton is depressed or an isolation signal is received, the valve loses power. The leak cannot be isolated.
- 6. NIA I M (ALL) Reactor Manual Scram (Mode Switch to Shutdown)
Before the HPCl Area temperature reaches the Max Safe Operating Temperature (MSO) of 210 OF, the crew briefs and places the Mode Switch in Shutdown. (CT)
When Scram Reports are complete the crew enters EOP 29.100.01, RPV Control, Sheet 1 (Level 3) and AOP 20.000.21, Reactor Scram.
- 7. RB Steam Tunnel Leak I MSlVs Fail to Isolate Crew observes increasing temperature in RB Steam Tunnel B21MF0009 on IPCS. Crew should attempt to isolate the steam leak, by B21MF0054 closing the MSIVs, when the area temperature is 2 160 O F (MNO), to isolate all systems discharging into the area. IF area temp is 2 200 OF and the MSlVs are not closed, then the crew should close them due to the auto isolation failure.
NOTE: MSL C MSlVs do not fully close.
- 8. M (ALL) When Area Temperatures are > MSO (210 O F ) in 2 areas the EOP directs Emergency Depressurization, EOP 29.1 00.01 RPV Flood/ED, Sheet 3 (EOP Contingency 2).
CRS directs BOP to open 5 SRVs (ADS preferred) (CT) and while the plant is depressurizing the crew briefs water level restoration and control.
9 NIA The crew restores and maintains water level 173 - 214" (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D,38 of 39
Outline Review 10/30/07 I COMMENT I RESPONSElRESOLUTlON I WRITTEN EXAM:
No comments.
ADMIN JPMs:
II Suggestions:
-On the RO and SRO ES 301-1 forms, assign Ialign common letter designators to the admin JPMs.
SYSTEM JPMs:
I- Suggestions:
On the RO and SRO-I:-U ES 301-2 forms. alian similar JPMs to the same 'letter designatof
. I
-Pick the 5 SRO-U from the SRO-I JPMs (created 1 new JPM).
- 1. How did you select the JPMs from the previous 2 exams?
- 2. The Emergency or Abnormal inplant JPM KAs have to Licensee followed their process for randomly selecting exam material (submitted copy with outline).
Licensee will look to see if they can apply one of I
come from the 295- KAs vice the Generic 2.4.- section the 295- KAs to the existing JPM.
(SF 7, 216000. Defeat ARI Logic Trips).
- 3. Delete the reference to Generic 2.1.30 from the system Agreed.
JPM. DC Electrical Distribution, 263000. on ES-301-2.
I SCENARIOS:
- 1. No "low power" scenario (ref ES 301, D.5.c) ES 301, D.5.c says "should." QA sheets, ES-301-4 and -201-2 do not require a low power scenario.
Have used low power scenarios on previous exams and minimum number of events that can be used (don't want to be oredictable).
I SCENARlOl:
- 1. Event 3, where should the RRMG walk-away occur to If RRMG speed is 57%. will enter the prohibited ensure entry into the scramlexit region? region. Will coordinate with examiner directing events and practice during validation.
evaluation of the BOP. or does he only depress the trip Will look at providing more actions (ie. injection pushbutton? Need to look at taking more actions to achieve valve not dosing...).
a better evaluation.
- 3. Event 7, if there is no success path for aligning SBFW A, Will include manual startup of SLC andlor RCIC how do we hold the BOP accountable if he decides not to as part of the evaluation success path to achieve investigatethe SBFW A FOO1 failure, or does not identify it? adeauate RWL.
Page 1 of 3
Outline Review 10130107 COMMENT RESPONSE
- 5. Event 9, what are consequences of failing to isolate P44- Failure to isolate Div 2 EECW could result in an F606B? Suppose ATC fails, or decides not to perform the inner system LOCA due to heating of water in DW action, how do we hold him accountable? that causes piping to rupture. Isolation is required by EOP for PCP Sheet 2.
6 Event 10, spraying the Torus and DW is not a "N" Delete Event 10 as "N."
evolution It is an action directed by the EOPs when specific plant conditions require the action SCENARIO 2:
- 1. Event 2, why not have the rod driff out vice into, the core? The selected rod is full out, so will select a What are the ATC verifiable actions? partially inserted rod, and allow it to drifl out. The operator will be required to fully insert rod. Power will exceed required power limit.
- 2. Event 3, are there enough verifiable actions for an Will delete event as "C." but will leave in for a TS evaluation of the BOP? This is not a "C" because there are call.
no actions to take in response to the fan trip.
- 3. Event 4: Need to break up event and clarify who is getting
-not a "M." what credit. The "C" for ATClSRO is for failure of
-not a 'C" because starting SJAE and OG Ring Water pump the RRP Master Controller and taking individual does not provide a success path, still lose vacuum. manual control of RRPs (not starting the SJAE
-sufficient verifiable BOP actions for an evaluation? How do and OG RWP).
we hold the BOP accountable if he decides not to start SJAE or OG RWP, or is unsuccessful? The 'R" is for the Rapid Power Reduction.
-why is ATC given credit for 'C? Only "R" for SRO and ATC.
-may give 'C" for failure of the RMCS?
- 4. Event 6, this is "M-ALL" not "I-ALL," cannot restore level Delete the "I-ALL."
instrumentation. onlv take EOP directed actions for a flood.
SCENARIO 3:
- 1. Event 3, not a "C." BOP cannot take any verifiable Delete "C."
actions, cannot restore operability, can only stop test and make notifications.
- 2. Event 7: Clarify that "C" is failure of the normal scram
-what is the "C" and subsequent verifiable actions? What is function, and manual insertion of control rods is the success path (manually insert rods)? the success path.
-can't pet a 'C" and 'M" for the same event.
- 3. Event 8, what are the verifiable ATC actions for an Clarify the success criteria for starting the second evaluation (ie, what is critieria for being unsat)? SLC pump, ie. before BIT exceeds 110 degrees F.
SCENARIO 4 Page 2 of 3
COMMENT RESPONSElRESOLUTlON
- 1. Event 2, what audible cues does the ATC receive? High RWL on P-603. Need to verify during Suppose ATC doesn't identify the failure (BOP or SRO may validation.
unless we pull them back somehow).
3.Event 5a and b, not a "C," because can't isolate HPCl Delete "C."
steam leak. Don't have to take any action and get same result. Only provides a reason to scram.
- 4. Event 7, good chance BOPISRO will not identify "failure of Will leave in, but not depend on MSlVs to auto-isolate" if they manually close valves before exceeding 200 degrees F (would not get credit for "C."
Page 3 of 3