ML092870751
| ML092870751 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/13/2009 |
| From: | Operator Licensing and Human Performance Branch |
| To: | |
| References | |
| 50-259/09/301, 50-260/09/301, 50-296/09/301 | |
| Download: ML092870751 (62) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1
- Facility: Browns Ferry NPP Date of Examination:
Examination Level (circle one): RO'(SRO) Operating Test Number:
July 6 - 30, 2009 HLT 0801 Administrative Topic Type Describe activity to be performed Code *
(see Note)
Conduct of Operations M Determine Adequate Performance of License Reactivation JPM 541 (RO I SRO)
Conduct of Operations P Evaluate Recombiner Performance JPM 510 (RO/SRO)
Equipment Control D Perform Jet Pump Surveillance 2-SR-3.4.2.1 JPM 120F (RO I SRO)
- Radiation Control N Calculate the maximum permissible stay time within emergency dose limits and determine the approving authority JPM 528 (RO I SRO)
Emergency Plan N,S Classify the Event per the REP (Primary System Leakage (Torus Pressure) Exceeding PSP Curve)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (M)odified from bank (:: 1)
(P)revious 2 exams t: 1; randomly selected)
(S)imulator
HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License license Reactivation
- Modified:: OPDP-10 is a new procedure that removed information from OPDP-1 ,
Modified Conduct of Operations; and modified critical data in JPM
- OPDP-10, Maintenance, Reactivation and Proficiency for Non-OPDP-10, License Status Maintenance, Licensed Positions, Rev. Rev. 0, Appendix E
- G2-1.4 Knowtedge (32.1.4 KnOwtedge6f of individual licensed operator respOnsibilities responslbUIties related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of Bctlvellcense active license alatus, status, 10CFR55, 10CFR55, etc. (CFR: 41.10 143.2) IMPORTANCE:
41 .10/43.2) IMPORTANCe: RO 3.3 SR03.8 SRO .3.8
- b. Evaluate Recombiner Performance
- Previous: JPM revised to newest revision of 3-01-66 Previous:
- 3-01-66, Oft-Gas 3-01-66, Off-Gas System System,, Rev 57
- G2~ 1.7 Ability G2.1.7 Abili1y to evlluate evaluate plant performance perfonnance andrnake and make operational judgments based on operating chorae_llea, characteristics, reactor behavior, Indand instrument interpretation. 41 .5/43.5/45.12/45.13) IMPORTANCE RO 4.4 SRO 4.7 Interpretation. (CFR: 41.5/43.5/45.12/45.13)
- c. Perform Jet Pump Surveillance 2-SR-3.4.2.1 2-SR-3.4.2.1
- Direct: JPM revised to newest revision of 2-SR-3.4.2.1 2-SR-3.4.2.1
- 2-SR-3.4.2.1, Jet Pump Operability, 2-SR-3.4.2.1, Operability, Rev 25
- G2.2-12 Knowledge of of Surveillance Procedures.
G2.2.12 Knowtedge PrOcedures. (CFR: 41.10/43.3/45.13) 41.10 143.3/45.13)
IMPORTANCE: R03.7 RO 3. 7SROSR04.14.1
- d. Calculate the maximum permissible stay time within emergency dose limits and determine the approving authority
- New: JPM - Classroom
- EPIP-15, EPIP-15, EMERGENCY EXPOSURE, EXPOSURE, Rev 9 2~3.4 knOwt8dge
- G 2-3.4 Knowledge of radiation expOsure exposure limits under normal nonnal or emergency conditions. (CFR: 41 41.12 143.4 145.1 0) IMPORTANCE RO 3.2 SRO 3.7
.12/43.4/45.10)
.1PMs shown in italics
HLT 0801 Administrative Topics Narrative Administrative Topics: (continued)
CUlVe)
- New Ne w JPM - Simulator
- EPIP-1 EPIP*1 , Emergency Classification Procedure, Rev. 43, Primary Containment Procedure. Rev.
2.0, 2.1 2.0, Section 2.1
- EPIP-4, Site Area Emergency, Emergency, Rev. 31
- SRO Only
- GZ.4.38 Ability to take actions called for In G2.4.3B in the facility emergency
_ y ptan. plan, Incluc6.
including supporting or acting as emergency coordinator coordinatQr if required.
required. . (CFR: 41.10 41.10/143.51 43.S /
45.11) IMPORTANCE:
IMPORTANCE; SRO 4.4 SRO only JPHs JPMs shown in italics
ES-301 Administrative Topics Outline Form ES-301-1 I. Facility: Browns Ferry NPP Date of Examination:
Examination Level (circle one): RO '(SRO) Operating Test Number:
July 6 - 30,2009 HLT 0801 Administrative Topic Type Describe activity to be performed Code *
(see Note)
Conduct of Operations M Determine Adequate Performance of License Reactivation JPM 541 (RO / SRO)
Conduct of Operations D Perform Jet Pump Surveillance 2-SR-3.4.2.1 JPM 120F (RO / SRO)
/
Equipment Control P Determine Correct Method of Verification on a Given System JPM 550 (RO / SRO)
- Radiation Control N Calculate the maximum permisSible stay time within emergency dose limits and determine the approving authority JPM 528 (RO / SRO)
)j Emergency Plan N,S Classify the Event per the REP (Primary System Leakage (Torus Pressure) Exceeding PSP Curve)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol Room (D)irect from bank C:: 3 for ROs; :s. 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ~ 1)
(P)revious 2 exams C:: 1; randomly selected)
(S)imulator
HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License Reactivation
- Modified: OPDP-l0 OPDP-10 is a new procedure that removed information from OPDP-l, OPDP-1 ,
Conduct of Operations; Operations; and modified critical data in JPM
- OPDP-10, License Status Maintenance, OPDP-l0, Maintenance, Reactivation and Proficiency for Non-Licensed Lice nsed Positions, Rev. 0, Appendix E
- G2.1.4 Knowtedge of lndlvlduailicensed G2.1.4KnoWtedge individual licensed operator .... -Iliff r e _ to .hlft ponslbilltie. related responsibilities staffing. such as medical reqUirements, staffing, requirements, "no-&O'o" "no-solo" operation.
operation, maintenance of actlvelicen active license
.. status,
_ . 10CFR55.
10CFR55, etc. (CFR: 41 41.10
.10 143.2) IMPORTANC~: RO 3.3 143.2) IMPORTANCE:
SRO 3.8 b.. Perform Jet Pump Surveillance 2-SR-3.4.2.1 b
- Direct: JPM revised to newest revision of 2-SR-3.4.2.
2-SR-3.4.2.11
- 2-SR-3.4.2.1,, Jet Pump Operability, 2-SR-3.4.2.1 Operability, Rev 25
- G2.1.7 AbIlity Ability to evaluate plant performance and make operational judgme"tsjuc:tgmentS instrument based on operating characteristics, reactor behavior, and Instrument 41.5143.5145.12145.13) IMPORTANCE RO 4.4 SR04 interpretation. (CFR: 41.5/43.5/45.12/45.1311I1PORTANCE interpetath>n. SRO 4.7*.,
- c. Determine Correct Method of Verification on a Given System
- Exam: HLT 0707 (Modified slightly based on NRC feedback)
Previous NRC Exam:
- Program,, Rev.
SPP-10.3, Verification Program Rev. 1, Sections 3.3.1 3.3.1,3.4.2, 3.4.3
,3.4.2, and 3.4 .3
- the G2.2.14 Knowledge of the process for forcontroUingequipment controlling equipment configuration or status. (CFR: 41.10/43.3/45.13) 41.10 143.3145.13) IIiPORTANCE:
- d. Calculate the maximum permissible stay time within emergency dose limits and determine the approving authority
- New: JPM - Classroom EPIP-15,, EMERGENCY EXPOSURE,
- EPIP-15 EXPOSURE, Rev 9 expOsure limits under normal
- G 2.3.4 Knowledge of radiation exposure nonnal or em_ncy emergency 41 ..1~ 143~4/45.10) IMPORTANCE RO 3.2 conditions. (CFR: 41.12/43.4/45.10) 3.2, SRO 3.7 SRO only JPMs JPftfs shown in italics
HLT 0801 Administrative Topics Narrative Administrative Topics: (continued)
- e. Classify the Event per the REP (Primary Sys. Leakage (Torus Pressure)
Exceeding PSP Curve)
- New JPM - Simulator
- EPIP-1 , Emergency Classification Procedure. 43, Primary Containment Rev. 43.
Procedure, Rev.
2.0, Section 2.1 2.0, 2.1
- EPIP-4, Site Area Emergency.
EPIP-4, Emergency, Rev. 31
- SRO Only
- G2.4..38 G2.4.38.Ability to AbIlity to take ~lIed fo, talce actions called for in the facility emergency plan, including supporting or acling acting as emergancy emergency coordinator if required. (CFR: 41.10 41.10/43.5/
/43.5/
45~ 1 1) IMPORTANCE: SRO 4..4 45.11) 4.4
ES-301 Administrative Topics Outline Form ES-301-1
- Facility: Browns Ferry NPP Date of Examination:
Examination Level (circle one): RO'(SRO) Operating Test Number:
July 6 - 30,2009 HLT 0801 Administrative Topic (see Note)
Conduct of Operations Type Code
- M Describe activity to be performed Detennine Adequate Perfonnance of Licens~tion t/
!/i /
fy Conduct of Operations D Conduct of Operations Questiyred QUestio~red Turnover Tumover Information JPM 512 (RO / SRO)
/
Equipment Control P Determine Correct Metho~"Verification on a Given System JPM 550 (RO / SRO)/
/
- /
/
/
//
Radiation Control D Determine the pose Limitation for Declared and Undeclared Pregnant Female Employees and Their Eligibility for Overtime
/
JPM 511lRO ./
/ SRO)
//~
/
Emergency Plan N,S ClaSsify the Event per the REP (Primary System Leakage fT'orus Pressure) Exceeding PSP Curve) vfforus
/'
/
/' JPM 487TC (SRO Only) totaly{re required for SROs. RO applicants require only 4 items unless they NOTE: All items (5 totaly(re are retaking only the ~Jjininistrative topics, when all 5 are required.
/
/
(N)ew or (M)odified from bank ~ 1)
(P)revious 2 exams ~ 1; randomly selected)
(S)imulator
HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License Reactivation
- Modified:: OPOP-10 Modified OPDP-10 is a new procedure that removed information from OPOP-1 OPDP-1.,
Conduct of Operations; and modified critical data in JPM
- OPDP-10, License Status Maintenance, OPOP-10. Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev.
Rev. 00,, Appendix E
- G2.1 .4 Knowledge G2.1.4 KrioWl8dge of individuailicensad operator responsibilities indiViduai' licensedoperator _to resPonsibilities related to shift staffing, such as medical requirements, ""no-solo" stalling, nCHOlo" operation, maintenance of active Ucense 10CFR55, etc. (CFR: 41.10143.2) license, status, IOCFR55, 41 .10 143.2) IMPORTANCE: RO 3.3 SRO 3.8
- b. Conduct of Operations Question - Required Turnover Information
- Direct from Bank
- OPDP-1,, Conduct of Operations, Rev.
OPOP-1 Rev. 12, section 7.3.L
- q2~1.3 G2.1 .3 Knowledge 01 of shift or short-term short-tenn relieltumoyer practlceo. (CFR: 41.101 relieftumover practices. 41 .10 I 45.13) IMPORTANCE: RO 3.7SRO 3.7 SRO .3.9 3.9
- c. Determine Correct Method of Verification on a Given System Previous NRC Exam: HLT G2.2.14 Knowtedge HLT 0707 (Modified slightly based on NRC feedback)
SPP-10.3, Verification Program Program,, Rev. 1, Sections 3.3.1, 3.4.2, and 3.4.3 Knowledge of the process for lor controlling equipment configuration or status. (CFR: 41.10 statua. 43.3' 45.13) IMPORTANCE: RO 3.9 SRO 4.3 41.10'143,3145.13) d.. Determine the Dose Limitation for Declared and Undeclared Pregnant Female d
Employees and Their Eligibility for Overtime
- Direct from Bank
- SPP-5.1, Radiological Controls, Rev. 6, 6, Section 3.4.1 3.4.1
- radiatiorfexposure G2.3.4 Knowledge of radiation exposure limits under normal or emergency 41.12143.4/45.10) IMPORTANCE:
conditions. (CFR: 41.12143.4145.10) IIIPORTANCE: RO 3.2 SRO 3.7
HLT 0801 Administrative Topics Narrative
- r-. rr:' roo>""*"
r:;;:;: .<;::.i D
Administrative Topics: (continued) , ' . t;:k~.~",~ ~~
, ' ' ' ; . t. _" \
-'\,....
'-.;" ..I~
f
, 'fJ't.J- ~
- e. Classify the Event per the REP (Primary Sys. Leakage (Torus Pressure)
Exceeding PSP CUlVe)
Curve)
- New JPM - Simulator
- EPIP-1 , Emergency Classification Procedure, Rev. 43, Primary Containment 2.0, Section 2.
2.11
- EPIP-4, Site Area Emergency, Rev. 31
- SRO Only
- G2.4.'3BAbi/ity fOr GZ.4.38 AbIlity to take actions called for In in the facility "",.. gency pIM, facilnYfHnfwgency pian, Including including as emergency coorrtinator supporting or acting es coordinator if requIred.
required. (CFR:
(CFR:41. 10143.51 41.10143.51 45.11) IMPORTANCE: SRO 4.4
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- Facility:
Facilily: Browns Ferry NPP Exam Level (circle one):
Control Room Systems.
4Rqj)/
one): RO ~O;VI SRO-U Date of Examination:
Operating Test No.:
Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
July Jul~ 6 - 30, 2009 HLT 0801 Safety System I/ JPM Title Type Code*Code-Function a.
- a. Alternate RPV Injection - Standby Coolant S,E, S, E, EN,L, EN , L, N 2 b.
- b. RWM Functional Test for Startup 3-SR-3.3.2.1.2 S, L, N 7
- e. Emergency Ventilate Primary Containment S S, D, E, L 5
- g. Off-Gas Post-Treatment Radiation HI-HI-HI S, A.
S, A, 0D,, E, E, LL 9
- h. Placing Standby Steam Jet Air Ejector in Operation S,E,N S, E, N 4 Systems. (3 for RO); (3 for SRO~);
In-Plant Systems@ SRO-I); (3 or 2 for SRO-U)
- i. Shift From 'A' Set of CRD Stabilizing Valves to 'B' Set D, E, L, R 1 j.j. Place B2-3 B2-31; +/- 24V Neutron Monitoring Battery A, N 6 Charaer in Service to Battery Board 3 CharQer
- k. Bypass RCIC Low Pressure Isolation 3-EOI EoEN, L.
0 , E. L, 2 ApJ)endix-16A Aooendix-16A R
@ AU All RO and SRO-l SRO-I control room (and in-plant) systems must be different and serve different safety functions;; all 5 SRO-U systems must serve different ufety functions safety functions ; in-plant In-plant systems and functions may overlap overtap those tested in In the control room room..
- Type Codes Criteria for RO I SRO-II SRO-U SRO*U (A)ltemate (A)ltemale path 4-6 I 4-6 I 2-3 (C)ontrol room (D)lrect from bank ~9/~8/~4
~9/!::8 /~ 4 (E)mergency or abnormal fn-plant in-plant ~1/~1J~1
~1/~1'~1 (EN)gineered safety feature I ~
-* I *- 1 ::. 1 (control room system)
(L)ow-Power I Shutdown ~1/~1/~1
- ,1/::.1/::,1 (N)ew Of or (M)odified from bank induding including 1(A) ~2/~2/~1 (P)revious 2 exams ~ 3 I !~ 3 I ~
.:: .:: 2 (randomly selected)
(R)CA ~1/~1/~1
~l/!.'/::'l (S)imulator (S)imutator
HLT 0801 Control Room/In-Plant Room/ln*Plant Systems JPM Narrative Control Room Systems:
- New I Emergency or Abnormal In-Plant I Low-Power I ENgineered Safety Feature I Simulator
- Appendix-70, Alternate RPV Injection System Lineup Standby Coolant, 3-EOI Appendix-7D. Coolant, Rev. 2
- 203000 RHRlLPCI: Injection Mode (Plant specific)
Specific) A4.01'Ability A4.07 AbIlity to manually operate ancllor ope'"' c(mtrolroom:
and/or monitor in the control room: Reactor Water Level IMPORTANCE:
IIiPORTAHeE:
- New I Low-Power I Simulator
- 3-SR-3.3.2.1.2, RWM Functional Test for Startup, Rev. Rev. 3
- 201006 Rod Worth lIinimizer Minim1z8r Systert, System (RWM)
(RWII) (Plant Specific) A2.0S A2.05 Ability to (aJ (a) predict the im ....cta of the following on the ROD impacts ROO WORTH IIINIMIZER INIMlZER SYSTEM (RWII); and (b) based on those (RWM); _ uae procedures to correct, control, predictions, use or mitigate th.
the consequences of those abnonnal abnormal conditions condition. or operations:
operation.: Out QuI of sequence rod movement: Plant-5pecific Plant.specific (Not BWR-6)
BWR~) IMPORTANCE: RO 3.1
- c.
SRO 3.5 SR03.5 c . Place RCIC in Test Mode From Standby for Alternate RPV Pressure Control (JPM 43F U2)
- Direct from bank I Emergency or Abnormal In-Plant I Low-Power I Simulator
- Alternate Path:
Path : RCIC Trip Throttle Valve (71-9) is tripped and must be reset and opened opened.. RCIC Flow Controller fails while in service and candidate must take manual control
- 2-EOI Appendix-11 Appendix-l1B, B, Alternate Alternale RPV Pressure Control Systems RCIC Test Mode, Rev. 5 Mode,
- 241000 ReactorlTurbine Pressure Regulating System A4.02 Ability AbIlity to manually operate and/or monitpr monitor Inin the control room: R.actor ReactQr pressure IMPORTANCE:
IIiPORTAHCE:
- Modified I Emergency or Abnormal In-Plant I Low-Power I Simulator
- Alternate Path:
Path: must start other pump due to no flow
- 2-EOI Appendix-3A, Appendix-3A, SLC Injection, Injection , Rev. 5
- 211000 Standby Liquid liquid Control *A4.08 A4.OS Ability to manually operate'j 'ndJor monitor operate ancllor in the control room: System initiation: F!lant.pecific Plant...pecllic IMPORTANCE: RO 4.2 SR04.2
HLT 0801 Control Room/In-Plant Systems JPM Narrative
- e. Emergency Ventilate Primary Containment (JPM 55 U2)
- Direct from bank /I Emergency or Abnormal In-Plant I/ Low-Power /I Simulator
- 2-EOI Appendix-13, Appendix-13 . Emergency Venting Primary Containment, Containment. Rev.Rev. 6
- Prhllary Containment System and Auxiriarieis 223001 Primary A2.07 Ability to (a)
Auxiliaries Ai07 (al predict precllc1 tht.impacts the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; AUXIUARIES; and (bl (b) based on those predictions, useu.. procedures to correct, comtet.
control, or mitigate the consequences of those abnormal conditions condltiona o, orr operations: High drywell ......
operatlona: pressure IMPORTANCE: RO 4.2 SRO 4 ure .IMPORTANCE: ..3 4.3
- f. Parallel DIG With System 4KV SID Board at Panel 9-23 (JPM 104F U2)
- Direct from bank I/ Simulator
- Alternate Path:
Path: Once paralleled with offsite source, source, a voltage transient will occur requiring candidate to trip the output breaker
- 0-01-82 0-01-82., Standby Diesel Generator System, System , Rev.
Rev. 99, Section 8.1 8.1
- 264000 Emergency Emervency Generators (DieseVJetl (OieseUJet) A4.04 A4.D4 Ability to manUally manually operate and/or monitor in the control room: Manual start, loading, and atoppil!ll stopping of emergency generator: Plant-specific IMPORTANCE: RO 3.7 SRO 3.7 emervency
- g. Off-Gas Post-Treatment Radiation HI-HI-HI (JPM 390F U3) U31
- Direct from bank I/ Emergency or Abnormal In-Plant /I Low-Power /I Simulator
- Alternate Path:
Path : Offgas System Isolation Valve, Valve , 3-FCV-66-28 fails to close automatically requiring candidate to close manually
- 3-ARP-9-4C, 3-ARP-9-4C . Panel 9-4 3-XA-55-4C, 3-XA-55-4C , Rev.
Rev. 29, 29, Window Wind ow 35 (Page 45 of 45) and 3-AOI-66-2, 3-AOI-66-2 . Offgas Post Treatment Radiation Hi Hi Hi, Rev. Rev. 9
- 271000 Offgas System A2.D4A2.04 AbilitY Ability to (a)
(al predict the impacts of the following thelmpacll on the OFFGAS SYSTEM; and (bl (b) based on those predlctlona, predictions, ....
use procedures procedu.... to cOrrect, correct, control, or mitigate the consequences of those abnormal abnonnal conditions or operations:
operatlona: . Offgas Offgaa system aystem high radiation IMPORTANCE: RO 3.7 SRO 4.1
- h. Placing Standby Steam Jet Air Ejector in Operation (JPM 346 U3)
- New I/ Emergency or Abnormal In-Plant /I Simulator
- System,, Rev. 56, 3-01-66, Off-Gas System 56, Section 8.4
- 239001 Main ariel S~m System A2,oa and Reheat Steam A2.08 Ability to (a)
(al predict precllc1 the impac:ts impacts aftha of the following on the MAIN AND REHEAT STEAM SYSTEM; and (blbased (b) based on predictions, u those predictiona, use
.. procedures to correct, control, or mitigate the consequences of those abnormal conditions condltiona or operations: Low condenser vacuum IMPORTANCE: RO 3.6 SR03.6 SRO 3,6
HLT 0801 Control Roomlln-Plant Room/In-Plant Systems JPM Narrative In-Plant Systems:
i.
I. Shift From A'A' Set of CRD Stabilizing Valves to 'B' Set (JPM 113 U2)
- Direct from bank I Emergency or Abnormal In-Plant I Low-Power I RCA Entry
- 2-01-85, Control Rod Drive System,System, Rev. 112, 112, Section 6.4
- 201001 Control Rod Drive Hydraulic System A3.01 Al,01 Ability tomorlitor to monitor aautomatic operations of thetha CONTROL ROD ROO DRIVE HYDRAULIC SYSTEM including: Valve V.1v8 operation IMPORTANCE: RO 3.0 3,0 SRO 3.03,0 j.
j, Place B2-3 + 24V Neutron MonitoriMonitoringng Battery Charger in Service to Battery Board 3 (JPM 308F 30aF U3)
- New
- Alternate Path:
Path : When the Battery Charger is placed in service, service, voltage and amps will be out-of-specification out-aI-specification requiring candidate to open breakers and notify the Unit Supervisor
- 0-01-570, 0-01-57D, DC Electrical System, System, Rev. 121,121 , Section 5.13
- 263000 D.C, K1,02 Knowledge oftha D.C. Electrical Distribution K1:02 of the phyaical physiccll connactlons connections and/or ca .... _
cause-effect relationships _ n D.C, between D.C. ELECTRICAl,;;
ELECTRlC~
DISTRIBUTION DlSTRlBUnON and the tha following: aattery Battery charger and battery IMPORTANCE:
- from bank I Emergency or Abnormal In-Plant I Low*Power Direct Irom Low-Power I ENgineered Salety Feature I RCA Entry Safety
- 217000 Reactor Core Isolation Cooling System Syatem (RCIC) A2.03 A2,03 Ability to (a) predict (INdict the lmpacts of the th. impacts tha following on the tha REACTOR CORE ISOLATION ISOLAnON C-OOUNG COOUNG SYSTEM (RCIC); and (b) based _
baaed on those .... procedures to correct, predictions, use control, or mltigata mitigate the tha consequences of those abnormal conditions or operations: .Valve closures IMPORTANCE: RO .3,4 3.4 SRO 3.3
ES-301 Control Room/In-Plant Systems Outline Form ES*301*2 ES-301-2
- Facility: Browns Ferry NPP Exam Level (circle one): RO ~Ro-]H Control Room Systems. Systems@! (8 for RO):
4RD;i), SRO-U Date of Examination:
No.:
Operating Test No.:
July 6 - 30.
HlT 0801 HLT RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) 30, 2009 Safety System I JPM Title Type Code-Code*
Function
- b. Attemate Alternate RPV Injection - Standby Coolant S, E, S. E,EN,L, EN. L. N 2
- c. Place RCIC in Test Mode From Standby for Attemate Alternate S,A, D.
S,A. D, E.E, L 3 RPV Pressure Control
- d. Placing Standby Steam Jet Air Ejector in Operation S,E, S, E, N 4
- e. Emergency Ventilate Primary Containment D, E.L S, D. E, L 5 ff.. Parallel DIG Wfth With System 4KV SID Board at Panel 9- S, A,D S. 6 23
- g. RWM Functional Test for Startup 3-SR-3.3.2.1.2 3-SR-3.3.2.1 .2 S,L,N S, L. N 7
- h. Off-Gas Post-Treatment Radiation HI-HI-HI S, A, D, S. D,E,LE, L 9 In-Plant Systems.
Systems@ (3 for RO); (3 for SRO-I); SRO~) ; (3 or 2 for SRO-U)
- i.
Ij .
k.
Shift From 'A' Set of CRD Stabilizing Valves to 'B' Set Bypass RCIC Low Pressure Isolation 3-EOI Aj)p~ndix-16A Aooendix-16A Place B2-3 +/- 24V Neutron Monftoring Monitoring Battery D, E, D. E,L,R D. E, EN, L.
R L, R L,
1 2
A,N A, N 6 Charaer in Service to Batterv Chamer Battery Board 3
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; aU functions; all 5 SRO*U SRO-U systems must serve different safety functions; in-plant systems and functions functions ; In-plant may overlap those tested In in the control room room..
- Type Codes Criteria for RO I SRO-II SRO-l f SRO-U (A)lternate path (A)I/emale 4-6 I 4-64*6 I 2*3 2* 3 (C)onlra!
(C)ontrol room (D)irect (D)irect. from bank ~9/~8/~
- 91:! 8 /:: 4 in-plant (E)mergency or abnormal in..planl ~1/~1/~1
?1/?1/?1 (EN)gineered safety feature *- I *- I ~
? 1 (control room system)
(l )ow*Power I Shutdown (L)ow-Power ~1/!, 1 !!. 1
?1/?1/.?1 (N)ew or (M)odified (M)odffied from bank Induding including 1(A) ?2/.?2/.?1
!.21 !.2!!.1 (P)revious 2 exams ~3 J I ~ 3 I ~ 2 (randomly selected)
(R)CA .?1 1=:1 I!.
!,1 1=:1l (S)imulator
HLT 0801 Control Room/In-Plant Roomlln-Plant Systems JPM Narrative Control Room Systems:
- Modified I/ Emergency or Abnormal In-Plant I/ Low-Power I/ Simulator
- Path : must start other pump due to no flow Alternate Path:
- 2-EOI Appendix-3A, SLC Injection, Injection , Rev. 5
- 211000 Standby Liquid Control A4.08 M .OB Ability to manually operata oPerate and/or
_ndlor monitof monitor in in the controt control room room:: System Initiation:
initiation: Plant Plant..specific
..peclfle IMPORTANCE: RO ... 4.22 SRO 4.2 SR04.2
- New I/ Emergency or Abnormal In-Plant I/ Low-Power I/ ENgineered Safety Feature I/ Simulator
- 3-EOI Appendix-70 Appendix-70,, Alternate RPV Injection System Lineup Standby Coolant, Coolant, Rev. 2
- 203000 RHRlLPCI:
RHRIlPCI: Injection InjeCtion Mode (Plant (Plclnt Speclfle)
Specific) M .07 Ability to manually A4.07 operate andlor monitof operata monitor Inin the control room room;': Reactor ReactQr Water Level IMPORTANCE:
IMpORTANCE:
- Direct from bank I/ Emergency or Abnormal In-Plant I/ Low-Power I/ Simulator
- Alternate Path : RCIC Trip Throttle Valve (71-9)(71 -9) is tripped and must be reset and opened. RCIC Flow Controller fails while in service and candidate must take manual control
- ReactOrfTurbine Pressure Regulating Syatam 241000 ReactorfTurblne System M A4.02
,02 Ability to man manually
....1y operate andlor monitof operata monitor in the control room room:: Reactor Reactorpressure p....ure IMPORTANCE:
- d. Placing Standby Steam Jet Air Ejector in Operation (JPM 346 U3)
- New I/ Emergency or Abnormal In-Plant I/ Simulator
- 3-01-66, Off-Gas System, Rev. Rev. 56, Section 8.4
- 239001 Main and Reheat Steam System A2.08 Ability to (al (a) predict the Impacts impac of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) ,based based on those th proceduras to correct, control, or mitigate the
.... predictions, use procedures consequences 01 of th those
.... abnormal conditions or Qr operations: Low condenser cOlld..nser vacuum , IMPORTANCE: ,RO RO 3.6 SRO 3.6
HLT 0801 Control Room/In-Plant Roomlln-Plant Systems JPM Narrative
- e. Emergency Ventilate Primary Containment (JPM 55 U2)
- Direct from bank I/ Emergency or Abnormal In-Planl In-Plant l/ Low-Power I/ Simulator
- 2-EOI Appendix-13, Containment, Rev. 6 Appendix-13 , Emergency Venting Primary Containment,
- 223001 Primary Containment System and Auxiliaries A2.07 Ability to (a) predict prediCt impacte of the following on the PRIMARY CONTAINMENT SYSTEM AND the impacts AUXILIARIES; and (b) baaed AUXIUARlES; based on those predictio .... use procedu predictions. procedures.... to ~
correct, control. or mitigate the consequences of those abnonnal control, abnormal conditions or operations: High drywall p~ure IMPORTANCE: RO 4.2 SRO drywell pressure $RO 4,3 4.3
- f. Parallel DIG With System 4KV SID Board at Panel 9-23 (JPM 104F U2)
- Direct from bank I/ Simulator _,1/ .:~
I" 't* ~\
- Alternate Path: Once paralleled with ollsite offsite source, a voltage transient will I,} ,\, /
occur requiring candidate ca ndidate to trip the output breaker K' ,~ .,
- 0-01-82, Standby Diesel Generator System, Rev. 99, Section 8.1 Rev. 99, 8.1
- 264000 Emergency Generators (DIeseUJet)
(OieseUJet) M,04 A4.04 Ability toto' manually operate and/or monitor In andlor in the control room: Manual start.
start, loading. and stopping of emergency generator: Plant-specific IMPORTANCE: RO 3,7 emergency'generator:Plant-specific 3.7 SRO 3.7
- gg.. RWM Functional Testfor Test for Startup 3-SR-3.3.2.1 New I/ Low-Power I/ Simulator 3-SR-3.3.2.1.2 .2 (JPM 399 U3) 3-SR-3.3.2.1.2, RWM Functional Test for Startup, Rev. 3 ROd Worth Minimizer System (RWM) (Plant Specific) A2.OS 201006 Rod A2.0S Ability to (a' (a) predict the Impacte impacts of the following on the ROD WORTH MINIMIZER SYSTEM based on those predictions (RWM); and (b) baaed predictions.. ....
use procedu procedures correct, control.
.... to col1'8c1, or mitigate the consequences of those abnonnal conditions or operstio operations:
...: Out of sequence rod movement:
moveme"t: Plant-Specific Plant-5peciflc (Not BWR-6) IMPORTANCE: RO 3.1 SRO 3.5 SR03.5
- h. Off-Gas Post-Treatment Radiation HI-HI-HI (JPM 390F U3)
- Direct from bank I/ Emergency or Abnormal In-Plant I/ Low-Power I/ Simulator
- Offgas System Isolation Valve Alternate Path: Ollgas Valve,, 3-FCV-66-28 fails to close automatically requiring ca candidate ndidate to close manually
- 3-ARP-9-4C, Panel 9-4 3-XA-55-4C, Rev. 29, 29, Window 35 (Page 45 of 45) and 3-AOI-66-2, Offgas Post Treatment Radiation Hi Hi Hi, Rev.
3-AOI-66-2, Ollgas Rev. 9
- Offgas System A2.04 271000 Offgaa the Ai04 Ability to (a) predict the Impacte impacts of the following on the OFFGAS SYSTEM; and (b) baaed based on those prediction predictions... usa use procedu procedures to
.... to mitigate the consequences of those abnormal correct, control. or mltlgal8 abnonnal conditions or operations: Offgaa radi~on IMPORTANCE:
Offgas system high radiation IMPORTANCE:RO RO 3.7 SRO 4.1 4.1
HLT 0801 Roomlln-Plant Systems JPM Narrative Control Room/In-Plant
- I-'t-In*Plant In-Plant Systems
- ~ .;.
r"' ~ , I" r"'~ ~l~~-
f k~
- , '- r~
\,.J "
i
,Lw ..._ ,h-L l.
- Direct from bank I/ Emergency or Abnormal In* Plant I/ Low*
In-Plant Power /I RCA Entry Low-Power
- 2*01*85, 2-01-85, Control Rod Drive System, System, Rev.
Rev. 112, Section 6.4
- 201001 Control Rod Drive Hydraulic System A3.01 AbIlityAbility to monito< aulom8tlc monitor automatic operations of tho operatiO"" 01 the CONTROL ROD DRIVE HYDRAULIC HYDRAUUC SYSTEM Inctudlng:including: ValYe Valve operation IMPORTANCE: RO 3.0 SRO 3.0
- Direct from bank I/ Emergency or Abnormalln*Plant Abnormal In-Plant I/ Low*Power Low-Power I/ ENgineered Safety Feature I RCA Entry
- 3*EOI 3-EOI Appendix-16A, Appendix-16A, Bypassing RCIC Low RPV Pressure Isolation Interlocks, Interlocks, Rev.
Rev. 1
- 217000 Reactor Core Isolation Cooling System Syotem (RCIC)
(RCtCl A2.03 AbIlity Ability to (a) (al pradlc1 predict the Impacts impacts 01 of tholollowlng the following on tho the REACTOR CORE ISOLAnON COOLING COOUNG SYSTEM (RCIC); (b) based on those predictions, (RCICI; and (bl predictions. use procedu procedures.... to correct, control, or mitigate tho the consequences of those abnonnal conditions Or abnormal conditiO"" 0<
operations: Valve closu....
closures IMPORTANCE:
- k. Place B2*3 B2-3 + 24V Neutron Monitoring Battery Charger in Service to Battery Board 3 (JPM 30aF308F U3)
- New
- Alternate Path:
Path: When the Battery Charger is placed in service, service, voltage and amps will be out*ol*specification out-of-specification requiring candidate to open breakers and notify the Unit Supervisor
- 0*01*57D 0-01-570 , DC Electrical System, System , Rev.
Rev. 121 121,, Section 5.13
- ElectriCal Distribution Kl.02 263000 D.C. Electrical K1.02 Knowledge 01 of the phyolcal physical connections Indio<
and/or cause-elfect cause-effect relationships between
_ D.C. ELECTRICAL DISTRISUnON and thololl_ing:
DISTRIBUnON Sallery charger and battery the following: Battery _ r y IMPORTANCE:
- ~r;~~~:r: ~~~:~~ :!~!i:: '~t: ff
~ ....*~.0 : \.,. ~'~'::.,.~~ &
- Facimy:
Facility:
Tier Browns Ferry NPP Group K
1 K
2 K
3 K
4 K
5 Date of Exam RO KIA K
6 Exam::
KiA Category Points A
1 A
2 A
3 July 06 - 30, A
4 G
G
- 30. 2009 Total A2 P\2 SRO-Only Points G*
G+ Total
- 1. 11 4 3 4 3 2 4 20 4 3 7 Emergency
& 2 2 1 1 1 1 1 7 2 1 3 NfA N/A N/A NfA Abnormal Plant Tier Tie' Totals 6 4 5 4 3 5 27 6 4 10 Evolutions 11 4 2 3 2 2 3 2 2 2 2 2 28 3 2 5 2.
Pla nt Plant 2 2 1 1 1 1 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Tie' 6 3 4 3 3 4 3 3 3 3 3 38 5 3 8 Totals
- 3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 7 2 2 3 3 2 2 2 1 Notes: 1. Ensure that at least two topics from every KJA KIA category are sampled within each t.ier tier of the RO and SRO-only outlines (i.e.,(i.e. , except for one category in Tier 3 of the SRO-only outline outline., the *"TIer Tier Totals" Totals* in each KIAKiA category shall not be less than two).
0 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 +/-1 from that specified in the revisions. The final RO exam must total 75 points and the SRO-only exam table based on NRC reviSions.
must total 25 points.
- 3. Systems/evolutions within each group are identified on the associated outline; systems or facility should be deleted and justified; operationally important, evolutions that do not apply at the facitity important, site-specific systems/evolutions that are not included on the outline should be added added.. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4. Select topics from as many systems and evolutions as possible: possible; sample every system or evolution in the group before selecting a second topic for any system or evolution .
In
- 5. Absent a plant-specific priority, priority. only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
77."" The generic (G) t<JAs KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system . Refer to Section D.1.b of ES-401 topiCS for the applicable KlAs.
B.
- 6. On the following pages, enter the KIA numbers, numbers. a brief description of each topiC, topic, the topics' ratIngs (IR) for the applicable license level, and the point totals (#)
importance ratings (# ) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 33,, select topics from Section 2 of the KIA catalog, and enter the KIA t<JA numbers, descnptions, IRs, and point totals (#
descriptions, (#)) on Form ES-401-3.
ES-401*3. limit Limit SRO selections to KlAs t<JAs that are 55.43..
linked to 10 CFR 55.43 IC.c.':/ /. a
:=-~
~~
." II! 20
() ~----------------------------~ F-onn Form--=ES ~0 (1
ES~o1
.1'--
-40~l~ .l~----
-1 ES-401 ES-401 BWR Examination Outline form ES-401-1 Fonn ES-401 -1 Emergency and Abnormal Abnonnal Plant evolutions 1{Group 1 (RO I SRO)
Evolutions - Tier 1/Group ElAPE # I/ Name Name'/ Safety Function Functio n K
K 1
K K
2 K
K 3
A 1
A 2
aG KJA Topic(s)
KIA I.
IR 295001 Partial or Complete Loss of Forced 1 AA1.02 AA1 .02 (10CFR 55.41 .7)
Core Flow Circulation I{ 1 & 4 Ability Abi lity to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE COR E FLOW CIRCULATION : 3.3 1
- RPS 295003 Partial or Complete lLoss of AC 16 oss 01 /6 1 1 AK1.03 (10CFR 55 .41 .8) 55.41 Knowledge of the operational implications of the following fol1owing concepts as they apply to PARTIAL OR COMPLETE COM PLETE LOSS OF AC POWER:
2.9 2
- Under voltage I/ degraded voltage effects on electrical loads G2.4.50 (10CFR 55.43.5 *- SRO Only)
Ability to verify system alarm setpoints and operate controls identified in the 4.0 76 alarm response manual.
295004 Partial or Total Loss of DC Pwr 16/6 1 AK3.02 AK3 .02 (10CFR 55.455.411.5)
.5)
Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF DC POWER: POWER: 2.9 3
- Ground isolation I/ fault determination 295005 Main Turbine Generator Trip 13 I3 11 . G2.4.21 G2.4.21 (10CFR 55.41 .7)
Knowledge of the parameters and logic used to assess the status of safety functions, such 'aass reactivity control, control, core cooling and heat removal, removal , reactor 4.0 4 coolant system integrity, integrity , containment conditions, radioactivity release control,control ,
etc .
etc, 295006 SCRAM I/11 1 . AK2.02 (10CFR 55.41 .7) 55.41.7)
Knowledge of the interrelations between SCRAM and the following following:: 3.8 5
- Reactor water level control system SRO only only K/
K/ As shown in Italics italics 4/9/2009 11 :06: 18 AM 4/ 9/2009 .- 11:06:18 Page 2
-ES-40 ES-401
- tt ------------------------2 2.tt Fonn E ESt-.1----
sl-.1---
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO 1 SRO)
ElAPE # I Name I Safety Function K K K A A G KIA Topic(s) IR #
1 2 3 1 2 295016 Control Room Abandonment 17 1 G2.4.30 (10CFR 55.41.10)
Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the 2.7 6 transmission system operator.
1 G2.4.3 (10CFR 55.43.5* SRO Only) 3.9 77 Ability to identify post-accident instrumentation.
295018 Partial or Total Loss of CCW 18 1 1 AA1.02 (10CFR 55.41.7)
Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: 3.3 7
- System loads AA2.01 (10CFR 55.43.5* SRO Only)
Ability to determine and/or interpret the following as they apply to PARTIAL OR 3.4 78
. COMPLETE LOSS OF COMPONENT COOLING WATER:
- Component temperatures 295019 Partial or Total Loss of Ins!. Air 1 8 1 AK2.18 (10CFR 55.41.7)
Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: 3.5 8
- ADS: Plant-Specific 295021 Loss of Shutdown Cooling 14 1 G2.2.4 (1 OCFR 55.41.7)
(multi-unit license) Ability to explain the variations in control board/control room 3.6 9 layouts, systems, instrumentation, and procedural actions between units at a facility.
SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 3
~ES_401 E~S~4~071~<:>~ 0 ~--------------------------------~22 '"J-'----------------.:F~O;;rm~E:s: Form o -
o~ :! -I,-------
S_401-1 ES40!1'1" ES-401 Examrnatlon Outline BWR Examination ES--401 * '
Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1IGfCUp 11 (RO IRQ I SRO)
ElAPE # /I Name I Safety Function ElAPE' ,
K K
1 K
K 2
K K
3 A
1 I
A 2
G KIA Toplc(a)
Topic(s) I.
IR 1#
295023 Refueling Ace AI:;c 18 I8 1 1 AA1.04 (10CFR 55.41 .7)
Ability to operate andlor and/or monitor the following as they apply to REFUELING ACCIDENTS: 3.4 10
- Radiation monitoring equipment (fOCFR 55.43.5 - SRO Only)
AA2.0f (10CFR AA2.01 and/or interpret the following as they apply to REFUELING Ability to determine andlor 4.0 79 I ACCIDENTS:
- Area radiation levels I
Drywell Pressure 15 295024 High Drywell I5 1 EA2.03 (10CFR 55.41 .10)
Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE: 3.8 3.B 11
- Suppression pool level 295025 High Hrgh Reactor Pressure 13I3 1 1 EK2.04 EK2 .04 (10CFR 55.41 .7)
Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: 3.9 12
- ARJlRPT/ATWS: Plant-Specific ARIfRPTIA1WS: Planl-Specific EA2.01 EA2.0f (10CFR (fDCFR 55.43.5 - SRO Only) fol/owing as Ability to determine and/or interpret the foflowing 8S they apply to HIGH 4.3 80 REACTOR PRESSURE:
- Reactor pressure Supplesslon Pool High Water 295026 Suppression 1 Dl:talls "R~
EK3.02 (10CFR 55.41 .5) - 'tleirllt , Recol"O .A Rej('r:l~d ret 01 ReJ&!Pd K'AKJA.... *
'5 Temp. 15 Temp, Knowledge of the reasons for the following following responses responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: 3.9 13
- Suppression pool cooling 2960~
~ 1oI1g" GaAleiAmeA' Ulitl 'fepi,' FMIIi.. ,Iii CelI.IMlIAt :fempe,..,. I - - - - - - NIA for BFN - KIA for Mark N/A Mail< III Containments ONLY ONL Y --- ----
SRO only KjAsK/ As shown in italics itJIlics 4/9/2009 - 11 :06: 18 AM Page 4
--e
--e-----------e-----------e--
ES-401 2 e e--
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)
ElAPE # I Name I Safety Function K K K A A G KIA Topic(s) IR #
1 2 3 1 2 295028 High Drywell Temperature / 5 1 1 EK1.01 (10CFR 55.41.8)
Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: 3.5 14
- Reactor water level measurement EA2.01 (10CFR 55.43.5 .. SRO Only) **Details in Record of Rejected KlAs**
Ability to determine and/or interpret the fol/owing as they apply to HIGH 4.1 81 DRYWELL TEMPERA TURE:
- Drywel/ temperature 295030 Low Suppression Pool Wtr Lvi / 5 1 EK3.03 (10CFR 55.41.5)
Knowledge of the reasons for the following responses as they apply to LOW SUPPRESSION POOL WATER LEVEL: 3.6 15
- RCIC operation: Plant-Specific 295031 Reactor Low Water Level / 2 1 EA2.03 (10CFR 55.41.10)
Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: 4.2 16
- Reactor pressure 295037 SCRAM Condition Present and 1 G2.2.12 (10CFR 55.41.10)
Power Above APRM Downscale or Unknown / 1 Knowledge of surveillance procedures. 3.7 17 295038 High Off-site Release Rate / 9 1 ...
EK1.03 (10CFR 55.41.10) **Details in Record of Rejected KlAs**
Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE:
2.8 18
- Meteorological ~ffegs QD MeteorolQgical effects ~ff-~ite release on off-site release SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 5
-=-=-=,---e ES-401 ES-401 0 '---------------------=e 20 -------------=------=""'O 2 ( l"--c--
ES-401-1 Form ES-401 *1 ES~Ol ES-401 BWR Examination Examlnalion Outline OuUfne ES-40H Form ES-401 *1 I Emergency and Abnormal Abnorma l Plant Evolutions Evolulions - Tter lIGroup 1 (RO I SRO)
Tier 1/Group ElAPE .# 1I Name I Safety Function EJAPE K
1 K
2 K
3 A
1
- A 2
G KIA To Toplc(s) pl c(s) I.
IR 600000 Plant Fire Sile J FIIS On Srte / a8 1 AK3.04 (10CFR 55.41 .5) I Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: 2.8 19 I
- Actions contained in the abnormal procedure for plant fire on sile site 700000 Generator Voltage and Electric Grid 100000 1 AK1 .01 (10CFR 55.41.5) 1 AK1.01 55.41 .5) I Disturbances 16 Knowledge of the operational implications of the following concepts as they to GENERATOR VOLTAGE apply 10 VOLTAGE AND ELECTRIC GRID DISTURBANCES: 3.3 20 I
- Definition of terms: volts.
volts, watts, amps, VARs, power factor GZ.4.31 (10CFR 55.43.5 *- SRO Only)
G2.4.31 (10CFR 4.1 4.1 82 I Knowledge of annunciator alarms, indications,. 0" or response procedures.
KJA KIA Category Totals; (RO)
Tolals: (ROJ 4 3 4 3 2 4 Gmup Group Point Total' Total: (RO) 20 C8tegory T0/81s" KIA CBlegory (SRO))
Totals: (SRO 4 3 Group Point Tot81 TOfel:: (SRO) 7 SRO only Kj K/As shown in italics 4/ 9/ 2009*11:06:
4/9/2009 18 AM
- 11:06:18 Page 6
~~"~------------------~3tt~----------------~-="~~---
'.~
ES-401 o
3~ -
o~
ES~ -1 Form ES-401-1 Fonn ES-401 BWR Examination OUUine Outline Form Fonn ES-401 ES-401-1-1 Emergency 800and Abnormal Evolutions - Tter Abnonnal Plant Evolution, IlGtoup 2 (RO II SRO)
Tier llGroup ElAPE ./ # I Name I Safety Functlon Function K
1 K
2 K
l3 A
1 A
2 G KIA Toplc(s)
Topic(s) I.
IR
_003 8' MilAGIAII.A bOIl If Main 39iOO3 LoMe COAd'RlleF ~o # 3
..t 1j.ao#3 - - -- - - - NOT RAN DOMLY SELECTED RANDOMLY -- ------
391iOO~ HII*'
20i001 Pfeil. life J 3
~ *** , PAM'IIM!
High Re8a&oF a - - - -- - - NOT RAN DOMLY SELECTED-RANDOMLY SELECTED--- - --- --
39&008 a8iOOl Nilh High R wat.f bawl'
- oter tNellf Re8a&aF b8'J8I $ a 3 - - - - - - NOT RANDOMLY RANDOML Y SELECTED - ------.- --
295009 Low Reador Reactor Water Waler LevellLevel / 2 1 AK2.04 (10CFR 55.41 .7)
Knowledge of the interrelations between lOW LOW REACTOR WATER lEVEL LEVEL and the following:
following :
2.6 21 21
- Reactor water cleanup Drywell Pressure 15 295010 High Dryweli 1 G2.4.49 (10CFR 55.41 .10)
Ability to perform without reference to procedures those actions that require 4.6 22 immediate operation of system components and controls.
aQi011 Hill! Call"'I 395011 High Contain", ......* ,,'
"1 TaM" #,Ii
- felllil J - - - - - - N/A for BFN - t<JAKJA for Marl<
Mark III Containments ONLY ONL Y --- -----
295012 High Drywe" Drywall Temperature /I S 5 1 1 AK1.01 (10CFR 55.41 .9)
Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: 3.3 23
- Pressure I temperature relationship G2.4.34 (fOCFR (10CFR 55.43.5 - SRO Only) 4.1 4.1 83 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
Suppression Pool Temp. I15 295013 High Suppr1!ssion 5 1 AA2.02 (fO (10 CFR 55.43.5 - SRO Only)
Ability to determine and/Or and/or interpret the (0110 wing as they apply to HIGH following SUPPRESSION POOL TEMPERA TEMPERATURE: TURE:
3.5 84
- Localized heating / stratification ae601 391CU 4
~ IAaM_At R.aa&~ A4'ill,,,!
l"IMlten' R'I8I~o"ity Addition! 1
- - - -- - - NOT RANDOMLY RANDOML Y SELECTED --- -- -
SRO only K/ K/As shown in italics 4/9/2009 4/ 9/2009 - 11 :06:18 :06: 18 AM Page 7
~*----------~
'------ - - -------"0.3-0----------~O~ 3 0 0-Form ES-401-1 ES-.401 ES-401 BWR Examination OUillne examination Ouliine ES-401 -,
Form ES-401-1 Emergency and Abnormal Plant Evolutions - TIer Tier 1/Group 2 (RO (RD /I SRO)
ElAPE ",# I Name I Safety Function K 1
K 2
K 3
A 1
A 2
G KIA Topic(.)
Topic(s) I.
IR #I 0!95OHi
- aNOli IAeMlpl.,. S~RAM ~ ~I 1"$MIple" StRMA! - - - - - - NOT RANDOML RANDOMLY Y SELECTED~
SELECTED ------ ----
295017 High Off-s~e Release Hi9h Off-site Rele ase Rate I19 9 1 AK3 AK3.03.03 (10CFR 55.41 .5)
Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: 3.3 24
- Implementation of the site emergency plan
Moao IA,\h.fteAI lIel.tl8A I,t 5I & 7"1-GeR', l.alatiaA - - - -- - -- NOT RANDOMLY SELECTED .. - -- ----
295022 loss Loss of CRD Pumps 11 I1 1 AA2.03 (10CFR 55.41 .10)
Ability to determine and/or interpret the following as they apply to lOSS LOSS OF CRD PUMPS: 3.1 25
- CRD mechanism temperatures 295029 High Suppression Pool Pool WI, Lvl 15 Wtf Lvi i5 1 EA1 EA1.04.D4 (10CFR 55.41 .7)
Abitity to operate and/or Ability andlor monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL: 3.4 26
- Rete: Plant-Specific RCIC: Plant*Specific
~iOa:a
- !85030!
AM.
Hitll S'IiIU.~ CSA,-iAAMlA' Wig'" SleaA"a!}'
TM'Ip.RlIu,. ~I ,5 ARIa +MlpeF8'"RI C8flWlfWMAt
- - -- -- - - RANDOMLY NOT RANDOML Y SELECTED 295033 High High Secondary Containment 1 EA2.03 EA 2.03 (10(1 0 CFR 55.43.5 - SRO Only)
Levels IJ 9 Area Radiation LevelS determine and/or interpret the following as Ability to detennine as they apply to HIGH SECONDARY CONTAINMENT AREA RADIA T/ON TION LEVELS:
4.2 85
- Cause of high area radiation 2950"34 S,GII".a')'
28IOa4 CeIIl.I""'IAI SeeeA"aFy COAlaiARIeAt V."IIIIIiGfl Hllh VlAlliMleR RlI1II.&ieA ~ "Q wig'" RHlalieA - - - - - - NOT RANDOMLY SELECTED "
- lQiOal SIGOA"IIY 0!9iQ35 s.U"..')'GIIA gMfilAlAllal Pi'll' gllll'lMlal PAIl..."1'1
......"1 Hit'"
CeA'-iARIeRt
,. "! i Willi
- - - - - - NOT RANDOMLY SELECTED SRO only K/ K/ As shown in italics 4/9/2009 - 11 11:06:18
- 06 :18 AM Page 8
,0
~E~S-4~07 ES-401 1~ * --------------------------------~ 3 3
- rJ ~--------------------------~ F-Onn
--~ES~0p .----
{)
40~
Form ES-401-1 1-71-------
ES.,.Ol ES-401 Elamlnatlon OUIline BWR Examlnallon Ollliine ES~Ol* '
Form ES-401-1 Emergency and Abnormal Plant Evolutions Eyolutions - Tier (RO I SRO)
TlElf lIGroup 2'<RO ElAPE # I Name I Safety Function E1APE'/
K K
1 ,
K 2
K 3
A 1 ,*
A 2
G Toplc{s)
KIA Topic(s) IR II 295036 Secondary Containment High 1 EK1.01 EK1.01 (10CFR (10CFR 55.41 .10) evel J 5 Sump/Area Water lLevell Knowledge of the operational implications of the following concepts as they they apply 10 to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: LEVEL:
2.9 27
- Radiation releases HII~ I;:n.Q:
iOOOOO High iOOOOQ ~fll'R GlHto, Gml HyaFeg8R GaRB. ~ i - - - - - - NOT RANDOMLY SELECTED - --..
-- -~
KIA Category Totals:
KiA Totals: (RO) 2 1 1 1 1 1 PoInITola];
Group Point Tota.l: (RO) 7 KIA Cetsgol)' TOials: (SRO)
Category Totals: 2 1 Group Point Toral: (SRO)
PoInt Total: 3 SRO only K/ K/ As shown in italicsItalics 4/9/2009 - 11:06:18 11 :06: 18 AM Page 9
~~"~----------------~
ES-401 ES-401 @ 44"----------------~~
0 FonnESQ-Fonn ()~~--
"1--1----
ES-401-1 ES-401 OutUne BWR Examination Outline Form ES-4Dl-1 ES-401 * '
Plant SySlems Systems - Tier TIer 2/Group 21Group 1, (RO I SRO)
System" System # II Name K
1 K
2 K
3 K
4 K
5 K
6 A
A 1
A A
2 A
A 3
A A
4 G KIA Topic(s)
Topic{s) I.
IR 203000 RHRlLPCI: Injection 203000 RHRll PCI: I"Jedion 1 K5.02 (10CFR 55.41 .5) '*Details In Record
' "Details In Reco rd of Rejected K/As**
K/As "
Mode Knowledge of the operational implications of the following concepts as they apply to RHR I/ LPCI : INJECTION MODE (PLANT SPECIFIC): SPECIFIC) :
3.5 28
- Core cooling methods 205000 Shutdown Cooling 1 1 K2.02 (10CFR (1 OCFR 55.41 .7)
Knowledge of electrical power supplies to the following following:: 2.5 29
- Motor operated valves u
A4.03 (10CFR 55.41.7)55.41 .7) **--Detail!; In Record of Rejected K/As **
Detai ls in Ability to manually operate andlor and/or monitor in the control room:
room: 3.6 30
- SOC I/ RHR discharge valves 206000 HPCI 2Q6000 1 1 K4.03 (10CFR 55.41 .7) ***Oetails Rejecte(i KJAs"
- Oetails in Record of Rejected K/AsH Knowledge of HIGH PRESSURE COOLANT INJECTION (HPCI)
SYSTEM design feature(s) andlor and/or interlocks which provide for the 4.2 31 following::
following
- Resetting turbine trips:
trips: BWR-2,3,4 A2.16 (10CFR 55.43.5 - SRO Only)
AbiUty to (a) predict the Impacts Ability impacts of the following on the HIGH PRESSURE COOLANT INJECT/ON INJECTION (HPCI) SYSTEM; and (b) based 4.1 86 on those predictions, predictions, use procedures to correct. control, or mitigate the correct, control, consequences of of those abnormal conditions or operations:
- High drywell pressure: BWR-2,3,4 BWR-2,3,4 (1iM.".,,9Y.
- aQ~9QQ leelatleR ag7.000
~
I*
- II",R (IiiM8rs8RG)')
GeRdeRS8' - - --
- -- - - - - - - - - - NJA for N/A /or BFN - No Isolation Condenser{s)
Condenser(6) ---
SRO only K/As shown in Italics italics 4/ 9/ 2009 - 11:06:18 AM 4/9/2009 Page 10
==~4t~----------------~44t----------------~~
O ...,
Form ES-401 ~~--
~--
01-1
- 1 ES-401 ES401 Examlnallon Outline BWR Examination OutlIne ES-40H Form ES-401 *1 Plant Systems - Tier TlElr 21Group 2JGroup 11 (RO I SRO)
K System #./I Name N.me K
1 K
2 K
3 K
4 5 K
6 A
1 A
2 A
3 A
4 G KIA Topic(s)
Toplc!s) I.
IR 209001 LPCS 1 K1.12 (10CFR 55.41 .5)
KU2 Knowledge of the physical connections and/or cause-effect relationships bet'Neen between the LOW PRESSURE CORE SPRAY (LPCS) (lPCS) 2.9 32 SYSTEM and the following:
- ECCS room coolers 208002HPC&
- i!09QQ2104PGS
- - - - - - - - - - -- NIA N/A for BFN - No HPCS Sy.tem-* System -.----- ---
211000SLC 211000 SLC 1 ' A4.08 (10CFR 55.41 .7)
Ability to manually operate and/or monitor in the controlcontrol room:
room : 4.2 33 212000 RPS
- System initiation:
initiation: Plant-Specific 1 1 Kl .11 (10CFR 55.41.7)
Kl.11 55.41 .7)
Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM (RPS) will have on the following :: 3.0 34
- Recirculation system A2.20 (10CFR 55.43.5 -* SRO Only)
Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM (RPS); and (b) based on those predictions, predictions, use procedures to correct, correct, control, or mitigate the consequences of 4.2 87 those abnormal conditions or operations:
2150031RM
- Full system activation (full*SCRAM)
(full-SCRAM) 1 K4.04 (10CFR 55.41 .7)
Knowledge of INTERMEDIATE RANGE MO NITOR (IRM) SYSTEM MONITOR design feature(s) feature(s) and/or inter10cks interlocks which provide for the following :: 2.9 35
- Varying system sensitivity levels using range switches SRO only K/As shown in italics 4/9/2009*- 11 4/9/2009 :06: 18 AM 11:06: Page 11II
--e------------e ES-401 ES-401
- 4 4 . Esl-.1----
Form E SJ----
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO I SRO)
System # I Name K K K K K K A A A A G KIA Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 215004 Source Range Monitor 1 A3.01 (10CFR 55.41.7)
Ability to monitor automatic operations of the SOURCE RANGE MONITOR (SRM) SYSTEM including: 3.2 36
- Meters and recorders 215005 APRM I LPRM A2.07 (10CFR 55.41.5) 1 Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR / LOCAL POWER RANGE MONITOR
. (APRM / LPRM) SYSTEM; and (b) based on those predictions, use 3.2 37 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Recirculation flow channels flow mismatch SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 12
_--,~I~
-ES-40-1~~I~~----------------------4tt ES-401 4
- Form Form A __
EsI-.1----
ES~-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (RO I SRO)
System # I Name K K K K K K A A A A 0 KIA Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 217000 RCIC 2 1 K3.02 (1 OCFR 55.41.7)
Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM will have on the 3.6 38 following:
- Reactor vessel pressure K3.04 (10CFR 55.41.7) (Unit Differences) I Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM will have on the 3.6 39 following:
- Adequate core cooling G2.4.41 (10CFR 55.43.5. SRO Only)
Knowledge of the emergency action level thresholds and 4.6 88 classifications.
218000 ADS 1 K1.02 (10CFR 55.41.5)
Knowledge of the physical connections and/or cause-effect relationships between the AUTOMATIC DEPRESSURIZATION 4.0 40 SYSTEM (ADS) and the following:
L _ - - _ ... - - - - - - - - L.... *. ~~ -_. -_ ... ~--
Low pressure core spray: Plant-Specific
- -- _ .... _ .... _ .... _ ... - - _ ... _ ..... - _ ..... _ ...... - _ ..... _ .... _ . _ .. _ ... - _ .... - L -... _ _
SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 13
--~il~~-------------------41t
_---"11' ES-401
- ,1-.1- -
Form ESt-.1----
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (RO / SRO)
K K K K K K A A A A G KIA Topic(s) IR #
System # I Name 1 2 3 4 5 6 1 2 3 4 223002 PCIS/Nuclear Steam Supply Shutoff 2 K1.03 (10CFR 55.41.5)
Knowledge of the physical connections and/or cause-effect relationships between the PRIMARY CONTAINMENT ISOLATION 3.0 41 SYSTEM (PCIS) / NUCLEAR STEAM SUPPLY SHUT-OFF and the following:
- Plant ventilation K1.13 (10CFR 55.41.7)
Knowledge of the physical connections and/or cause-effect relationships between the PRIMARY CONTAINMENT ISOLATION 2.7 42 SYSTEM (PC IS) / NUCLEAR STEAM SUPPLY SHUT-OFF and the following:
239002 SRVs
- Traversing in-core probe system 1 1 A1.01 (10CFR 55.41.5)
Ability to predict and/or monitor changes in parameters associated I with operating the RELIEF / SAFETY VALVES (SRVs) controls 3.3 43 i
including:
I Tail pipe temperature I
G2.4.45 (10CFR 55.43.5
- SRO Only) 4.3 89 Ability to prioritize and interpret the significance of each annunciator or alarm.
259002 Reactor Water Level 1 G2.4.45 (10CFR 55.41.10)
Control Ability to prioritize and interpret the significance of each annunciator or 4.1 44
- _L ... c.~ -- - "_ *... -
alarm. _ ... _ ..... --- -_ ... - _ ... _._ _
.... .... - _ .... - - ..... ~ ... -
SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 14
-ES-4-0-1~1~----------------------------4tt ES-401 I 4. Form ESt-.1----
ESt-.1---
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (RO / SRO)
System # / Name K K K K K K A A A A G KIA Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 261000 SGTS 1 1 K6.05 (10CFR 55.41.7) **Details in Record of Rejected K/As**
Knowledge of the effect that a loss or malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM (SGTS): 3.1 45
- Reactor protection system: Plant-Specific A2.11 (10CFR 55.43.5* SRO Only)
Ability to (a) predict the impacts of the following on the STANDBY GAS TREA TMENT SYSTEM (SGTS); and (b) based on those predictions, use procedures to correct, control, or mitigate the 3.3 90 consequences of those abnormal conditions or operations:
262001 AC Electrical
- High containment pressure 1 1 A3.04 (10CFR 55.41.7) **Details in Record of Rejected K/As*'
Distribution Ability to monitor automatic operations of the AC. ELECTRICAL DISTRIBUTION SYSTEM including: 3.4 46 I
Load sequencing I
G2.2.39 (10CFR 55.41.10)
Knowledge of less than or equal to one hour Technical Specification 3.9 47 action statements for systems.
SRO only KjAs shown in italics 4/9/2009 - 11:06:18 AM Page 15
~E~S~4701o--"'~------------------------------~
ES-401 0 4"'----------------------------~F~
40 o-nn-=E~
Fonn SQ~~;II'1_-1----
ES 1-- ~1------
ES-4011 ES-40 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (RO I SRO)
System # I Name K
1 K
2 K
3 K
4 K
5 K
6 A
1
- A 2
A 3
A 4
G KIA Topic(s) IR I
I (AC/DC) 262002 UPS (ACfDC) 2 KG.02 (10CFR K6.02 (1 OCFR 55.41 55.41.7)
.7)
Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (UPS) 2.8 48 (AC. I D.C.):
(A.C.I D.C.):
- + D.C. electrical power I
KG.03 ((110CFR K6.03 OCFR 55.41 55.41.7)
.7)
Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (UPS) 2.7 49 (AC. I D.C.):
(A.C.I D.C.) :
- + Static inverter 263000 DC Electrical A2.01 (10CFR 55.41 .5)
Distribution 1 55.41.5)
Ability to (a) predict the impacts afthe of the following on the D.C.
D.C.
ELECTRICAL DISTRIBUTION SYSTEM SYSTEM;; and (b) based on thoseIhose predictions, predictions, use procedures to correct, control, or mitigate the 2.8 50 consequences of those abnormal conditions or operations:
operations:
+ Grounds 264000 EDGs 1 K5.05 (10CFR (tOCFR 55.41 .5)
Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL I JET): 3.4 51
- + Paralleling AC AC.. power sources 300000 Instru ment Air Instrument K2.01 (10CFR 55.41 .7) 1 Knowledge of electrical power supplies to the following:
following: 2.8 52
- compress~
Instrument air compressor
_+_'nst!ument SRO only K/As shown in italics 11 :06: 18 AM 4/9/2009 - 11:06:18 Page 16
- -0
-=
E-=-
S-4
--=
ES-4010 1: --
e 4 0 Form o~-
ESQ~ 1--1----
Form ES-401-1 -:
ES ....01 ES-401 Examination Outline BWR Examlnatlon Form ES-4Q1*1 ES-401-1 Plant Systems - rter Tier 21Groop (RQ I SRO) 2lGroup 1 (RO 4 ,
5 6 11
- KKIKIKIKIK K K K K IKIA K A IAIAIAIG A A G System "# I Name System Name 400000 Component Cooling 1 22 33 4
- 2 2 3 3 4
- Topic(s)
KIA Toplc(s) IIR
- #I 1 A1.01 (10CFR 55.41 .5)
Water Ability to predict and/or monitor changes in parameters associated with oper.Hng operating the COMPONENT COOLING WATER SYSTEM 2.8 53 controls including:
- CCW flow rate Point Totals.
KIA Category POint Totals:
(RO) 4412 2 131212 3 2 2 133 1212121212 2 2 2 2 2 TOIal (RO)
Group Point Tolal: (RO ) 26 KIA Category POint Totals.
category Pomt Totals:
Group Point Total: 5 SRO only K/AsK/ As shown in italics 11 :06: 18 AM 4/9/2009 - 11:06:18 Page 17
E=-S-4 ES-401-:C::c O1 :-,e o 5 0 ESQ Form ES-401-1 Form 0,,------ ~1--1:-----
ES~01 ES""Ol Examination Outline BWR Ekamlnalion Form ES-401*' ES-401*1 Plant Systems - Tier 2JGroup 2 (RO I SRO)
System til Systom
- J Name K
1 K
2 K
3 K
4 K
5 K
6 A
A 1
A 2
A A
3 ..*
A G KIA Toplc(s) I.
IR 201001 eRO CRD Hydraulic 1 K6.04 (10CFR (1 OCFR 55.41 .7)
Knowledge of the effect that a tossloss or malfunction of the following will have on the CONTROL ROD DRIVE HYDRAULIC SYSTEM:
3.6 54
- RPS 2O~OO~ RMes
- 10100.2 RM~S
- - - -- - - - - - - - RANDOMLY SELECTE NOT RANDOMLY SELECTED D ---
~01008 COM,eI 3Q100a MaallaAlsm MeGh.AM
~eAIF81 RM Rea I"iBRa 0fW, gA'IfI
- - - - - - - - - - - NOT RANDOMLY SELECTED ----
____c.
~9~OO4 RGes OlQ1QQ4 RS~S
- - - - - - - - - - - N/A for BFN - BWR 4/5 ONLY ONL Y --- --
~9~OO6 ACIS 30101;1& R~IS - - - - - - - - - - - fOr BFN - BWR 6 ONLY N/A for --
,~9~00fi
- iQ1QQi RWM - - - - - - - - - - - NOT RANDOMLY SELECTED SELECTED- ---.-- ---
202001 202001 Recirculation 1 A2.10 A (10CFR 55.43.5 - SRO Only) 2.10 (10CFR I
Ability to (a) predict the impacts of the following on the I RECIRCULA TlON SYSTEM; and (b) based on those predictions, RECIRCULATION USB use procedures to correct, control, or mitigate the consequences of 3.9 91 those abnormal conditions or operations:
- seal failure Recirculation pump s8al agaoga
~gO!oo~ R Flew e8"'fOI
- ewlM!8f1 ~IQI\tJI Reelf8111atl8R ~eRIFeI
- - - - - - - - - - - NOT RANDOMLY SELECTED---
SELECTED -
2Q400QRWCU 204000 RWGY - - - - -- - - - - -- -- RANDOMLY SELECTED NOT RANDOMLY -- ----
~~4000 RPaS
- 11.1>>0 RPIS
- - - - -- -- - - - - - NQT NOT RANDOMLY SELECTED . -.---- .--- --- -
215001 Traversing In-core In*core Probe 1 A3.03 A (1 OCFR 55.41.7) 3.03 (10CFR 55.41 .7)
Ability to monitor automatic operations of the TRAVERSING IN-CORE PROBE including:
including:
2.5 2 .5 55
- Valve operation:
operation: Not-BWR1 Not-8WR1
- - L-____ _ .. ___ _ L .. _ _ __ _
SRO only K/ K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 18
~
~E~S4~Ol ES-401 O
~4It--------------------------------~ n 5 41t 5 Form o O~-
Form ES40"'
ES401-1 1""":-1,---------
ES-401 ES-401 BWR Examination Outline Fcmn E$-401 Form ES-401 -1 Plant Systems - Tier 2/Group 22 IRO (RO I SRO)
A A A A G System .# ,I Name K 1
K 2
K 3
K 4
K 5
K 6 1 2 A
3 A
4 G
KiA Toplc(s, KIA Topic(s) IR I.
21 5002 RBM 215002 1 1 K1.02 Kl .02 (10CFR 55.41 .6)
Knowledge of the physical connections andfor cause--effect cause-effect relationships between ROO ROD BLOCK MONITOR SYSTEM and the 3.2 56 following following::
- BWR-3,4,5 LPRM : BWR-3.4 .5 (10CFR 55.43.5 - SRO Only)
A2.05 (fOCFR A2.0S Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use 3.3 92 procedures to correct, control, or mitigate the consequences of of those abnormal conditions or operations:
- RBM high or inoperable: BWR*3,4.5 BWR-3,4,5
~11OOO
- UiOOO N\IIoI NlialaaF
- r 8eRaF IAII.
IIdlr 11\111. -- - - - - - - - - - - RANDOML Y SELECTED NOT RANDOMLY -------- - .- -
2219000 19000 RHRlLPCI: Torus/Pool RHRIlPC I: TorusIPool 1 K2.02 (10CFR 55.41 .7)
Cootrng Cooling Mode Knowledge of electrical power supplies to the following: 3.1 57
- Pumps
~300~ P a2:1OG1 Pfima~ G~; IAeI
.....I)' CJ:Mr lAd AIIII>
AWII. NOT RANDOMLY SELECTED -
- aMOO1 RHRJ'..P(;l aaiQOl Made RWRJl-PGI:i Cm:F GlMl' S,MY SpFay
- - - - - - - -- - - - RAN DOMLY SELECTED NOT RANDOMLY --- --
RWRP... PGI: ~.01 2i10QQ0 RHMPCI; ;efUe.tPeel 230000
- ,..
- t Mgil Spray Meda - - - - - - - - - - - NOT RANDOMLY SELECTED --.-- ----
Cooling/Cleanup 233000 Fuel Pool Coohrlg/Cleanup 1 G2.4.3S (10CFR 55.43.5 G2.4.35 (fOCFR 55.43.5*- SRO Only)
Knowledge of local auxifiary auxiliary operator tasks during an emergency 4.0 93 and the resultant operational effects.
effects.
234000 ~w" 3a4000 I"wal ""AiNA.
WIAdllA9 ",w,"'IAI iqwlpmaAI - - - - - - - - -- -- -- NOT RANDOMLY SELECTED ------ ---- -
a3900~ MilA a31KlCn ~1aIA 1M a.,.,.,.
~"..I steam lAd Rahaal
-- - - - - - - - - - - NOT RANDOMLY SELECTED -' -:-- --
SRO only Kj K/As shown in italics 4/9/2009 - 11:06:18 AM Page 19
~
E=S~ 47 ES-401 01~ *0 - - - - - --*
~------------------------------~ 5 5
~F~ o-nn~E=0 S~4~01~-7 Form ES-401-1 1 -------
ES--401 ES.401 BWR Examination Outline Form ES-401-1 ES.401-1 Ptant Systems - Tier Plant (RO'I SRO) 2JGroup 2 (RO TIer 21Group System System" # JI Name K 1
K 2
K 3
K K 4 5 K
6 ***
- A 1
A 2
A 3
A 4
G KIA Topic,s)
Topic(s) I.
IR 239003 MSIV Leakage ContrOl Control 1 K4.02 (10CFR 55.41 .7) ,7)
Knowledge of MSIV LEAKAGE CONTROL SYSTEM design featu re(s) andlor feature(s) andler interlocks which provide for the following: 3.0 58
- Performance Perfonnance of intended safety function following any active component failure: BWR-4,5,6(P-Spec)
BWR4.5,6(P-Spec) any single 241000 ReactorfTurbine ReactorlTurbine Pressure 1 A1.01 (10CFR 55.41 .5) "Oet,ul" A1.01 **Detalls in Kel.~rcl In Rf- :Old of
')1 Re K!!-d
- If:JE' KtAs"
- ted 1( '45 Regulator andlor monitor changes In Ability to predict and/or in parameters associated operating the REACTOR I/ TURBINE PRESSU with operaling wilh PRESSURE RE 3.9 59 REGULATING SYSTEM controls including:
- Reactor pressure Main Turbine Gen. I AUK, 245000 MaIn Aux. 1 K5.07 (10CFR 55.41 .5)
Knowledge of the operational operational implications implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY AUXI LIARY 2.6 60 I I
SYSTEMS:
- Generator operations and limitations 256OOC1 ReaClor 256000 Reactor Condensate 1 G2.1.30 (10CFR 55.41 .7) 4.4 61 Ability toto locale locate and operate components, including local controls. controls, 2&.900~
~'&QO~ ReaeteF fOJ::88"wetef Rullle, ........' - - -- - -
- - -- - - - -- NOT RANOOML RANDOMLY Y SELECTED --- -- --.--
iM.OOOR 01811000 Reiweate
....... - - - - - - - - - - - NOT RANOOML RANDOMLY Y SELECTED --- -----.-
Offgas 2710000ffgas 271000 1 A4.06 (10CFR 55.4 A4.0S 55.411.7)
.7)
Ability toto manually operate and/or andlor monitor in in the control room room:: 3.3 62
- System indicating lights and alarms SRO only K/ K/ As shown in italics 4/9/2009 - 11:06:18 11 :06: 18 AM Page 20
~~"~----------------~5"
=.0 ES-401 5
&\ Form ESQ 0~1-C-_1:-----
Form ES-401-1 ES-401 ES"'Ol BWR Examination Outline Form ESES-40t-1
... Ol -1 Plant Systems - Tier 21Group 2 (RO I SRO)
K K K K K K A A A A G System'll I Name System'/ KIA KJA Topic(_)
Topic(s) IR I 1 2 3 4 5 6 1 2 3 4
- i~agog RadiatillA MIIA~.Mg
- !;aOOQ R.IlIaIIIlA MIIAiteFiRIt - - - - -- - - - - - - NOT RANDOMLY SELECTED -- .--.- - - ----- I
- iIlOOO as&QOO fOl",
IOIFe Pl9llGtj8A PFGteetillR - -- - -- -- - - - - -- - NOT RANDOML RANDOMLY Y SELECTED --- --- ---
Planl Ventilallon 288000 Plant Ventilation 1 A2.05 A2 .05 (10CFR 55.41 .5)
Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS; and (b) based on those predictions, predictions. use procedures to correct, control, or mitigate the consequences of 2.6 63 those abnormal conditions or operations:
- Extreme outside weather conditions: Plant-Specific 29000 2900011 SeCOndary Secondary CTMT 1 K3.01 (10CFR 55.41 .7)
K3.01 Knowledge of the effect that a loss or malfunction of the SECONDARY CONTAINMENT will have on the following:
4.0 4 .0 64
- rates Off-site radioactive release raies 38QQQ3 0I9OQQ3 eeA&N1 GIIRlfel Re_
Reem HVAC HVAG - - - - - - - - - - - NOT RANDOMLY SELECTED- SELECTED--- ..
-----1 Reaetor Vessellntemals 290002 Reactor 1 K1.04 (10CFR 55.41 .5)
Knowledge of the physical connections andlor and/or cause-effect I relationships between REACTOR VESSEL INTERNALS and the 3.4 65 following::
following
- HPCI: Plant*Specific Plant-Specific I KIA Category PoInt Point Totals:
(RO)I (RO 2 1 1 1 1 1 1 1 1 1 1 PoInt Total:
Group Point (RO) 12 I I KIA Category Point
~R6)egoty Point Totsls:
Totals:
2 1 Gt'OUp Point Total: (SRO)
Group 3 (SRO)
SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 2211
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401*3 ES-401-3
- '1 Facility:
Category E~lTY NPP Brownsi Ferry KIA.
KlA#
2 ..1.
- 1. G2.1.39 (10CFR 55.41.
Topic 10) 55.41 .10)
Date of Exam: ~6-July 6
- 3 IR 3.6 3 .6 RO 0 , 201)9 30, 66 66 2009 SRO-Only IR #
Knowledge of conservative decision making practices.
G2.1.13 GZ.1.13 (10CFR 55.43.5- 55.43.5 - SRO Only) 3.2 94 Knowledge of faCility facility requirements for CJ)
VJ controfling controlling vital/controlled access.
c:
C 0 2 ..1.
- 1. G2.1.6 (10CFR 55.41.10) 55.41 .10) 3.8 3 .8 67 67
+=i
""C1l m
(lI L...
~
Q)
Ability to ma transients.
managenage the control room room crew during during Q.
.0
.0 G2.1.4 (10CFR GZ.1.4 (10CFR 55.43.Z 55.43.2 - SRO Only)
..... Knowledge of individual licensed operator 3.B 95
~
~- 0 responsibilities related to to shift staffing, such such as
-0<.>
~
medical requirements, "no-solo" ~no-sofo
- operation,
- l maintenance of active license status, 10CFR55,
-C
'U etc.
c:
C 0
U 0 ~
- M-, NOT RANOOML RANDOMLY Y SELECTED - - - -
~
- M-, NOT RANOOML RANDOMLY Y SELECTED - - - -
- ~
~
~
- M-,
Subtotal 2.2.
2 .2 .
NOT RANOOML RAN DOMLY SELECTED RANDOMLY SELECTED NOT RANOOML G2.2.20 , I(10CFR
' 55.41 .10) 55.41.10) 2.6 2 .6 68 68 2
2 Knowledge of the process for managing troubleshooting activities.
G2.2.19 (10CFR GZ.Z.19 (10CFR 55.43.5 - SRO Only) 3.4 96
-0 Knowledge of maintenance work order
~
C 0
2.2.
2 .2 .
requirements.
G2.2.22 (10CFR 55.41 .5)
Knowledge of limiting conditions for operations 4.0 699 6
N -
()
U C
Q)
C1l E
and safety limits.
G2.2.23 GZ.Z.Z3 (10CFR limits .
(10CFR 55.43.2 - SRO Only)
Ability to track Technical Techn ical Specification limiting 4.6 97 conditions (orfor \,'./.,.<;;, auv, '0.
.-Q.
- J
~
0-
~ RANDOMLY NOT RANOOML Y SELECTED - - - -
W ~ RANDOMLY NOT RANOOML Y SELECTED - - - -
~ RANDOMLY NOT RANOOML Y SELECTED - - - -
~ RANDOMLY NOT RANOOML Y SELECTED - - - -
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401*3 ES-401-3
~
il Facility: Browns Ferry NPP Date of Exam:
Exam : Julv6 ~OO~
July 6 -. 30 .~
RO SRO-Only Category KlA#
KiA # Topic IR # IR #
2.3 G2.3.14 (10CFR 55.41 .12) 3.4 70 Knowledge of radiation or contamination hazards that that may arise during normal, abnormal, abnormal. or emergency conditions or activities.
(10CFR 55.43.4-GZ.3.11 (10CFR G2.3.11 55.43.4 - SRO Only) 4.3 98 Ability to to control radiation releases.
-0 2.3 3.2 71 G2.3.4 (1 OCFR 55.41 .12)
(10CFR
"-~ Knowledge of radiation exposure limits limits under C normal or emergency conditions.
normal 0a 3.6 99 0
() G2.3.7 (10CFR (10CFR 55.43.415- SRO Only)
('I')
(") C Ability to comply with radiation radiation work permit a0
- .t:i
- 0:;
requirements during normal or abnormal conditions.
ro ell "0 3.5 72 - -
"c::
a::
ro ell 2.3 G2.3.7 (10CFR 55.41 .12)
Ability to comply rad iation work permit comply with radiation requirements during normal normal or abnormal conditions.
~
- !,3 NOT RANDOMLY SELECTED -- - - -
~
- !,3 NOT RANDOMLY SELECTED - - - -
~
- !,3 NOT RANDOMLY SELECTED - - - -
Subtotal 3 2 2.4. G2.4.1B (10CFR G2.4.18 (10CFR 55.41.10) 55.41 .10) 3.3 73 cC Knowledge of the specific bases for EOPs.
CO ell a.
C-
~
- J
- l C/'J If)
~
Q.)
2.4.
G2.4.B (10CFR 55.43.5 - SRO Only)
GZ.4.B Knowledge of how abnormal operating procedures are used in G2.4.26 (10CFR in conjunction with EOPs.
(1 OCFR 55.41 .10) 3.1 74 -
4.5 100
'0
-C Knowledge of facility protection requ1rements protection requirements Q.)
Q) 0 including fire brigade and portable fire fighting V 0 equipment usage.
~
a.
C-2.4. G2.4.6 (1 OCFR 55.41 ..10)
(10CFR 10) 3.7 75 - -
0 Knowledge of EOP mitigation strategies.
strategies, c
C Q.)
Q)
C)
Cl ~ NOT RANDOMLY RAN DOML Y SELECTED - - - -
E
~
Q.)
Q) ~ NOT RANDOMLY SELECTED - - - -
w UJ ~ NOT RANDOMLY SELECTED - - - -
10 1
7 Page 23
DRAFT ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility: !5rlwllf ~"if
~"If Date of Exam: 2 oC)
(5 () '1 #<frr.
RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4
- Total
- 1. 1 4 3 4 3 2 4 20 4 3 7 Emergency & 2 1 1 1 1 1 7 2 1 3 2
Abnormal Plant N/A N/A Evolutions Tier Totals 6 4 5 4 3 5 27 6 4 10 1 4 2 3 2 2 3 2 2 2 2 2 26 3 2 5
- 2. I 2 2 1 1 1 1 1 1 1 1 1 1 12 0 2 1 3 Plant I Systems Tier Totals 6 3 4 3 3 4 3 3 3 3 3 38 5 3 8 I
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 2 1 I
- 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 ATIer Totals@
in each KIA category shall not be less than two).
- 2. The point total for each group and tier in the proposeq outline must match that specified in the table.
The final point total for each group and tier may deviate by V1 from that specified in the table e
based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 pOints.
- 3. Systems/evolutions Systems/evolutlons 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 ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution I in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be I selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
I 6. Select SRO topics for TIers 1 and 2 from the shaded systems and KIA categories.
i
- 7. *The generic (G) KIAs In Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
- 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter I
the group and tier totals for each category in the table above; Iffuel 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
- 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, selecttoplcs from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, I
L~~__~_. ~.
and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
J DRAFT
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO IR SRO T1G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 295001AA1. Partial or Complete Loss of Forced 3.3 3.3 3.3 3.3 DOD D D 0 ~ D D D D R~ .................................................. .
Core Flow Circulation / 1 & 4 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/
45.6) 295003AK1. Partial or Complete Loss of AC / 6 2.9 2.9 3.2 3.2 ~
~ 0 D D 0 D0 D 0 D 0 D 0 D 0 D 0 D 0 D0 Under voltage/degraded voltage effects on electrical loads ................................................ .
Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) 295004AK3. Partial or Total Loss of DC Pwr / 6 2.9 2.9 3.3 3.3 [J D ~ D D D D D [J D L---.-JL---.l~L---.-JL-JL---.-JL-J Ground isolation/fault determination ................. .
Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13)
_._------_._-- -.--,----------.-----,-~----
295005G2.4 Main Turbine Generator Trip / 3 4.0 4.6 0 D D 0 D 0 D 0 DODD D D D 0 D 0 D 0 ~
~ Knowledge of the parameters and logic used to assess the status of safety functions This is a Generic, no stem statement is associated.
associated .
295006AK2. SCRAM /1 / 1 3.8 3.8 3.8 3.8 D
[ ~ D D D D D D D D D Reactor water level control system .................. ..
Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) 295016G2.4 Control Room Abandonment Abandonmentl7 /7 2.7 4.1 0 D [] CJ 0D 0 0 DOD 0 ~
DDDDDD~ Knowledge of events related to system operations/status that must be reported to internal orginizations or ou1side This is a Generic, no stem statement is agencies.
associated.
Page 1 of 4 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION: IR T1G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 RO SRO 295018AA1. Partial or Total Loss of CCW I 8 3.3 3.3 3.4 3.4 0 0 0 0 0 [J li'l System loads ......................................... .
Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I 45.5 I 45.6) 295019AK2.
~-
Partial or Total Loss of Inst. Air 18 3.5 3.5 0
.~~-.~--
~
~DDD 0 0 0 o -----.~-------
0 0 0 ADS: Plant-Specific ................................. .
Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7 I 45.7 I 45.8)
_. _.._ - . _ - - - ..... -~ ....- - -.....- - . - . - - - ...
-,,~~-----.--- .._
~~----- -- --_._. _ - - - - _ .- - - - .
. -_. ~-.- ..-
295021G2.2 Loss of Shutdown Cooling I 4 3.6 3.6 I~J D
[J 0 D o D OLJ [] D D OOli'l ~ (multi-unit) Ability to explain the variations in control
~ . . . . board layouts, systems, instrumentation and procedural This ISis a Generic, Genenc, no stem statement ISis actions between actions units at between units at aa facility.
facility.
associated.
---.-~-.--~-- ... ----.-~- _
295023AA1. Refueling Acc Cooling Mode I 8 3.4 3.7 o ODOli'lDO o Radiation monitoring equipment... .................... .
Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5 I 45.6)
- .--- _ . _ - _ . - - _ .. _-_... ~--.-.-- ....- - . _ . _ - _. . _ - - - - _.. _ - - - - _ ... _ - - - .~-- ..- - - . - - - . - ....- - . - . - - . - . - - - -
295024EA2. High Drywell Pressure I 5 3.8 3.8 0 0 0 0 ~ 0 0 Suppression pool leveL .............................. .
Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 I 43.5 I 45.13)
- ' -.--.--~.--- ._-- -~---~-.-- .-------~------ ..- - - - -... ~-- . . ._-_ ...._ - - - - - - - .. _ - - - -
295025EK2. High Reactor Pressure I 3 3.9 4.1 li'l 0 0 0 0 0 0 0 0 ARI/RPTIA TWS: Plant-Specific ........................ .
Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7 I 45.7 / 45.8)
Page 2 of 4 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO IR SRO T1G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 295027EK3. High Containment Temperature / 5 3.2 3.2 3.2 3.2 0 0 ~ DOD 0 DOD 0 Containment spray: Plant-Specific ................... .
Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFA: 41.5/41.10/45.6/
45.13) 29502SEK1. High Drywell Temperature / 5 3.5 3.5 3.7 3.7 ~
~ 0 0 0 0 0 0 0 0 0 Reactor water level measurement.. .................... .
Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFA: 41.S to 41.10/45.3) 295030EK3. Low Suppression Pool Wtr Lvi / 5 3.6 3.7 0 0 ~ o o o RCIC operation: Plant-Specific ...................... .
Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFA: 41.5/41.10/45.6/
45.13)
---.~--~--~--~~------~--~--.-----------.------~~~-~------- ----------.~~---~~-----. ~~-
295031EA2. Reactor Low Water Level / 2 4.2 4.2 4.2 4.2 0 0 0 0 0 0 DD~D 0 ~ 0 D 0 Reactor pressure .............................. .
Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTlON):(CFA: 41.10/43.5/
45.13)
--.------~---------~----------~-.--- ------- -~-------~~- ~~----~----------~---
295037G2.2 SCRAM Condition Present and Power 3.7 4.1 0 D 0 0 D D 0 D0 0 D D 0 D 0 ~ Knowledge of surveillance procedures.
Above APRM Downscale or Unknown . .
// 1 1 This is a Generic, no stem statement ISis associated.
~----~--~---- ~-------~-- .. -~---.--~-------.------~~--~~--
29503SEK1. High Off-site Release Rate / 9 2.5 3.1 ~ D 0 [J 0 [J DOD 0 0 0 Biological effects of radiOisotope ingestion ......... .
Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFA: 41.S to 41.10 / 45.3)
Page 3 of 4 10/221200S 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO IR SRO T1G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 600000AK3. Plant Fire On Site / 8 2.8 2.8 3.4 3.4 D D ~ D D D D D D 0 [J Actions contained in the abnormal procedure for plant fire on site Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13) 700000AK1. Generator Voltage and Electric Grid 3.3 3.5 ~J
~J D D D D D D D D 0 Definition of the terms: volts, watts, amps, VARS, power Distrurbancecs factor Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3)
Page 4 of 4 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO SRO T1 G2 BWR EXAMINATION OUTLINE I R K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:
FORM ES-401-1 295009AK2. Low Reactor Water Level / 2 2.6 2.6 D r;(I Dl~DDDDDD o Reactor water cleanup ................................ .
Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8)
- _ _ _ _ ~ _ _ _ ~. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- _ _ 0" _ _ _ _ _
- _ _ _ ~_. _ _ _ o _ _ _ _ _ _ _ _ _ _ 0 295010G2.4 High Drywell Pressure / 5 4.6 4.6 4.4 4.4 0 0 0 DOD DOD 0 0 0 D 0 D0 D 0 D 0 ~
~ Ability to perform without reference to procedures those actions that require immediate operation of system This is a Generic, no stem statement is components and controls.
associated.
295012AK1. High Drywell Temperature / 5 3.3 3.5 ~
~ D 0 [] 0 o 000 Pressure/temperature relationship .................... .
Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) 295017AK3. High Off-site Release Rate / 9 3.3 4.5 O~O[JOOOO[10 Implementation of site emergency plan ................ .
Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13) 295022AA2. Loss of CRD Pumps / 1 3.1 3.2 D D D D D ~ 0 D CRD mechanism temperatures ........................... .
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13) 295029EA1. High Suppression Pool Wtr Lvi / 5 3.4 3.4 3.5 3.5 DOD DOD ~ D DO 00 RCIC: Plant-Specific ................................ .
Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.7/45.5/
45.6)
Page 1 of 2 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO SRO T1G2 BWR EXAMINATION OUTLINE I R K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:
FORM ES-401-1 295036EK1. Secondary Containment High 2.9 3.1 ~
~ 0 0 0 [J 0 0 DOD 0 Radiation releases ................................... .
Sump/Area Water Levell 5 Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFA: 41.8 to 41.10/45.3)
Page 2 of 2 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
AO IR SAO T2G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 203000K5.0 AHA/LPCI: Injection Mode 2.7 2.7 2.9 2.9 0 0 0 0 ~ 0 LJ 0 0 0 0 Testable check valve operation Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFA: 41.5/45.7)
--- ----- ---~-.~ .. - - - - - --~--,,~~---.~------ ._--
205000K2.0 Shutdown Cooling 2.5 2.7 0 ~
~ 0 0 0 0 0000 Motor operated valves Knowledge of electrical power supplies to the foliowing:(CFA: 41.7) o0 o0
-~--~~-----~~--------~~. .------------~---. ---.~~----~- -----------.--~----
206000K4.1 HPCI 3.1 3.3 0 0 0 ~ 0 [.J 0 Minimizing fission product concentration in the
. condensate storage tank (valve closures on system Knowledge of (SYSTEM) deSign design feature(s) initiation): BWA-2,3,4(P-Spec) initiation): BWA-2 34(P-Spec) and or interlock(s) which provide for the ' ,
foliowing:(CFR: 41.7) 207000A4.0 Isolation (Emergency) Condenser 3 3.2 ODD o ooo~o Primary and shell sidetemperatures: BWA-2,3 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 209001 K1.1 LPCS 2.9 3.1 ~ ECCS room coolers Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFA: 41.2 to 41.9/45.7 to 45.8)
[J o
.~--~~~-~~- ---~--~---~~---~~-----~- ----------.--~-------------.-.-----------~-
209002A3.0 HPCS 3.7 3.7 [J 0 0 0 0 [J 0 [J ~ 0 System flow: BWA-5,6 Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7/45.5)
~--~--~----~~----~~-----.---------------------~---~-----. ~-------- ~.-~------- -----
211000A4.0 SLC 4.2 4.2 0 0 0 0 0 0 OD~O System initiation: Plant-Specific Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)
Page 1 of 5 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO IR SRO T2G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 212000K3,1 RPS 3,0 3.0 3,3 3.3 D D ~ D D D D D D [J D Recirculation system Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 215003K4.0 IRM 2.9 2.9 2.9 2.9 0 D D D ~ D DOD 0 0 0 Varying system sensitivity levels using range switches Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41,7) 215004A3.0 Source Range Monitor 3,2 3.2 000000 ~DD Meters and recorders Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7/45,5)
- -------~--
215005A2.0 APRMI1 LPRM APRM 3.2 3.4 0 [J 0 DDD~ o Recirculation flow channels flow mismatch Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 41.5 I 43.51 45.31 45.13) 217000K3.0 RCIC 3,6 3,6 3.6 3.6 0 0 ~ D D DOD 0 0 0 Adequate core cooling Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)
---~~-~.--. . ~~-.-.~~-.---~~--
217000K3.0 RCIC 3.6 3.6 3.6 3.6 0 0 ~ 0 D [J 0 0 0 0 0 Reactor vessel pressure Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41,7/45.6)
Page 2 of 5 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
- q****
T2G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 21S000K1.0 ADS 4.0 4.1 ~
~ 0 0 0 0 0 0 0 [J 00 0 0 Low pressure core spray: Plant-Specific Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.S) 223002K1.0 PCIS/Nuclear Steam Supply Shutoff 3.0 3.2 ~ 0 0 0 0 0 0 0 DO o Plant ventilation Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.S) 223002K1.1 PCIS/Nuclear Steam Supply Shutoff 2.7 2.9 ~ 0 00000 00 o Traversing in-core probe system Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.S)
-- - - - ----.-.-------------.-~~-- --_._----_._----_._. ~-- --.----~- -.----~-- ..- - - - - - - - - . - -
239002A1.0 SRVs 3.3 3.4 0 [] 0 D 0 ~ 0 0 D 0 Tail pipe temperature Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/
45.5) 259002G2.4 Reactor Water Level Control 4.1 4.3 n 0 0 II 0 il 0 n 0Il 0n II n ooo~n n ~ Ability to prioritize and interpret the significance of each annunciator or alarm.
This is a Generic, no stem statement is associated.
~--------------.~---.-.~--~-~-.--- -----~--- ----.~- ----- - - - - - - - - -
261000K6.0 SGTS 3.1 3.3 0 OO[J~OO 00 Primary containment high pressure: Plant-Specific Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7)
Page 3 of 5 10/221200S 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO IR SRO T2G1 BWR EXAMINATION OUTLINE K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:
262001G2.2 AC Electrical Distribution 3.9 3.9 4.S 4.S D0 0 D0 D0 DOD 00 D oo~ D ~ Knowledge of less than one hour technical specification action statements for systems.
This is a Generic, no stem statement is associated.
262002K6.0 UPS (AC/DC) 2.8 3.1 00 O~D[JOOO D.C. electrical power Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.71 4S.7)
~-- .....- _ . _ - -.. _ - _ . - - - - .. _ - - - - - - - - - _ .....- - _ . _ - - - - _ . - - - - - _ ...._ - - -
262002K6.0 UPS (AC/DC) 2.7 2.9 D 0 0 0 0 ~J 0 0 0 0 Static inverter Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.71 4S.7)
- - - - - - - - - - . - - - - - - . - - - . - - -..- - -.. -.---.---.--------.------~.---------
263000A2.0 DC Electrical Distribution 2.8 3.2 0 0 0 lJ 0 ~ 0 lJ Grounds Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.S 1 43.S 1 4S.3 14S.13) 264000KS.0 EDGs 3.4 3.4 3.4 3.4 0 0 0 0 ~ 0 0 0 0 0 0 Paralleling A.C. power sources Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.S 1 4S.7) 300000K2.0 Instrument Air 2.8 2.8 0 ~DDD
~ 0 0 0 0 o 00 Instrument air compressor Knowledge of electrical power supplies to the foliowing:(CFR: 41.7)
Page 4 of S 10/2212008 10:1S AM
(I ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 400000A1.0 Component Cooling Water 2.8 2.8 0 0 0 0 0 0 ~ 0 0 0 0 CCW flow rate Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5)
Page 5 of 5 10/2212008 10: 15 AM
ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:
RO SRO 201001K6.0 CRD Hydraulic 3.6 3.7 ODD o~ooooo RPS Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/ 4S.7) 201004A1.0 RSCS 3.3 3.3 3.3 3.3 0 0 0 0 0 0 ~ D [J o Reactor manual control system: BWR-4,S Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.S /
4S.S)
-- --~~-~.- .. -.~_ .. ~.- .. ---~~------.-~.--~--.~---~-.--.~~~-
21S001A3.0 Traversing In-core Probe 2.S 2.S 2.6 2.6 DOD 0 0 0 0 0 ~ 0 D ooooo~ Valve operation: Not-BWR1 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/ 4S.S) 21S002K1.0 RBM 3.2 3.1 ~
~ 0 0 [J 0 0 0 o 0 [I DO LPRM: BWR-3,4,S Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/ 4S.7 to 4S.8) 219000K2.0 RHA/LPCI: Torus/Pool Cooling Mode 3.1 3.3 0 ~ 0 DO o Pumps Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 239003K4.0 MSIV Leakage Control 3 3.4 3.4 DO
[J [J [J ~ 0 0 0 0 0 0 0 0 0 0 o 0 Performance of intended safety function following any single active component failure: BWR-4,S,6(P-Spec)
Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 24S000KS.0 Main Turbine Gen. / Aux. 2.6 2.9 0 [] [] 0 ~ o DOD 00 Generator operations and limitations Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.S / 4S.7)
Page 1 of 2 10/2212008 10:1S AM
()
ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 256000G2.1 Reactor Condensate 4.4 4.0 n D i[ll nD I-I n n II n Il n ~ Ability to locate and operate components, including local controls.
This is a Generic, no stem statement is associated. .
271000A4.0 Offgas 3.3 3.3 3.2 3.2 D D D D D D C U D D~D ~ D System indicating lights and alarms Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 288000A2.0 Plant Ventilation 2.6 2.6 2.7 2.7 DOD D DOD ~ D D Plant* Specific Extreme outside weather conditions: Plant-Specific Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 290001K3.0 Secondary CTMT 4.0 4.4 D D ~ D D D D D D D Off-site Off*site radioactive release rates Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 290002K1.0 Reactor Vessel Internals 3.4 3.5 ~ 0 [J D D D D D D Plant-Specific HPCI: Plant* Specific Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8)
Page 2 of 2 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO IR SRO T3 BWR EXAMINATION OUTLINE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 G2.1.39 Conduct of operations 3.6 4.3 000 000 oo~
OO~ Knowledge of conservative decision making practices 0 0 0 0 0 0 0 0
~
~---~ --~--- ------------------------------------------~----- -----------------------~ ~ ----~--~
G2.1.6 Conduct of operations 3.8 4.8 0 ~
~ Ability to manage the control room crew during plant transients.
o
.-------.----~ ---~----------
G2.2.20 Equipment Control 2.6 3.8 0 o 000 ~ Knowledge of the process for managing troubleshooting activities.
G2.2.22 Equipment Control 4.0 4.7 0 [l 0 o o o ~ Knowledge of limiting conditions for operations and safety limits.
o
---~-~-------
G2.3.14 Radiation Control 3.4 3.8 [J 0 0 0 0 0 Ii'] Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities
-- -- - - - ---.- ._----- - - -~----- --------- - - - - - - - - - - - - - - - - ------_.---------._----
G2.3.4 Radiation Control 0 3.2 3.7 I I II rl n rl n I-l 0000 0 o 0 ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 0 0 0 0 OOD ~ Ability to comply with radiation work permit requirements during normal or abnormal conditions Page 1 of 2 10/2212008 10:15 AM
(t ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
AO SAO G2.4.18 Emergency Procedures/Plans 3.3 4.0 DlJDlJDDD D~ Knowledge of the specific bases for EOPs.
---, --- ----------------~---
G2.4.26 Emergency Procedures/Plans 3.1 3.1 3.6 3.6 0 0 0 0 DOD 0 0 0 ~ Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
-~----- - -----~-
~--'---"-~----'----"'-'-- - ~- -_
G2.4.6 Emergency Procedures/Plans 3.7 4.7 0 0 00000 D~ Knowledge symptom based EOP mitigation strategies.
Page 2 of 2 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO SRO SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 295003G2.4.50 Partial or Complete Loss of AC / 6 4.2 4.2 4.0 4.0 C.J D 00 D D DOD D D ~
OOODOOO~ . Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
This is a Generic, no stem statement is associated.
295016G2.4.3 Control Room Abandonment / 7 3.7 3.9 0 D D D D D OOOOD o D ~ Ability to identify post-accident instrumentation.
This is a Generic, no stem statement is associated.
295018AA2.01 Partial or Total Loss of CCW / 8 3.3 3.4 0 o OOO~O o Component temperatures ............................... .
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
- ... ----~- ..- - - - . - - - - - - _ . _ - - - - - - - - - - ._-_. - - - - . - - - - -.. -~---------- .. _ - - - ._----------------------
295023AA2.01 Refueling Acc Cooling Mode / 8 3.6 4.0 0 D D O[JO~O o Area radiation levels ................................ .
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13) 295025EA2.01 High Reactor Pressure / 3 4.3 4.3 0 o OOO~OOO Reactor pressure ..................................... .
Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13) 295027EA2.01 High Containment Temperature / 5 3.7 3.7 3.7 3.7 0 [1 0 [J 0 0 0 ~ 0 0 Containment temperature: Mark-ilL ................ .
Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
Page 1 of 2 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
AO SAO SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 700000G2.4.31 Generator Voltage and Electric Grid Distrurbancecs 4.2 4.1 o D DODD DDD~ D~ Knowledge of annunciators alarms, indications or response procedures This is a Generic, no stem statement is associated.
Page 2 of 2 10/2212008 10:15 AM
ES-401, REV' 9 KA NAME I SAFETY FUNCTION:
RO SRO SRO T1G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 295012G2.4.34 High Drywell Temperature / 5 4.2 4.2 4.1 4.1 0DDDDD0 0 0 0 0D[JDD~
[J 0 0 ~ Knowledge of RO tasks performed outside the main control room during an emergency and the resultant This is a Generic, no stem statement is operational effects associated.
295013AA2.02 High Suppression Pool Temp. /5 3.2 3.5 0D 0D D [1 o D D~DD D~ Localized heating/stratification ..................... .
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
~~-.---.~~-----.-----.--.--~ .. ----~------ -----~ .. - - - _._----_.._ - - - - - - - - - - - - - -
295033EA2.03 High Secondary Containment Area Radiation Levels / 9 3.7 4.2 D DDD ~DDD Cause of high area radiation ........................ .
Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
Page 1 of 1 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO SRO SRO T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 206000A2.16 HPCI 4 4.1 0 0 [] 0 ~ 0 High drywell pressure: BWR-2,3,4 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/ 45.13) 212000A2.20 RPS 4.1 4.2 0 0 OljDO~OO Full system activation (full-SCRAM)
Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) o
~------.~---.- ~-
217000G2.4.41 RCIC 2.9 4.6 [JOOl]O OO~ DIi'l Knowledge of the emergency action level thresholds and classifications.
This is a Generic, no stem statement is associated.
239002G2.4.45 SRVs 4.1 4.1 4.3 4.3 0 11 11 0 0n 110 n0 [] i-I n 0 n0 n0 n0 ~
~ Ability to prioritize and interpret the significance of each annunciator or alarm.
This is a Generic, no stem statement is associated.
261000A2.11 SGTS 3.2 3.3 0 [1 00 ~OOO High containment pressure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)
Page 1 of 1 10/2212008 10:15 AM
ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:
RO SRO 202001 A2.1 0 Recirculation 3.5 3.5 3.9 3.9 0 0 0 0 0 0 0 ~ 0 D D Recirculation pump seal failure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)
.~~~-.--.------~~~--.---.~-----------~-~---~-.--.--.------------- ...- - - --~.-----.--
215002A2.05 RBM 3.2 3.2 3.3 3.3 D 1"1 II D [J r-l Dn IlJi D D ii'I~ D D D RBM high or inoperable: BWR-3,4,5 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)
.~----~~-'~-----'-~---'-'--'-.--.-'-- - - - -.. - .. - - ... ~---.
233000G2.4.35 Fuel Pool Cooling/Cleanup 3.8 3.8 4.0 4.0 i-I n
[J D DODn II n D n n D nDOD I-I rl ii'I
~ Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects This is a GeneriC, Generic, no stem statement is associated.
Page 1 of 1 10/22/2008 10:15 AM 10122/2008
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO SRO SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-1 G2.1.13 Conduct of operations 2.5 3.2 0 0 OC]OOD ~ Knowledge of facility requirements for controlling vital /
controlled access.
o
---~~ ------~-------.------
G2.1.4 Conduct of operations 3.3 3.B 0 D 0 D D D D 000 D ~ Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license statur, 10CFR55 etc.
- - - - - - - - - - - -... - - - . - - - - - - - - - - - - - - - - - . - - - - -.. --~--.---- _.-- ------
G2.2.19 Equipment Control 2.3 3.4 0 DOD D 0 0 0 0 ~
~ Knowledge of maintenance work order requirements.
G2.2.23 Equipment Control 3.1 4.6 o DO OO~ D~ Ability to track Technical Specification limiting conditions for operations.
.-------.---::---c----- -_._-------------.- - --------_ -_
-.. -~-
G2.3.11 Radiation Control 3.B 4.3 D 0 0 0 0 0 COO DU~ ~ Ability to control radiation releases
----- -.---------------------------~-.-------.------------ ---.-~-----.----
G2.3.7 Radiation Control 3.5 3.6 D D D 000 o [J D [J D D D 0 D 0 D 0 [~
[~ Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.B Emergency Procedures/Plans 3.B 4.5 D 0 0 0 0 0 0 0 0 0 0 D~ ~ Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Page 1 of 1 10/221200B 10:15 AM