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:
July 6 - 30, 2009 Examination Level (circle one): RO'(SRO) Operating Test Number:
HLT 0801 Administrative Topic Type Describe activity to be performed (see Note)
Code
- 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.
- Type Codes & Criteria:
(C}ontrol Room (D)irect from bank t: 3 for ROs; ~ 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (:: 1)
(P)revious 2 exams t: 1; randomly selected)
(S)imulator SRO only JPMs shown in italics ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30, 2009 Examination Level (circle one): RO'(SRO) Operating Test Number:
HLT 0801 Administrative Topic Type Describe activity to be performed (see Note)
Code
- 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.
- Type Codes & Criteria:
(C}ontrol Room (D)irect from bank t: 3 for ROs; ~ 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (:: 1)
(P)revious 2 exams t: 1; randomly selected)
(S)imulator SRO only JPMs shown in italics
HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License Reactivation Modified: OPDP-10 is a new procedure that removed information from OPDP-1,
Conduct of Operations; and modified critical data in JPM OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev. 0, Appendix E (32.1.4 KnOwtedge6f individual licensed operator respOnsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10/43.2) IMPORTANCe: RO 3.3 SRO.3.8
- b. Evaluate Recombiner Performance Previous: JPM revised to newest revision of 3-01-66 3-01-66, Oft-Gas System, Rev 57 G2~ 1.7 Ability to evaluate plant performance andrnake operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5/43.5/45.12/45.13) IMPORTANCE RO 4.4 SRO 4.7
- c. Perform Jet Pump Surveillance 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, Jet Pump Operability, Rev 25 G2.2.12 Knowledge of of Surveillance PrOcedures. (CFR: 41.10/43.3/45.13)
IMPORTANCE: RO 3. 7SRO 4.1
- d. Calculate the maximum permissible stay time within emergency dose limits and determine the approving authority New: JPM - Classroom EPIP-15, EMERGENCY EXPOSURE, Rev 9 G 2~3.4 knOwt8dge of radiation expOsure limits under normal or emergency conditions. (CFR: 41.12 143.4 145.1 0) IMPORTANCE RO 3.2 SRO 3.7 SRO only JPMs shown in italics HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of license Reactivation Modified: OPDP-10 is a new procedure that removed information from OPDP-1,
Conduct of Operations; and modified critical data in JPM OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev. 0, Appendix E G2-1.4 Knowtedge of individual licensed operator responslbUIties related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of Bctlvellcense alatus, 10CFR55, etc. (CFR: 41.10 143.2) IMPORTANCE: RO 3.3 SR03.8
- b. Evaluate Recombiner Performance Previous: JPM revised to newest revision of 3-01-66 3-01-66, Off-Gas System, Rev 57 G2.1.7 Abili1y to evlluate plant perfonnance and make operational judgments based on operating chorae_llea, reactor behavior, Ind instrument Interpretation. (CFR: 41.5/43.5/45.12/45.13) IMPORTANCE RO 4.4 SRO 4.7
- c. Perform Jet Pump Surveillance 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, Jet Pump Operability, Rev 25 G2.2-12 Knowtedge of of Surveillance Procedures. (CFR: 41.10 143.3/45.13)
IMPORTANCE: R03.7 SR04.1
- d. Calculate the maximum permissible stay time within emergency dose limits and determine the approving authority New: JPM - Classroom EPIP-15, EMERGENCY EXPOSURE, Rev 9 G 2-3.4 Knowledge of radiation exposure limits under nonnal or emergency conditions. (CFR: 41.12/43.4/45.10) IMPORTANCE RO 3.2 SRO 3.7 SRO only.1PMs 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 CUlVe)
New JPM - Simulator EPIP-1, Emergency Classification Procedure, Rev. 43, Primary Containment 2.0, Section 2.1 EPIP-4, Site Area Emergency, Rev. 31 SRO Only G2.4.3B Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinatQr if required.. (CFR: 41.10/ 43.S /
45.11) IMPORTANCE; SRO 4.4 SRO only JPMs 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. Rev. 43, Primary Containment 2.0, Section 2.1 EPIP-4, Site Area Emergency, Rev. 31 SRO Only GZ.4.38 Ability to take actions called for In the facility _y ptan. Incluc6.
supporting or acting as emergency coordinator if required. (CFR: 41.10143.51 45.11) IMPORTANCE: SRO 4.4 SRO only JPHs shown in italics
I.
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30,2009 Examination Level (circle one): RO '(SRO) Operating Test Number:
HLT 0801 Administrative Topic Type Describe activity to be performed (see Note)
Code
- 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)
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:
5k~~ft~_..t si/J fa i (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 DRAFT SRO only JPMs shown in italics
)
I.
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30,2009 Examination Level (circle one): RO '(SRO) Operating Test Number:
HLT 0801 Administrative Topic Type Describe activity to be performed (see Note)
Code
- 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)
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:
5k~~ft~_..t si/J fa i (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 DRAFT SRO only JPMs shown in italics j
HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License Reactivation Modified: OPDP-10 is a new procedure that removed information from OPDP-1,
Conduct of Operations; and modified critical data in JPM OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev. 0, Appendix E G2.1.4KnoWtedge of individual licensed operator responsibilities related to -Iliff staffing. such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10 143.2) IMPORTANC~: RO 3.3 SRO 3.8
- b. Perform Jet Pump Surveillance 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, Jet Pump Operability, Rev 25 G2.1.7 Ability to evaluate plant performance and make operational juc:tgmentS based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5143.5145.12145.13) IMPORTANCE RO 4.4 SR04 *.,
- c. Determine Correct Method of Verification on a Given System Previous NRC Exam: HL T 0707 (Modified slightly based on NRC feedback)
SPP-10.3, Verification Program, Rev. 1, Sections 3.3.1,3.4.2, and 3.4.3 G2.2.14 Knowledge of the process forcontroUingequipment configuration or status. (CFR: 41.10 143.3145.13) IMPORTANCE: RO 3.9 SRO 4.3
- d. Calculate the maximum permissible stay time within emergency dose limits and determine the approving authority New: JPM - Classroom EPIP-15, EMERGENCY EXPOSURE, Rev 9 G 2.3.4 Knowledge of radiation expOsure limits under nonnal or emergency conditions. (CFR: 41.. 1~ 143~4/45.10) IMPORTANCE RO 3.2, SRO 3.7 SRO only JPMs shown in italics HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License Reactivation Modified: OPDP-l0 is a new procedure that removed information from OPDP-l, Conduct of Operations; and modified critical data in JPM OPDP-l0, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev. 0, Appendix E G2.1.4 Knowtedge of lndlvlduailicensed operator.... ponslbilltie. re_ to.hlft staffing, such as medical reqUirements, "no-&O'o" operation. maintenance of actlvelicen.. _.
10CFR55. etc. (CFR: 41.10 143.2) IMPORTANCE: RO 3.3 SRO 3.8
- b. Perform Jet Pump Surveillance 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, Jet Pump Operability, Rev 25 G2.1.7 AbIlity to evaluate plant performance and make operational judgme"ts based on operating characteristics, reactor behavior, and Instrument interpetath>n. (CFR: 41.5/43.5/45.12/45.1311I1PORTANCE RO 4.4 SRO 4.7
- c. Determine Correct Method of Verification on a Given System Previous NRC Exam: HL T 0707 (Modified slightly based on NRC feedback)
SPP-10.3, Verification Program, Rev. 1, Sections 3.3.1,3.4.2, and 3.4.3 G2.2.14 Knowledge of the process for controlling equipment configuration or status. (CFR: 41.10/43.3/45.13) IIiPORTANCE: RO 3.9 SRO 4.3
- d. Calculate the maximum permissible stay time within emergency dose limits and determine the approving authority New: JPM - Classroom EPIP-15, EMERGENCY EXPOSURE, Rev 9 G 2.3.4 Knowledge of radiation exposure limits under normal or em_ncy conditions. (CFR: 41.12/43.4/45.10) IMPORTANCE RO 3.2 SRO 3.7 SRO only 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, Rev. 43, Primary Containment 2.0, Section 2.1 EPIP-4, Site Area Emergency, Rev. 31 SRO Only G2.4.38.Ability to talce actions ~lIed for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (CFR: 41.10/43.5/
45~ 1 1) IMPORTANCE: SRO 4.4 SRO only JPMs 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. Rev. 43. Primary Containment 2.0, Section 2.1 EPIP-4, Site Area Emergency. Rev. 31 SRO Only G2.4..38 AbIlity to take actions called fo, in the facility emergency plan, including supporting or acling as emergancy coordinator if required. (CFR: 41.10 /43.5/
45.11) IMPORTANCE: SRO 4..4 SRO only JPMs shown in italics
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30,2009 Examination Level (circle one): RO'(SRO) Operating Test Number:
HLT 0801 Administrative Topic Type Describe activity to be performed t/
(see Note)
Code *
/
Conduct of Operations M
Detennine Adequate Perfonnance of Licens~tion JPM 541 (RO / SRO)
J 1/
fy Conduct of Operations D
Conduct of Operations Questiyred 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
/
./
//~
/
Emergency Plan N,S ClaSsify the Event per the REP (Primary System Leakage fT'orus Pressure) Exceeding PSP Curve)
/'
/
NOTE: All items (5 totaly{re required for SROs. RO applicants require only 4 items unless they are retaking only the ~Jjininistrative topics, when all 5 are required.
/
- Type Codes &7ria:
(C)ontrol Room (D)irect from bank ~ 3 for ROs;.s 4 for SROs and RO retakes)
/
(N)ew or (M)odified from bank ~ 1)
(P)revious 2 exams ~ 1; randomly selected)
(S)imulator SRO only JPMs shown in italics ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30,2009 Examination Level (circle one): RO'(SRO) Operating Test Number:
HLT 0801 Administrative Topic Type Describe activity to be performed !/i (see Note)
Code *
/
Conduct of Operations M
Detennine Adequate Perfonnance of Licens~tion JPM 541 (RO / SRO)
J 1/
fy Conduct of Operations D
Conduct of Operations QUestio~red Turnover 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
/
./
//~
/
Emergency Plan N,S ClaSsify the Event per the REP (Primary System Leakage vfforus Pressure) Exceeding PSP Curve)
/
NOTE: All items (5 totaly(re required for SROs. RO applicants require only 4 items unless they are retaking only the ~Jjininistrative topics, when all 5 are required.
/
- Type Codes &7ria:
(C)ontrol Room (D)irect from bank ~ 3 for ROs;.s 4 for SROs and RO retakes)
/
(N)ew or (M)odified from bank ~ 1)
(P)revious 2 exams ~ 1; randomly selected)
(S)imulator SRO only JPMs shown in italics
HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License Reactivation Modified: OPDP-10 is a new procedure that removed information from OPDP-1,
Conduct of Operations; and modified critical data in JPM OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev. 0, Appendix E G2.1.4 KrioWl8dge of indiViduai'licensedoperator resPonsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license, status, 10CFR55, etc. (CFR: 41.10143.2) IMPORTANCE: RO 3.3 SRO 3.8
- b. Conduct of Operations Question - Required Turnover Information Direct from Bank OPDP-1, Conduct of Operations, Rev. 12, section 7.3.L q2~1.3 Knowledge of shift or short-tenn relieftumover practices. (CFR: 41.101 45.13) IMPORTANCE: RO 3.7SRO.3.9
- c. Determine Correct Method of Verification on a Given System Previous NRC Exam: HL T 0707 (Modified slightly based on NRC feedback)
SPP-10.3, Verification Program, Rev. 1, Sections 3.3.1, 3.4.2, and 3.4.3 G2.2.14 Knowledge of the process for controlling equipment configuration or status. (CFR: 41.10' 43.3' 45.13) IMPORTANCE: RO 3.9 SRO 4.3
- d. Determine the Dose Limitation for Declared and Undeclared Pregnant Female Employees and Their Eligibility for Overtime Direct from Bank SPP-5.1, Radiological Controls, Rev. 6, Section 3.4.1 G2.3.4 Knowledge of radiatiorfexposure limits under normal or emergency conditions. (CFR: 41.12143.4/45.10) IIIPORTANCE: RO 3.2 SRO 3.7 SRO only JPMs shown in italics HLT 0801 Administrative Topics Narrative Administrative Topics:
- a. Determine Adequate Performance of License Reactivation Modified: OPOP-10 is a new procedure that removed information from OPOP-1.
Conduct of Operations; and modified critical data in JPM OPOP-10. License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev. 0, Appendix E G2.1.4 Knowledge of individuailicensad operator responsibilities _to shift stalling, such as medical requirements, "nCHOlo" operation, maintenance of active Ucense status, IOCFR55, etc. (CFR: 41.10 143.2) IMPORTANCE: RO 3.3 SRO 3.8
- b. Conduct of Operations Question - Required Turnover Information Direct from Bank OPOP-1, Conduct of Operations, Rev. 12, section 7.3.L G2.1.3 Knowledge 01 shift or short-term relieltumoyer practlceo. (CFR: 41.10 I 45.13) IMPORTANCE: RO 3.7 SRO 3.9
- c. Determine Correct Method of Verification on a Given System Previous NRC Exam: HLT 0707 (Modified slightly based on NRC feedback)
SPP-10.3, Verification Program, Rev. 1, Sections 3.3.1, 3.4.2, and 3.4.3 G2.2.14 Knowtedge of the process lor controlling equipment configuration or statua. (CFR: 41.10 143,3145.13) IMPORTANCE: RO 3.9 SRO 4.3
- d. Determine the Dose Limitation for Declared and Undeclared Pregnant Female Employees and Their Eligibility for Overtime Direct from Bank SPP-5.1, Radiological Controls, Rev. 6, Section 3.4.1 G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12143.4145.10) IMPORTANCE: RO 3.2 SRO 3.7 SRO only JPMs shown in italics
HLT 0801 Administrative Topics Narrative Administrative Topics: (continued) r:'
r:;;:;:.<;::.i k~.~",~
f
~~
t;:
'\\,....
~
- e. Classify the Event per the REP (Primary Sys. Leakage (Torus Pressure)
Exceeding PSP Curve)
New JPM - Simulator EPIP-1, Emergency Classification Procedure, Rev. 43, Primary Containment 2.0, Section 2. 1 EPIP-4, Site Area Emergency, Rev. 31 SRO Only G2.4.'3BAbi/ity to take actions called fOr in the facilnYfHnfwgency pian, including supporting or acting as emergency coordinator if required. (CFR:41. 10143.51 45.11) IMPORTANCE: SRO 4.4 SRO only JPMs shown in italics HLT 0801 Administrative Topics Narrative Administrative Topics: (continued)
D-r-. r roo>""*"
;. t.
\\
I~
, 'fJ't.J- '- ;"
- e. Classify the Event per the REP (Primary Sys. Leakage (Torus Pressure)
Exceeding PSP CUlVe)
New JPM - Simulator EPIP-1, Emergency Classification Procedure, Rev. 43, Primary Containment 2.0, Section 2.1 EPIP-4, Site Area Emergency, Rev. 31 SRO Only GZ.4.38 AbIlity to take actions called for In the facility "",.. gency pIM, Including supporting or acting es emergency coorrtinator if requIred. (CFR: 41.10143.51 45.11) IMPORTANCE: SRO 4.4 SRO only JPMs shown in italics
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30, 2009 Exam Level (circle one): RO 4Rqj)/ SRO-U Operating Test No.:
HLT 0801 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a.
Alternate RPV Injection - Standby Coolant S,E, EN,L, N 2
- b.
RWM Functional Test for Startup 3-SR-3.3.2.1.2 S, L, N 7
- c.
Place RCIC in Test Mode From Standby for Alternate S,A, 0, E, L 3
RPV Pressure Control
- d.
Start and Inject SLC Solution Into the RPV S, A, M, E, L 1
- e.
Emergency Ventilate Primary Containment S D, E, L 5
- f.
Parallel DIG WIth System 4KV SID Board at Panel 9-S, A, D 6
23
- g.
Off-Gas Post-Treatment Radiation HI-HI-HI S, A. 0, E, L 9
- h.
Placing Standby Steam Jet Air Ejector in Operation S,E,N 4
In-Plant Systems@ (3 for RO); (3 for 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.
Place B2-3 +/- 24V Neutron Monitoring Battery A, N 6
Charaer in Service to Battery Board 3
- k.
Bypass RCIC Low Pressure Isolation 3-EOI 0, E. EN, L.
2 ApJ)endix-16A R
AU RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SRO-II SRO-U (A)ltemate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)lrect from bank
~9/~8/~4 (E)mergency or abnormal in-plant
~1/~1J~1 (EN)gineered safety feature
- I - I ~ 1 (control room system)
(L)ow-Power I Shutdown
~1/~1/~1 (N)ew or (M)odified from bank including 1 (A)
~2/~2/~1 (P)revious 2 exams
~ 3 I ~ 3 I ~ 2 (randomly selected)
(R)CA
~1/~1/~1 (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facilily:
Browns Ferry NPP Date of Examination:
Jul~ 6 - 30, 2009 Exam Level (circle one): RO ~O;VI SRO-U Operating Test No.:
HLT 0801 Control Room Systems. (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code-Safety Function
- a.
Alternate RPV Injection - Standby Coolant S, E, EN, L, N 2
- b.
RWM Functional Test for Startup 3-SR-3.3.2.1.2 S, L, N 7
- c.
Place RCIC in Test Mode From Standby for Alternate S,A, D, E, L 3
RPV Pressure Control
- d.
Start and Inject SLC Solution Into the RPV S,A,M, E, L 1
- e.
Emergency Ventilate Primary Containment S, D, E, L 5
- f.
Parallel DIG W~h System 4KV SID Board at Panel 9-23 S, A,D 6
- g.
Off-Gas Post-Treatment Radiation HI-HI-HI S,A, D, E, L 9
- h.
Placing Standby Steam Jet Air Ejector in Operation S, E, N 4
In-Plant Systems. (3 for RO); (3 for SRO~) ; (3 or 2 for SRO-U)
- i.
Shift From 'A' Set of CRD Stabilizing Valves to 'B' Set D, E, L, R 1
- j.
Place B2-31; 24V Neutron Monitoring Battery CharQer in Service to Battery Board 3 A, N 6
- k.
Bypass RCIC Low Pressure Isolation 3-EOI 0, Eo EN, L, 2
Aooendix-16A R
All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different ufety functions; In-plant systems and functions may overtap those tested In the control room.
- Type Codes Criteria for RO I SRO-II SRO*U (A)ltemale path 4-6 I 4-6 I 2-3 (C)ontrol room (D)lrect from bank
~9/!::8 /~ 4 (E)mergency or abnormal fn-plant
~1/~1'~1 (EN)gineered safety feature
- I
- 1 ::. 1 (control room system)
(L)ow-Power I Shutdown
- ,1/::.1/::,1 (N)ew Of (M)odified from bank induding 1 (A)
~2/~2/~1 (P)revious 2 exams
.:: 3 I ! 3 I.:: 2 (randomly selected)
(R)CA
~l/!.'/::'l (S)imutator
HLT 0801 Control Room/In-Plant Systems JPM Narrative Control Room Systems:
New I Emergency or Abnormal In-Plant I Low-Power I ENgineered Safety Feature I Simulator 3-EOI Appendix-70, Alternate RPV Injection System Lineup Standby Coolant, Rev. 2 203000 RHRlLPCI: Injection Mode (Plant specific) A4.01'Ability to manually operate and/or monitor in the c(mtrolroom: Reactor Water Level IMPORTANCE:
New I Low-Power I Simulator 3-SR-3.3.2.1.2, RWM Functional Test for Startup, Rev. 3 201006 Rod Worth Minim1z8r Systert, (RWM) (Plant Specific) A2.0S Ability to (aJ predict the impacts of the following on the ROD WORTH INIMlZER SYSTEM (RWM); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations: Out of sequence rod movement: Plant.specific (Not BWR-6) IMPORTANCE: RO 3.1 SRO 3.5
Direct from bank I Emergency or Abnormal In-Plant I Low-Power I Simulator Alternate Path: RCIC Trip Throttle Valve (71-9) is tripped and must be reset and opened. RCIC Flow Controller fails while in service and candidate must take manual control 2-EOI Appendix-11 B, Alternate RPV Pressure Control Systems RCIC Test Mode, Rev. 5 241000 ReactorlTurbine Pressure Regulating System A4.02 Ability to manually operate and/or monitpr in the control room: ReactQr pressure IMPORTANCE:
Modified I Emergency or Abnormal In-Plant I Low-Power I Simulator Alternate Path: must start other pump due to no flow 2-EOI Appendix-3A, SLC Injection, Rev. 5 211000 Standby Liquid Control* A4.08 Ability to manually operate'j 'ndJor monitor in the control room: System initiation: F!lant.pecific IMPORTANCE: RO 4.2 SR04.2 HLT 0801 Control 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 3-EOI Appendix-7D. Alternate RPV Injection System Lineup Standby Coolant, Rev. 2 203000 RHRlLPCI: Injection Mode (Plant Specific) A4.07 AbIlity to manually ope'"' ancllor monitor in the control room: Reactor Water Level IIiPORT AHeE:
New I Low-Power I Simulator 3-SR-3.3.2.1.2, RWM Functional Test for Startup, Rev. 3 201006 Rod Worth lIinimizer System (RWII) (Plant Specific) A2.05 Ability to (a) predict the im.... cta of the following on the ROO WORTH IIINIMIZER SYSTEM (RWII); and (b) based on _
predictions, uae procedures to correct, control, or mitigate th. consequences of those abnormal condition. or operation.: QuI of sequence rod movement: Plant-5pecific (Not BWR~) IMPORTANCE: RO 3.1 SR03.5
Direct from bank I Emergency or Abnormal In-Plant I Low-Power I Simulator Alternate Path: RCIC Trip Throttle Valve (71-9) is tripped and must be reset and opened. RCIC Flow Controller fails while in service and candidate must take manual control 2-EOI Appendix-l1B, Alternale RPV Pressure Control Systems RCIC Test Mode, Rev. 5 241000 ReactorlTurbine Pressure Regulating System A4.02 AbIlity to manually operate and/or monitor In the control room: R.actor pressure IIiPORT AHCE:
Modified I Emergency or Abnormal In-Plant I Low-Power I Simulator Alternate Path: must start other pump due to no flow 2-EOI Appendix-3A, SLC Injection, Rev. 5 211000 Standby liquid Control A4.OS Ability to manually operate ancllor monitor in the control room: System initiation: 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 / Emergency or Abnormal In-Plant / Low-Power / Simulator 2-EOI Appendix-13, Emergency Venting Primary Containment, Rev. 6 223001 Prhllary Containment System and Auxiriarieis Ai07 Ability to (a) predict tht.impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions o,r operations: High drywell pressure.IMPORTANCE: RO 4.2 SRO 4.. 3
- f. Parallel DIG With System 4KV SID Board at Panel 9-23 (JPM 104F U2)
Direct from bank / Simulator Alternate Path: Once paralleled with offsite source, a voltage transient will occur requiring candidate to trip the output breaker 0-01-82, Standby Diesel Generator System, Rev. 99, Section 8.1 264000 Emergency Generators (OieseUJet) A4.04 Ability to manUally operate and/or monitor in the control room: Manual start, loading, and stopping of emergency generator: Plant-specific IMPORTANCE: RO 3.7 SRO 3.7
- g. Off-Gas Post-Treatment Radiation HI-HI-HI (JPM 390F U3)
Direct from bank / Emergency or Abnormal In-Plant / Low-Power / Simulator Alternate Path: Offgas System Isolation Valve, 3-FCV-66-28 fails to close automatically requiring candidate to close manually 3-ARP-9-4C, Panel 9-4 3-XA-55-4C, Rev. 29, Window 35 (Page 45 of 45) and 3-AOI-66-2, Offgas Post Treatment Radiation Hi Hi Hi, Rev. 9 271000 Offgas System A2.04 AbilitY to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to cOrrect, control, or mitigate the consequences of those abnormal conditions or operations:. Offgas system high radiation IMPORTANCE: RO 3.7 SRO 4.1
- h. Placing Standby Steam Jet Air Ejector in Operation (JPM 346 U3)
New / Emergency or Abnormal In-Plant / Simulator 3-01-66, Off-Gas System, Rev. 56, Section 8.4 239001 Main ariel Reheat S~m System A2.08 Ability to (a) predict the impac:ts aftha following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low condenser vacuum IMPORTANCE: RO 3.6 SR03.6 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. Emergency Venting Primary Containment. Rev. 6 223001 Primary Containment System and Auxiliaries A2.07 Ability to (al precllc1 the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXIUARIES; and (bl based on those predictions, u.. procedures to comtet.
control, or mitigate the consequences of those abnormal condltiona or operatlona: High drywell...... ure IMPORTANCE: RO 4.2 SRO 4.3
- f.
Parallel DIG With System 4KV SID Board at Panel 9-23 (JPM 104F U2)
Direct from bank I Simulator Alternate Path: Once paralleled with offsite source, a voltage transient will occur requiring candidate to trip the output breaker 0-01-82. Standby Diesel Generator System, Rev. 99, Section 8.1 264000 Emervency Generators (DieseVJetl A4.D4 Ability to manually operate and/or monitor in the control room: Manual start, loading, and atoppil!ll of emervency generator: Plant-specific IMPORTANCE: RO 3.7 SRO 3.7
- g. Off-Gas Post-Treatment Radiation HI-HI-HI (JPM 390F U31 Direct from bank I Emergency or Abnormal In-Plant I Low-Power I Simulator Alternate Path: Offgas System Isolation Valve, 3-FCV-66-28 fails to close automatically requiring candidate to close manually 3-ARP-9-4C. Panel 9-4 3-XA-55-4C, Rev. 29, Window 35 (Page 45 of 45) and 3-AOI-66-2. Offgas Post Treatment Radiation Hi Hi Hi, Rev. 9 271000 Offgas System A2.D4 Ability to (al predict thelmpacll of the following on the OFFGAS SYSTEM; and (bl based on those predlctlona,.... procedu.... to correct, control, or mitigate the consequences of those abnonnal conditions or operatlona: Offgaa 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 3-01-66, Off-Gas System, Rev. 56, Section 8.4 239001 Main and Reheat Steam System A2,oa Ability to (al precllc1 the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (blbased on those predictiona, u.. procedures to correct, control, or mitigate the consequences of those abnormal condltiona or operations: Low condenser vacuum IMPORTANCE: RO 3.6 SRO 3,6
HLT 0801 Control Roomlln-Plant Systems JPM Narrative In-Plant Systems:
Direct from bank I Emergency or Abnormal In-Plant I Low-Power I RCA Entry 2-01-85, Control Rod Drive System, Rev. 112, Section 6.4 201001 Control Rod Drive Hydraulic System A3.01 Ability tomorlitor automatic operations of the CONTROL ROO DRIVE HYDRAULIC SYSTEM including: Valve operation IMPORTANCE: RO 3.0 SRO 3.0
New Alternate Path: When the Battery Charger is placed in service, voltage and amps will be out-of-specification requiring candidate to open breakers and notify the Unit Supervisor 0-01-570, DC Electrical System, Rev. 121, Section 5.13 263000 D.C. Electrical Distribution K1:02 Knowledge of the physiccll connections and/or cause-effect relationships between D.C. ELECTRICAl,;;
DISTRIBUTION and the following: aattery charger and battery IMPORTANCE:
Direct from bank I Emergency or Abnormal In-Plant I Low-Power I ENgineered Safety Feature I RCA Entry 3-EOI Appendix-16A, Bypassing RCIC Low RPV Pressure Isolation Interlocks, Rev. 1 217000 Reactor Core Isolation Cooling System (RCIC) A2.03 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION C-OOUNG SYSTEM (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:. Valve closures IMPORTANCE: RO.3.4 SRO 3.3 HLT 0801 Control Room/In-Plant Systems JPM Narrative In-Plant Systems:
I. Shift From '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, Rev. 112, Section 6.4 201001 Control Rod Drive Hydraulic System Al,01 Ability to monitor a_
operations of tha CONTROL ROD DRIVE HYDRAULIC SYSTEM including: V.1v8 operation IMPORTANCE: RO 3,0 SRO 3,0 j, Place B2-3 + 24V Neutron Monitoring Battery Charger in Service to Battery Board 3 (JPM 30aF U3)
New Alternate Path: When the Battery Charger is placed in service, voltage and amps will be out-aI-specification requiring candidate to open breakers and notify the Unit Supervisor 0-01-57D, DC Electrical System, Rev. 121, Section 5.13 263000 D.C, Electrical Distribution K1,02 Knowledge oftha phyaical connactlons and/or ca.... _
relationships _n D.C, ELECTRlC~
DlSTRlBUnON and tha following: Battery charger and battery IMPORTANCE:
RO 3.2 SRO 3,3 k, Bypass RCIC Low Pressure Isolation 3-EOI Appendix-16A (JPM 323 U3)
Direct Irom bank I Emergency or Abnormal In-Plant I Low*Power I ENgineered Salety Feature I RCA Entry 3-EOI Appendix-16A, Bypassing RCIC Low RPV Pressure Isolation Interlocks, Rev. 1 217000 Reactor Core Isolation Cooling Syatem (RCIC) A2,03 Ability to (a) (INdict th. lmpacts of tha following on tha REACTOR CORE ISOLAnON COOUNG SYSTEM (RCIC); and (b) baaed on _
predictions,.... procedures to correct, control, or mltigata tha consequences of those abnormal conditions or operations: Valve closures IMPORTANCE: RO 3,4 SRO 3.3
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30, 2009 Exam Level (circle one): RO 4RD;i), SRO-U Operating Test No.:
HlT 0801 Control Room Systems@! (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function
- a.
Start and Inject SLC Solution Into the RPV S, A, M, E, L 1
- b.
Alternate RPV Injection - Standby Coolant S, E,EN,L, N 2
- c.
Place RCIC in Test Mode From Standby for Alternate S,A, D, E, L 3
RPV Pressure Control
- d.
Placing Standby Steam Jet Air Ejector in Operation S,E, N 4
- e.
Emergency Ventilate Primary Containment S, D, E, L 5
- f.
Parallel DIG With System 4KV SID Board at Panel 9-S, A,D 6
23
- g.
RWM Functional Test for Startup 3-SR-3.3.2.1.2 S,L,N 7
- h.
Off-Gas Post-Treatment Radiation HI-HI-HI S, A, D,E,L 9
In-Plant Systems@ (3 for RO); (3 for 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.
Bypass RCIC Low Pressure Isolation 3-EOI D. E, EN, L, 2
Aj)p~ndix-16A R
- k.
Place B2-3 +/- 24V Neutron Monitoring Battery A,N 6
Charaer in Service to Battery Board 3 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 I 4*6 I 2*3 (C)ontrol room (D)irect. from bank
~9/~8/~ 4 (E)mergency or abnormal in-plant
?1/?1/?1 (EN)gineered safety feature
- I - I ? 1 (control room system)
(L)ow-Power I Shutdown
?1/?1/.?1 (N)ew or (M)odffied from bank including 1 (A)
?2/.?2/.?1 (P)revious 2 exams
~ 3 I ~ 3 I ~ 2 (randomly selected)
(R)CA
.?1 1=:1 1=:1 (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES*301*2 Facility:
Browns Ferry NPP Date of Examination:
July 6 - 30. 2009 Exam Level (circle one): RO ~Ro-]H SRO-U Operating Test No.:
HLT 0801 Control Room Systems. (8 for RO): (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code-Safety Function
- a.
Start and Inject SLC Solution Into the RPV S,A, M, E, L 1
- b.
Attemate RPV Injection - Standby Coolant S. E, EN. L. N 2
- c.
Place RCIC in Test Mode From Standby for Attemate S,A. D. E. L 3
RPV Pressure Control
- d.
Placing Standby Steam Jet Air Ejector in Operation S, E, N 4
- e.
Emergency Ventilate Primary Containment S, D. E.L 5
- f.
Parallel DIG Wfth System 4KV SID Board at Panel 9-S. A,D 6
23
- g.
RWM Functional Test for Startup 3-SR-3.3.2.1.2 S, L. N 7
- h.
Off-Gas Post-Treatment Radiation HI-HI-HI S. A, D, E, L 9
In-Plant Systems. (3 for RO); (3 for SRO~) ; (3 or 2 for SRO-U)
- i.
Shift From 'A' Set of CRD Stabilizing Valves to 'B' Set D. E, L, R 1
I Bypass RCIC Low Pressure Isolation 3-EOI D. E, EN, L.
2 Aooendix-16A R
- k.
Place B2-3 +/- 24V Neutron Monftoring Battery A, N 6
Chamer in Service to Batterv Board 3 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; aU 5 SRO*U systems must serve different safety functions; In-plant systems and functions may overlap those tested In the control room.
- Type Codes Criteria for RO I SRO-l f SRO-U (A)I/emale path 4-6 I 4-6 I 2*3 (C)onlra! room (D)irect from bank
- 91:! 8 /:: 4 (E)mergency or abnormal in..planl
~1/~1/~1 (EN)gineered safety feature
- I
- I ~ 1 (control room system)
(l )ow*Power I Shutdown
~1/!, 1
!!. 1 (N)ew or (M)odified from bank Induding 1 (A)
!.21 !.2!!.1 (P)revious 2 exams
~ 3 J ~ 3 I ~ 2 (randomly selected)
(R)CA
!,1 1=:1 I!. l (S)imulator
HLT 0801 Control Room/In-Plant Systems JPM Narrative Control Room Systems:
Modified / Emergency or Abnormal In-Plant / Low-Power / Simulator Alternate Path: must start other pump due to no flow 2-EOI Appendix-3A, SLC Injection, Rev. 5 211000 Standby Liquid Control A4.08 Ability to manually oPerate _ndlor monitor in the control room: System initiation: Plant..specific IMPORTANCE: RO... 2 SRO 4.2
New / Emergency or Abnormal In-Plant / Low-Power / ENgineered Safety Feature / Simulator 3-EOI Appendix-70, Alternate RPV Injection System Lineup Standby Coolant, Rev. 2 203000 RHRIlPCI: InjeCtion Mode (Plclnt Specific) A4.07 Ability to manually operate andlor monitor in the control room;' ReactQr Water Level IMpORTANCE:
Direct from bank / Emergency or Abnormal In-Plant / Low-Power / Simulator Alternate Path: RCIC Trip Throttle Valve (71-9) is tripped and must be reset and opened. RCIC Flow Controller fails while in service and candidate must take manual control 2-EOI Appendix-11 B, Alternate RPV Pressure Control Systems RCIC Test Mode, Rev. 5 241000 ReactOrfTurbine Pressure Regulating System A4.02 Ability to manually operate andlor monitor in the control room: Reactorpressure IMPORTANCE:
RO 4.1SRO 4.1
- d. Placing Standby Steam Jet Air Ejector in Operation (JPM 346 U3)
New / Emergency or Abnormal In-Plant / Simulator 3-01-66, Off-Gas System, Rev. 56, Section 8.4 239001 Main and Reheat Steam System A2.08 Ability to (a) predict the impac of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b),based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Qr operations: Low cOlld.. nser vacuum, IMPORTANCE:,RO 3.6 SRO 3.6 HLT 0801 Control Roomlln-Plant Systems JPM Narrative Control Room Systems:
Modified I Emergency or Abnormal In-Plant I Low-Power I Simulator Alternate Path: must start other pump due to no flow 2-EOI Appendix-3A, SLC Injection, Rev. 5 211000 Standby Liquid Control M.OB Ability to manually operata and/or monitof in the controt room: System Initiation: Plant.. peclfle IMPORTANCE: RO 4.2 SR04.2
New I Emergency or Abnormal In-Plant I Low-Power I ENgineered Safety Feature I Simulator 3-EOI Appendix-70, Alternate RPV Injection System Lineup Standby Coolant, Rev. 2 203000 RHRlLPCI: Injection Mode (Plant Speclfle) M.07 Ability to manually operata andlor monitof In the control room: Reactor Water Level IMPORTANCE:
Direct from bank I Emergency or Abnormal In-Plant I Low-Power I Simulator Alternate Path: RCIC Trip Throttle Valve (71-9) is tripped and must be reset and opened. RCIC Flow Controller fails while in service and candidate must take manual control 2-EOI Appendix-11 B, Alternate RPV Pressure Control Systems RCIC Test Mode, Rev. 5 241000 ReactorfTurblne Pressure Regulating Syatam M,02 Ability to man.... 1y operata andlor monitof in the control room: Reactor 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. 56, Section 8.4 239001 Main and Reheat Steam System A2.08 Ability to (al predict the Impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on th.... predictions, use proceduras to correct, control, or mitigate the consequences 01 th.... abnormal conditions or operations: Low condenser vacuum IMPORTANCE: RO 3.6 SRO 3.6
HLT 0801 Control Roomlln-Plant Systems JPM Narrative
- e. Emergency Ventilate Primary Containment (JPM 55 U2)
Direct from bank / Emergency or Abnormal In-Plant / Low-Power / Simulator 2-EOI Appendix-13, Emergency Venting Primary Containment, Rev. 6 223001 Primary Containment System and Auxiliaries A2.07 Ability to (a) prediCt the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions. use procedures to correct, control. or mitigate the consequences of those abnonnal conditions or operations: High drywell p~ure IMPORTANCE: RO 4.2 $RO 4.3
- f. Parallel DIG With System 4KV SID Board at Panel 9-23 (JPM 104F U2)
Direct from bank / Simulator Alternate Path: Once paralleled with offsite source, a voltage transient will occur requiring candidate to trip the output breaker 0-01-82, Standby Diesel Generator System, Rev. 99, Section 8.1 264000 Emergency Generators (OieseUJet) A4.04 Ability to'manually operate and/or monitor in the control room: Manual start. loading. and stopping of emergency'generator:Plant-specific IMPORTANCE: RO 3.7 SRO 3.7
New / Low-Power / Simulator 3-SR-3.3.2.1.2, RWM Functional Test for Startup, Rev. 3 201006 ROd Worth Minimizer System (RWM) (Plant Specific) A2.0S Ability to (a) predict the impacts of the following on the ROD WORTH MINIMIZER SYSTEM (RWM); and (b) based on those predictions. use procedures to correct, control.
or mitigate the consequences of those abnonnal conditions or operations: Out of sequence rod moveme"t: Plant-Specific (Not BWR-6) IMPORTANCE: RO 3.1 SRO 3.5
- h. Off-Gas Post-Treatment Radiation HI-HI-HI (JPM 390F U3)
Direct from bank / Emergency or Abnormal In-Plant / Low-Power / Simulator Alternate Path: Offgas System Isolation Valve, 3-FCV-66-28 fails to close automatically requiring candidate to close manually 3-ARP-9-4C, Panel 9-4 3-XA-55-4C, Rev. 29, Window 35 (Page 45 of 45) and 3-AOI-66-2, Offgas Post Treatment Radiation Hi Hi Hi, Rev. 9 271000 Offgas System Ai04 Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions. use procedures to correct, control. or mitigate the consequences of those abnonnal conditions or operations: Offgas system high radi~on IMPORTANCE:RO 3.7 SRO 4.1 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-Planl l Low-Power I Simulator 2-EOI Appendix-13, Emergency Venting Primary Containment, Rev. 6 223001 Primary Containment System and Auxiliaries A2.07 Ability to (a) predict the impacte of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXIUARlES; and (b) baaed on those predictio.... use procedu.... to ~
control, or mitigate the consequences of those abnormal conditions or operations: High drywall pressure IMPORTANCE: RO 4.2 SRO 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 source, a voltage transient will I,},\\, /
occur requiring candidate to trip the output breaker K'
,~.,
0-01-82, Standby Diesel Generator System, Rev. 99, Section 8.1 264000 Emergency Generators (DIeseUJet) M,04 Ability to manually operate andlor monitor In the control room: Manual start, loading. and stopping of emergency generator: Plant-specific IMPORTANCE: RO 3,7 SRO 3.7
New I Low-Power I Simulator 3-SR-3.3.2.1.2, RWM Functional Test for Startup, Rev. 3 201006 Rod Worth Minimizer System (RWM) (Plant Specific) A2.OS Ability to (a' predict the Impacte of the following on the ROD WORTH MINIMIZER SYSTEM (RWM); and (b) baaed on those predictions..... procedu.... to col1'8c1, control.
or mitigate the consequences of those abnonnal conditions or operstio... : Out of sequence rod movement: Plant-5peciflc (Not BWR-6) IMPORTANCE: RO 3.1 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 Alternate Path: Ollgas System Isolation Valve, 3-FCV-66-28 fails to close automatically requiring candidate to close manually 3-ARP-9-4C, Panel 9-4 3-XA-55-4C, Rev. 29, Window 35 (Page 45 of 45) and 3-AOI-66-2, Ollgas Post Treatment Radiation Hi Hi Hi, Rev. 9 271000 Offgaa System A2.04 Ability to (a) predict the Impacte of the following on the OFFGAS SYSTEM; and (b) baaed on those prediction.. usa procedu.... to correct, control. or mltlgal8 the consequences of those abnormal conditions or operations: Offgaa system high radiation IMPORTANCE: RO 3.7 SRO 4.1
HLT 0801 Control Roomlln-Plant Systems JPM Narrative In-Plant Systems:
r "' ~
I" r"'~ ~ l~~-
f;
,Lw... h-l k~
Direct from bank / Emergency or Abnormal In-Plant / Low-Power / RCA Entry 2-01-85, Control Rod Drive System, Rev. 112, Section 6.4 201001 Control Rod Drive Hydraulic System A3.01 Ability to monitor automatic operations of the CONTROL ROD DRIVE HYDRAUUC SYSTEM including: Valve operation IMPORTANCE: RO 3.0 SRO 3.0
Direct from bank / Emergency or Abnormal In-Plant / Low-Power / ENgineered Safety Feature I RCA Entry 3-EOI Appendix-16A, Bypassing RCIC Low RPV Pressure Isolation Interlocks, Rev. 1 217000 Reactor Core Isolation Cooling System (RCIC) A2.03 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLA nON COOUNG SYSTEM (RCIC); and (b) based on those predictions. use procedures to correct, control, or mitigate the consequences of those abnormal conditions Or operations: Valve closures IMPO.RT ANCI;: RO 3.4 SRO 3.3
New Alternate Path: When the Battery Charger is placed in service, voltage and amps will be out-of-specification requiring candidate to open breakers and notify the Unit Supervisor 0-01-570, DC Electrical System, Rev. 121, Section 5.13 263000 D.C. ElectriCal Distribution K1.02 Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUnON and the following: Battery charger and battery IMPORTANCE:
RO 3.2 SRO 3.3 HLT 0801 Control Room/In-Plant Systems JPM Narrative In*Plant Systems:
~.;., ; I-'t-i
\\,.J, '- r~ _ L
Direct from bank I Emergency or Abnormal In* Plant I Low*Power I RCA Entry 2*01*85, Control Rod Drive System, Rev. 112, Section 6.4 201001 Control Rod Drive Hydraulic System A3.01 AbIlity to monito< aulom8tlc operatiO"" 01 tho CONTROL ROD DRIVE HYDRAULIC SYSTEM Inctudlng: ValYe operation IMPORTANCE: RO 3.0 SRO 3.0
Direct from bank I Emergency or Abnormalln*Plant I Low*Power I ENgineered Safety Feature I RCA Entry 3*EOI Appendix-16A, Bypassing RCIC Low RPV Pressure Isolation Interlocks, Rev. 1 217000 Reactor Core Isolation Cooling Syotem (RCtCl A2.03 AbIlity to (al pradlc1 the Impacts 01 tholollowlng on tho REACTOR CORE ISOLA nON COOLING SYSTEM (RCICI; and (bl based on those predictions, use procedu.... to correct, control, or mitigate tho consequences of those abnonnal conditiO"" 0<
operations: Valve closu.... IMPORTANCE: RO 3.4 SRO 3.3
New Alternate Path: When the Battery Charger is placed in service, voltage and amps will be out*ol*specification requiring candidate to open breakers and notify the Unit Supervisor 0*01*57D, DC Electrical System, Rev. 121, Section 5.13 263000 D.C. Electrical Distribution Kl.02 Knowledge 01 the phyolcal connections Indio< cause-elfect relationships _
D.C. ELECTRICAL DISTRISUnON and thololl_ing: Sallery charger and _ry IMPORTANCE:
- ~r;~~~:r: ~~~:~~
- !~!i::
'~t: ff
~.... *~.0 : \\.,. ~ '~'::.,.~~
ES-401 1
Form ES-401-1 Facility:
Browns Ferry NPP Date of Exam:
July 06 - 30, 2009 RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
1 2
3 4
5 6
1 2
3 4
Total P\\2 G+
Total
- 1.
1 4
3 4
3 2
4 20 4
3 7
Emergency 2
2 1
1 1
1 1
7 2
1 3
Abnormal N/A N/A Plant Tier 6
4 5
4 3
5 27 6
4 10 Evolutions Totals 1
4 2
3 2
2 3
2 2
2 2
2 28 3
2 5
- 2.
2 2
1 1
1 1
1 1
1 1
1 1
12 0
2 1
3 Plant Systems Tier 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 10 7
Abilities Categories 2
2 3
3 2
2 2
1 Notes:
- 1.
Ensure that at least two topics from every KIA category are sampled within each t.ier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline. the "TIer Totals" in each KIA category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions 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/evolutions that are not included on the outline should be 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; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those 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.
7."
The generic (G) 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 for the applicable KlAs.
B.
On the following pages, enter the KIA numbers, a brief description of each topiC, the topics' importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
ES-401 1
Form ES-401-1 Facimy:
Browns Ferry NPP Date of Exam:
July 06 - 30. 2009 RO KiA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
1 2
3 4
5 6
1 2
3 4 -
Total A2 G*
Total
- 1.
1 4
3 4
3 2
4 20 4
3 7
Emergency 2
2 1
1 1
1 1
7 2
1 3
Abnormal NfA NfA Plant Tie' 6
4 5
4 3
5 27 6
4 10 Evolutions Totals 1
4 2
3 2
2 3
2 2
2 2
2 28 3
2 5
- 2.
2 2
1 1
1 1
1 1
1 1
1 1
12 0
2 1
3 Plant Systems Tie' 3
3 3
3 3
3 3
3 38 Totals 6
4 4
5 3
8
- 3. Generic Knowledge and 1
2 3
4 1
2 3
4 10 7
Abilities Categories 2
2 3
3 2
2 2
1 Notes:
- 1.
Ensure that at least two topics from every KJA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the *Tier Totals* in each KiA 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 table based on NRC reviSions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facitity should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be 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: sample every system or evolution In the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority. only those 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.
7 "
The generic (G) t<JAs 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 for the applicable KlAs.
- 6.
On the following pages, enter the KIA numbers. a brief description of each topic, the topics' importance ratIngs (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the t<JA numbers, descnptions, IRs, and point totals (#) on Form ES-401*3. limit SRO selections to t<JAs that are linked to 10 CFR 55.43.
IC.c.':/ /. a
0 (1.1'--
Form ES~o1 -1 ES-401 BWR Examination Outline Fonn ES-401-1 Emergency and Abnonnal Plant Evolutions - Tier 1/Group 1 (RO I SRO)
ElAPE # / Name / Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
295001 Partial or Complete Loss of Forced 1
AA1.02 (10CFR 55.41.7)
Core Flow Circulation I 1 & 4 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
3.3 1
1 AK1.03 (10CFR 55.41.8)
Knowledge of the operational implications of the following concepts as they 2.9 2
apply to PARTIAL OR COMPLETE LOSS OF AC POWER:
- Under voltage / 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 /6 1
AK3.02 (10CFR 55.41.5)
Knowledge of the reasons for the following responses as they apply to PARTIAL 2.9 3
- Ground isolation / fault determination 295005 Main Turbine Generator Trip I 3 1. G2.4.21 (10CFR 55.41.7)
Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor 4.0 4
coolant system integrity, containment conditions, radioactivity release control, etc.
295006 SCRAM I 1 1
. AK2.02 (10CFR 55.41.7)
Knowledge of the interrelations between SCRAM and the following:
3.8 5
:=-~
~~
" II!
()
0 2
~----------------------------~F-onn
--=
ES~
-40~l~
.l~----
ES-401 BWR Examination Outline form ES-401 -1 Emergency and Abnormal Plant evolutions - Tier 1{Group 1 (RO I SRO)
ElAPE # I Name' Safety Function K
K K
A
- a KJA Topic(s)
I.
1 2
3 1
2 295001 Partial or Complete Loss of Forced 1
AA1.02 (10CFR 55.41.7)
Core Flow Circulation { 1 & 4 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
3.3 1
1 AK1.03 (10CFR 55.41.8)
Knowledge of the operational implications of the fol1owing concepts as they 2.9 2
apply to PARTIAL OR COMPLETE LOSS OF AC POWER:
- 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 1
AK3.02 (10CFR 55.4 1.5)
Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF DC POWER:
2.9 3
- Ground isolation I fault determination 295005 Main Turbine Generator Trip 13 1
G2.4.21 (10CFR 55.41.7)
Knowledge of the parameters and logic used to assess the status of safety functions, such 'as reactivity control, core cooling and heat removal, reactor 4.0 4
coolant system integrity, containment conditions, radioactivity release control,
- etc, 295006 SCRAM /1 1
AK2.02 (10CFR 55.41.7)
Knowledge of the interrelations between SCRAM and the following:
3.8 5
- 2.
Fonn Esl-.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 2.7 6
internal organizations or external agencies, such as the State, the NRC, or the 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 3.3 7
COMPLETE LOSS OF COMPONENT COOLING WATER:
- 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 3.5 8
INSTRUMENT AIR and the following:
- 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-40-1-tt------------------------2tt Fonn ESt-.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 2.7 6
internal organizations or external agencies, such as the State, the NRC, or the 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 3.3 7
COMPLETE LOSS OF COMPONENT COOLING WATER:
- 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 3.5 8
INSTRUMENT AIR and the following:
- 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 0 2
o~
J-'----------------.:F~O;;rm~E:s:
S_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#
1 2
3 1
2 295023 Refueling Ace I 8 1 1 AA1.04 (10CFR 55.41.7)
Ability to operate andlor monitor the following as they apply to REFUELING 3.4 10 ACCIDENTS:
- Radiation monitoring equipment AA2.01 (10CFR 55.43.5 - SRO Only)
Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS:
4.0 79 I
- Area radiation levels I
295024 High Drywell Pressure I 5 1
EA2.03 (10CFR 55.41.10)
Ability to determine andlor interpret the following as they apply to HIGH 3.B 11 DRYWELL PRESSURE:
- Suppression pool level 295025 High Reactor Pressure I 3 1
1 EK2.04 (10CFR 55.41.7)
Knowledge of the interrelations between HIGH REACTOR PRESSURE and the 3.9 12 following:
- ARJlRPT/ATWS: Plant-Specific EA2.01 (10CFR 55.43.5 - SRO Only)
Ability to determine and/or interpret the fol/owing as they apply to HIGH 4.3 80 REACTOR PRESSURE:
- Reactor pressure 295026 Suppression Pool High Water 1
EK3.02 (10CFR 55.41.5)
Dl:talls, Recol"O.A Rej('r:l~d K'A....
- Temp. 15 Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:
3.9 13
- Suppression pool cooling 2960~ 1oI1g" GaAleiAmeA' :fempe,..,. Iii N/A for BFN - KIA for Mark III Containments ONL Y SRO only KjAs shown in italics 4/9/2009 - 11 :06: 18 AM Page 4
~E~S~4~071 ~<:>~~--------------------------------~2'"
o Form ES40!1'!1"-I,-------
ES-401 BWR Examrnatlon Outline Form ES--401*'
Emergency and Abnormal Plant Evolutions - Tier 1IGfCUp 1 IRQ I SRO)
ElAPE' / Name I Safety Function K
K K *
- G KIA Toplc(a)
I.
, 2 3
I 2
295023 Refueling AI:;c 18 1 1 AA1.04 (10CFR 55.41.7)
Ability to operate and/or monitor the following as they apply to REFUELING 3.4 10 ACCIDENTS:
- Radiation monitoring equipment AA2.0f (fOCFR 55.43.5 - SRO Only)
Ability to determine andlor interpret the following as they apply to REFUELING ACCIDENTS:
4.0 79
- Area radiation levels 295024 High Drywell Pressure 15 1
EA2.03 (10CFR 55.41.10)
Ability to determine andlor interpret the following as they apply to HIGH 3.8 11 DRYWELL PRESSURE:
- Suppression pool level 295025 Hrgh Reactor Pressure 13 1
1 EK2.04 (10CFR 55.41.7)
Knowledge of the interrelations between HIGH REACTOR PRESSURE and the 3.9 12 following:
- ARIfRPTIA1WS: Planl-Specific EA2.0f (fDCFR 55.43.5 - SRO Only)
Ability to determine and/or interpret the foflowing 8S they apply to HIGH REACTOR PRESSURE:
4.3 80
- Reactor pressure 295026 Supplesslon Pool High Water 1
EK3.02 (10CFR 55.41.5) - 'tleirllt "R~ ret 01 ReJ&!Pd KJA Temp, ' 5 Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:
3.9 13
- Suppression pool cooling
~
Ulitl CelI.IMlIAt 'fepi,' FMIIi.., I NIA for BFN - KIA for Mail< III Containments ONLY SRO only K/ As shown in itJIlics 4/9/2009 - 11:06:18 AM Page 4
--e e
e--
ES-401 2
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 3.5 14 apply to HIGH DRYWELL TEMPERATURE:
- 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 3.6 15 SUPPRESSION POOL WATER LEVEL:
- 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 4.2 16 LOW WATER LEVEL:
- Reactor pressure 295037 SCRAM Condition Present and 1 G2.2.12 (10CFR 55.41.10)
Power Above APRM Downscale or Knowledge of surveillance procedures.
3.7 17 Unknown / 1 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 2.8 18 apply to HIGH OFF-SITE RELEASE RATE:
- MeteorolQgical ~ffegs QD ~ff-~ite release SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 5
--e-----------e-----------e--
ES-401 2
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 3.5 14 apply to HIGH DRYWELL TEMPERATURE:
- 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 3.6 15 SUPPRESSION POOL WATER LEVEL:
- 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 4.2 16 LOW WATER LEVEL:
- Reactor pressure 295037 SCRAM Condition Present and 1 G2.2.12 (10CFR 55.41.10)
Power Above APRM Downscale or Knowledge of surveillance procedures.
3.7 17 Unknown / 1 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 2.8 18 apply to HIGH OFF-SITE RELEASE RATE:
- Meteorological effects on off-site release SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 5
ES-401 0 20
(
Form ES-401-1 ES-401 BWR Examlnalion OuUfne Emergency and Abnormal Plant Evolulions - Tier 1/Group 1 (RO I SRO)
Form ES-401 *1 I
ElAPE # I Name I Safety Function K
K K
A A
G KIA Toplc(s)
IR 1
2 3
1 2
600000 Plant Fire On Sile J 8 1
AK3.04 (10CFR 55.41.5)
I Knowledge of the reasons for the following responses as they apply to PLANT 2.8 19 FIRE ON SITE:
I
- Actions contained in the abnormal procedure for plant fire on site 700000 Generator Voltage and Electric Grid 1
1 AK1.01 (10CFR 55.41.5)
I Disturbances 16 Knowledge of the operational implications of the following concepts as they 3.3 20 apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:
I
- Definition of terms: volts, watts, amps, VARs, power factor G2.4.31 (10CFR 55.43.5 - SRO Only) 4.1 82 I
Knowledge of annunciator alarms, indications, or response procedures.
KIA Category Tolals: (RO) 4 3 4 3 2 4 Group Point Total: (RO) 20 KIA C8tegory Totals: (SRO) 4 3 Group Point Tot81: (SRO) 7 SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 6
-=-=-=,---e '---------------------=e -------------=------=""'Ol"--c--
ES-401 2
Form ES-401*1 ES~Ol BWR Examination Outline Form ES-40H Emergency and Abnormal Plant Evolutions - Tter lIGroup 1 (RO I SRO)
EJAPE. 1 Name I Safety Function K
K K
A
- G KIA Toplc(s)
I.
1 2
3 1
2 600000 Plant FIIS On Srte / a 1
AK3.04 (10CFR 55.41.5)
Knowledge of the reasons for the following responses as they apply to PLANT 2.8 19 FIRE ON SITE:
- Actions contained in the abnormal procedure for plant fire on sile 100000 Generator Voltage and Electric Grid 1
1 AK1.01 (10CFR 55.41.5)
Disturbances 16 Knowledge of the operational implications of the following concepts as they apply 10 GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:
3.3 20
- Definition of terms: volts. watts, amps, VARs, power factor GZ.4.31 (10CFR 55.43.5
- SRO Only) 4.1 82
. 0" KJA Category Totals; (ROJ 4 3 4 3 2 4 Gmup Point Total' (RO) 20 KIA CBlegory T0/81s" (SRO) 4 3 Group Point TOfel: (SRO) 7 SRO only Kj As shown in italics 4/9/2009*11:06:18 AM Page 6
o o~
'.~
3~ -
Form ES-401-1 ES-401 ES-401 BWR Examination Outline Fonn ES-401-1 Emergency and Abnonnal Plant Evolutions - Tier llGroup 2 (RO I SRO)
ElAPE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
39iOO3 bOIl 8' Main COAd'RlleF ~o # 3 NOT RANDOMLY SELECTED 391iOO~ High Re8a&oF Pfeil. life J 3 NOT RANDOMLY SELECTED---
39&008 High Re8a&aF wat.f b8'J8I $ 3 NOT RANDOML Y SELECTED 295009 Low Reactor Waler Levell 2 1
AK2.04 (10CFR 55.41.7)
Knowledge of the interrelations between LOW REACTOR WATER LEVEL and 2.6 21 the following:
- Reactor water cleanup 295010 High Drywell Pressure 15 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.
395011 High Contain",.*,,' :felllil # Ii N/A for BFN - KJA for Mark III Containments ONL Y 295012 High Drywall Temperature I 5 1
1 AK1.01 (10CFR 55.41.9)
Knowledge of the operational implications of the following concepts as they 3.3 23 apply to HIGH DRYWELL TEMPERATURE:
- Pressure I temperature relationship G2.4.34 (10CFR 55.43.5 - SRO Only) 4.1 83 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
295013 High Suppression Pool Temp. 15 1
AA2.02 (10 CFR 55.43.5 - SRO Only)
Ability to determine and/or interpret the following as they apply to HIGH 3.5 84 SUPPRESSION POOL TEMPERATURE:
- Localized heating / stratification 391CU 4 l"IMlten' R.aa&~ Addition! 1 NOT RANDOML Y SELECTED SRO only K/ As shown in italics 4/9/2009 - 11 :06: 18 AM Page 7
~~"~------------------~3tt~----------------~-="~~---
ES-401 Fonn ES~ -1 ES-401 BWR Examination OUUine Form ES-401-1 Emergency 800 Abnormal Plant Evolution, - Tter IlGtoup 2 (RO I SRO)
ElAPE./ Name I Safety Functlon K
K K
- A G
KIA Toplc(s)
I.
1 2
l 1
2
_003 LoMe If MilA GIAII.A.. t 1j.ao#3 NOT RANDOMLY SELECTED 20i001 HII*' ~ ***, PAM'IIM! a NOT RANDOMLY SELECTED-a8iOOl Nilh R ** oter tNellf bawl' a NOT RANDOMLY SELECTED 295009 Low Reador Water Level / 2 1
AK2.04 (10CFR 55.41.7)
Knowledge of the interrelations between lOW REACTOR WATER lEVEL and 2.6 21 the following:
- Reactor water cleanup 295010 High Dryweli Pressure 15 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..... "1 TaM" J,
N/A for BFN - t<JA for Marl< III Containments ONLY 295012 High Drywe" Temperature / S 1
1 AK1.01 (10CFR 55.41.9)
Knowledge of the operational implications of the following concepts as they 3.3 23 apply to HIGH DRYWELL TEMPERATURE:
- Pressure I temperature relationship G2.4.34 (fOCFR 55.43.5 - SRO Only) 4.1 83 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
295013 High Suppr1!ssion Pool Temp. I 5 1
AA2.02 (fO CFR 55.43.5 - SRO Only)
Ability to determine and/Or interpret the (0110 wing as they apply to HIGH 3.5 84 SUPPRESSION POOL TEMPERA TURE:
- Localized heating / stratification ae601 ~ IAaM_At R'I8I~o"ity A4'ill,,,! 1 NOT RANDOMLY SELECTED SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 7
'---------------"0.0 0 -
3 Form ES-401-1 ES-401 BWR examination Ouliine Form ES-401-1 Emergency and Abnormal Plant Evolutions - TIer 1/Group 2 (RO / SRO)
ElAPE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
0!95OHi IAeMlpl.,. S~RAM
~ ~
NOT RANDOML Y SELECTED~
295017 Hi9h Off-site Release Rate I 9 1
AK3.03 (10CFR 55.41.5)
Knowledge of the reasons for the following responses as they apply to HIGH 3.3 24 OFF-SITE RELEASE RATE:
- Implementation of the site emergency plan
AA2.03 (10CFR 55.41.10)
Ability to determine and/or interpret the following as they apply to LOSS OF CRD 3.1 25 PUMPS:
- CRD mechanism temperatures 295029 High Suppression Pool WI, Lvi i 5 1
EA1.04 (10CFR 55.41.7)
Ability to operate and/or monitor the following as they apply to HIGH 3.4 26 SUPPRESSION POOL WATER LEVEL:
- RCIC: Plant-Specific
- !85030! Wig'" SleaA"a!}' CSA,-iAAMlA' NOT RANDOML Y SELECTED ARIa +MlpeF8'"RI ~ 5 295033 High Secondary Containment 1
EA2.03 (10 CFR 55.43.5 - SRO Only)
Area Radiation Levels I 9 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIA TION LEVELS:
4.2 85
- Cause of high area radiation 2950"34 SeeeA"aFy COAlaiARIeAt NOT RANDOMLY SELECTED VlAlliMleR wig'" RHlalieA ~ "
0!9iQ35 SIGOA"IIY CeA'-iARIeRt Willi NOT RANDOMLY SELECTED gMfilAlAllal PAIl...,. ! i SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 8
~*----------~3-0----------~O~
ES-401 Form ES-401-1 ES-.401 BWR Examination OUillne Form ES-401-,
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RD I SRO)
ElAPE ", Name I Safety Function K
K K
A
- G KIA Topic(.)
I.
I 1
2 3
1 2
- aNOli 1"$MIple" StRMA! I NOT RANDOMLY SELECTED 295017 High Off-s~e Release Rate 19 1
AK3.03 (10CFR 55.41.5)
Knowledge of the reasons for the following responses as they apply to HIGH 3.3 24 OFF-SITE RELEASE RATE:
- Implementation of the site emergency plan Moao IA,\\h.fteAI GeR', lIel.tl8A I I & 7 NOT RANDOMLY SELECTED 295022 loss of CRD Pumps I 1 1
AA2.03 (10CFR 55.41.10)
Ability to determine and/or interpret the following as they apply to lOSS OF CRD 3.1 25 PUMPS:
- CRD mechanism temperatures 295029 High Suppression Pool Wtf Lvl 15 1
EA1.D4 (10CFR 55.41.7)
Abitity to operate andlor monitor the following as they apply to HIGH 3.4 26 SUPPRESSION POOL WATER LEVEL:
- Rete: Plant*Specific
~iOa:a Hitll S'IiIU.~ C8flWlfWMAt AM. TM'Ip.RlIu,. I,
NOT RANDOMLY SELECTED 295033 High Secondary Containment 1
EA2.03 (1 0 CFR 55.43.5 - SRO Only)
Area Radiation LevelS J 9 Ability to detennine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIA T/ON LEVELS:
4.2 85
- Cause of high area radiation 28IOa4 S,GII".a')' CeIIl.I""'IAI V."IIIIIiGfl Hllh RlI1II.&ieA ~ Q NOT RANDOMLY SELECTED
- lQiOal s.U".. ')'GIIA...... "1 Hit'"
gllll'lMlal Pi'll' "1'1 "
NOT RANDOMLY SELECTED SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 8
,0 rJ
{)p.----
ES-401 3
Form ES-401-1 ES-401 BWR Examlnallon OUIline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier lIGroup 2 (RO I SRO)
ElAPE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR II 1
2 3
1 2
295036 Secondary Containment High 1
EK1.01 (10CFR 55.41.10)
Sump/Area Water Levell 5 Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL:
2.9 27
- Radiation releases iOOOOQ High Gml HyaFeg8R GaRB. ~ i NOT RANDOMLY SELECTED KiA Category Totals: (RO) 2 1 1 1 1 1 Group Point Tota.l: (RO) 7 KIA Category Totals: (SRO) 2 1 Group Point Total: (SRO) 3 SRO only K/ As shown in italics 4/9/2009 - 11 :06: 18 AM Page 9 0
~E~S-4~07 1 ~ --------------------------------~
3
~--------------------------~F-Onn
--~
ES~
40~
1-71-------
ES.,.Ol BWR Elamlnatlon Ollliine Form ES~Ol* '
Emergency and Abnormal Plant Eyolutions - TlElf
'<RO I SRO)
E1APE'/ Name I Safety Function K
K K
A
- G KIA Toplc{s)
IR 1, 3 1,
295036 Secondary Containment High 1
EK1.01 (10CFR 55.41.10)
Sump/Area Water l evel J 5 Knowledge of the operational implications of the following concepts as they apply 10 SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL:
2.9 27
- Radiation releases iOOOOO HII~ I;:n.Q: ~fll'R GlHto, ~ i NOT RANDOMLY SELECTED
-~..
KIA Category Totals: (RO) 2 1 1 1 1 1 Group PoInITola]; (RO) 7 KIA Cetsgol)' TOials: (SRO) 2 1 Group PoInt Toral: (SRO) 3 SRO only K/ As shown in Italics 4/9/2009 - 11:06:18 AM Page 9
ES-401 40 FonnESQ-"1--1----
ES-401 BWR Examination Outline Form ES-4Dl-1 Plant Systems - Tier 21Group 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 203000 RHRlLPCI: Injection 1
K5.02 (10CFR 55.41.5) '*Details In Record of Rejected K/As**
Mode Knowledge of the operational implications of the following concepts as 3.5 28 they apply to RHR / LPCI: INJECTION MODE (PLANT SPECIFIC):
- Core cooling methods 205000 Shutdown Cooling 1
1 K2.02 (1 OCFR 55.41.7)
Knowledge of electrical power supplies to the following:
2.5 29
- Motor operated valves A4.03 (10CFR 55.41.7) **Details in Record of Rejected K/As u
Ability to manually operate and/or monitor in the control room:
3.6 30
1 K4.03 (10CFR 55.41.7) **Oetails in Record of Rejecte(i K/AsH Knowledge of HIGH PRESSURE COOLANT INJECTION (HPCI)
SYSTEM design feature(s) and/or interlocks which provide for the 4.2 31 following:
- Resetting turbine trips: BWR-2,3,4 A2.16 (10CFR 55.43.5 - SRO Only)
Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECT/ON (HPCI) SYSTEM; and (b) based 4.1 86 on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- High drywell pressure: BWR-2,3,4.-
- aQ~9QQ leelatleR (IiiM8rs8RG)')
GeRdeRS8' N/A for BFN - No Isolation Condenser{s)
SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 10
~~"~----------------~4"----------------~~()~~--
ES-401 Fonn ES-401-1 ES-401 BWR Examination OutUne Form ES-401*'
Plant SySlems - TIer 2/Group, (RO I SRO)
System" I Name K
K K
K K
K A
A A
A G
KIA Topic{s)
I.
1 2
3 4
5 6
1 2
3 4
203000 RHRll PCI: I"Jedion 1
K5.02 (10CFR 55.41.5) ' "Details In Record of Rejected K/As" Knowledge of the operational implications of the following concepts as 3.5 28 they apply to RHR I LPCI: INJECTION MODE (PLANT SPECIFIC):
- Core cooling methods 205000 Shutdown Cooling 1
1 K2.02 (10CFR 55.41.7)
Knowledge of electrical power supplies to the following:
2.5 29
- Motor operated valves A4.03 (10CFR 55.41.7) --Detail!; In Record of Rejected K/As**
Ability to manually operate andlor monitor in the control room:
3.6 30
1 K4.03 (10CFR 55.41.7) * *Oetails in Record of Rejected KJAs" Knowledge of HIGH PRESSURE COOLANT INJECTION (HPCI)
SYSTEM design feature(s) andlor interlocks which provide for the 4.2 31 following:
- Resetting turbine trips: BWR-2,3,4 A2.16 (10CFR 55.43.5 - SRO Only)
AbiUty to (a) predict the Impacts of the following on the HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM; and (b) based 4.1 86 on those predictions, use procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations:
- High drywell pressure: BWR-2,3,4 ag7.000 I ** II",R (1iM.".,,9Y.
~
NJA /or BFN - No Isolation Condenser(6)
SRO only K/ As shown in Italics 4/9/2009 - 11:06:18 AM Page 10
ES-401 0 o
O~--
4 Form ES... 01-1 ES401 BWR Examination Outline Form ES-401*1 Plant Systems - Tier 2JGroup 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 209001 LPCS 1
K1.12 (10CFR 55.41.5)
Knowledge of the physical connections and/or cause-effect relationships between the LOW PRESSURE CORE SPRAY (LPCS) 2.9 32 SYSTEM and the following:
- ECCS room coolers
' A4.08 (10CFR 55.41.7)
Ability to manually operate and/or monitor in the control room:
4.2 33
- System initiation: Plant-Specific 212000 RPS 1
1 Kl.11 (10CFR 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, 4.2 87 use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Full system activation (full-SCRAM) 2150031RM 1
K4.04 (10CFR 55.41.7)
Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM 2.9 35 design feature(s) and/or interlocks which provide for the following:
- Varying system sensitivity levels using range switches SRO only K/ As shown in italics 4/9/2009 - 11 :06: 18 AM Page 11
==~4t~----------------~44t----------------~~()
,~~--
ES-401 Form ES-401*1 ES-401 BWR Examlnallon OutlIne Form ES-40H Plant Systems - TlElr 21Group 1 (RO I SRO)
System./ N.me K
K K
K K
K * * *
- G KIA Toplc!s)
I.
1 2,
- 5
- 1 2,
- 209001 LPCS 1
KU2 (10CFR 55.41.5)
Knowledge of the physical connections and/or cause-effect relationships bet'Neen the LOW PRESSURE CORE SPRAY (lPCS) 2.9 32 SYSTEM and the following:
- ECCS room coolers 208002HPC&
211000 SLC 1
A4.08 (10CFR 55.41.7)
Ability to manually operate and/or monitor in the control room:
4.2 33
- System initiation: Plant-Specific 212000 RPS 1
1 Kl.11 (10CFR 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, 4.2 87 use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Full system activation (full*SCRAM) 2150031RM 1
K4.04 (10CFR 55.41.7)
Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM 2.9 35 design feature(s) and/or inter10cks which provide for the following:
- Varying system sensitivity levels using range switches SRO only K/ As shown in italics 4/9/2009* 11:06:18 AM Page I I
- 4.
Form ESJ----
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 3.2 36 MONITOR (SRM) SYSTEM including:
A2.07 (10CFR 55.41.5)
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
--e------------e ES-401 4
Form Esl-.1----
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 3.2 36 MONITOR (SRM) SYSTEM including:
A2.07 (10CFR 55.41.5)
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~
A __
ES-401 4
Form 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 3.6 39 CORE ISOLATION COOLING (RCIC) SYSTEM will have on the following:
- Adequate core cooling G2.4.41 (10CFR 55.43.5. SRO Only) 4.6 88 Knowledge of the emergency action level thresholds and 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:
- Low pressure core spray: Plant-Specific L
L.... *. ~~
~--
L-... __
SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 13
-ES-40-1~~I~~----------------------4tt Form EsI-.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)
Knowledge of the effect that a loss or malfunction of the REACTOR 3.6 39 CORE ISOLATION COOLING (RCIC) SYSTEM will have on the following:
- Adequate core cooling G2.4.41 (10CFR 55.43.5. SRO Only) 4.6 88 Knowledge of the emergency action level thresholds and 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:
- Low pressure core spray: Plant-Specific SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 13
_---"11'
,1-.1 --
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (RO / 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 223002 PCIS/Nuclear Steam 2
K1.03 (10CFR 55.41.5)
Supply Shutoff 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 2.7 42 relationships between the PRIMARY CONTAINMENT ISOLATION SYSTEM (PC IS) / NUCLEAR STEAM SUPPLY SHUT-OFF and the following:
- Traversing in-core probe system 239002 SRVs 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
--~il~~-------------------41t ES-401 Form ESt-.1----
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (RO / 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 223002 PCIS/Nuclear Steam 2
K1.03 (10CFR 55.41.5)
Supply Shutoff 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 2.7 42 relationships between the PRIMARY CONTAINMENT ISOLATION SYSTEM (PC IS) / NUCLEAR STEAM SUPPLY SHUT-OFF and the following:
- Traversing in-core probe system 239002 SRVs 1
1 A1.01 (10CFR 55.41.5)
Ability to predict and/or monitor changes in parameters associated 3.3 43 with operating the RELIEF / SAFETY VALVES (SRVs) controls including:
- Tail pipe temperature 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 alarm.
SRO only K/As shown in italics 4/9/2009 - 11:06:18 AM Page 14
ES-401 I
- 4.
Form 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 3.3 90 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- High containment pressure 262001 AC Electrical 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
-ES-4-0-1~1~----------------------------4tt Form 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 3.3 90 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- High containment pressure 262001 AC Electrical 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
- Load sequencing 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
ES-401 0 4 0 Fonn ESQ
- II'-1_-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 G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 I
I 262002 UPS (AC/DC) 2 KG.02 (1 OCFR 55.41.7)
Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (UPS)
(AC. I D.C.):
2.8 48
+
D.C. electrical power KG.03 (1 OCFR 55.41.7)
I Knowledge of the effect that a loss or malfunction of the following will 2.7 49 have on the UNINTERRUPTABLE POWER SUPPLY (UPS)
(AC. I D.C.):
+
Static inverter 263000 DC Electrical 1
A2.01 (10CFR 55.41.5)
Distribution Ability to (a) predict the impacts of the following on the D.C.
ELECTRICAL DISTRIBUTION SYSTEM; and (b) based on those 2.8 50 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
+
Grounds 264000 EDGs 1
K5.05 (10CFR 55.41.5)
Knowledge of the operational implications of the following concepts as 3.4 51 they apply to EMERGENCY GENERATORS (DIESEL I JET):
+
Paralleling AC. power sources 300000 Instrument Air 1
K2.01 (10CFR 55.41.7)
Knowledge of electrical power supplies to the following:
2.8 52
_+_'nst!ument air compress~
SRO only K/ As shown in italics 4/9/2009 - 11 :06: 18 AM Page 16
~E~S~4701o--"'~------------------------------~4"'----------------------------~F~o-nn-=E~
S~~1-~1 ------
ES-40 1 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
G KIA Topic(s)
IR 1
2 3
4 5
- 1 2
3 4
262002 UPS (ACfDC) 2 K6.02 (10CFR 55.41.7)
Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (UPS)
(A.C.I D.C.):
2.8 48
- D.C. electrical power K6.03 (10CFR 55.41.7)
Knowledge of the effect that a loss or malfunction of the following will 2.7 49 have on the UNINTERRUPTABLE POWER SUPPLY (UPS)
(A.C.I D.C.):
- Static inverter 263000 DC Electrical 1
A2.01 (10CFR 55.41.5)
Distribution Ability to (a) predict the impacts afthe following on the D.C.
ELECTRICAL DISTRIBUTION SYSTEM; and (b) based on Ihose 2.8 50 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Grounds 264000 EDGs 1
K5.05 (tOCFR 55.41.5)
Knowledge of the operational implications of the following concepts as 3.4 51 they apply to EMERGENCY GENERATORS (DIESEL I JET):
- Paralleling AC. power sources 300000 Instrument Air 1
K2.01 (10CFR 55.41.7)
Knowledge of electrical power supplies to the following:
2.8 52
--0 0
o~-
ES-401 4
Form ES-401-1 ES-401 System # I Name 400000 Component Cooling Water KIA Category Point Totals:
(RO)
KIA Category POint Totals:
(SRO)
BWR Examlnatlon Outline Plant Systems - Tier 2lGroup 1 (RO I SRO)
KIKIKIKIK IKIA IAIAIAIG 1 234 5 6
1 234 1
412 131212 13 1212121212 2
KIA Topic(s)
A1.01 (10CFR 55.41.5)
Ability to predict and/or monitor changes in parameters associated with operating the COMPONENT COOLING WATER SYSTEM controls including:
CCW flow rate Group Point Tolal: (RO)
Group Point Total: (SRO)
SRO only K/As shown in italics 4/9/2009 - 11 :06: 18 AM Form ES-401-1 IR 2.8 53 26 5
Page 17
-=E-=-S-4--=01:--e Form ESQ~1 --:-1----
ES.... 01 BWR Examination Outline Form ES-4Q1*1 Plant rter 21Groop 1 (RQ I SRO)
System " Name K
K K
K K
K A
- A A
G KIA Toplc(s)
I
- I 1
2 3
4,
- 1 2
3
- 400000 Component Cooling 1
A1.01 (10CFR 55.41.5)
Water Ability to predict and/or monitor changes in parameters associated with oper.Hng the COMPONENT COOLING WATER SYSTEM 2.8 53 controls including:
- CCW flow rate KIA Category POint Totals.
4 2 3 2 2 3 2 2 2 2 2 Group Point TOIal (RO) 26 (RO)
KIA category Pomt Totals.
3 2
Group Point Total: (SRO) 5 (SRO)
SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 17
o 0
0,,------
ES-401 5
Form ES-401-1 ES~01 BWR Examination Outline Form ES-401*1 Plant Systems - Tier 2JGroup 2 (RO I SRO)
System til Name K
K K
K K
K A
A A
A G
KIA Toplc(s)
IR 1
2 3
4 5
6 1
2 3..
201001 CRD Hydraulic 1
K6.04 (1 OCFR 55.41.7)
Knowledge of the effect that a loss or malfunction of the following 3.6 54 will have on the CONTROL ROD DRIVE HYDRAULIC SYSTEM:
- RPS 2O~OO~ RM~S NOT RANDOML Y SELECTED
~01008 ~eAIF81 Rea BRa gA'IfI NOT RANDOMLY SELECTED MaallaAlsm
~9~OO4 RS~S N/A for BFN - BWR 4/5 ONL Y
____ c. --.-
~9~OO6 R~IS N/A fOr BFN - BWR 6 ONLY
,~9~00fi RWM NOT RANDOMLY SELECTED-202001 Recirculation 1
A2.10 (10CFR 55.43.5 - SRO Only)
Ability to (a) predict the impacts of the following on the I
I RECIRCULA TlON SYSTEM; and (b) based on those predictions, 3.9 91 use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Recirculation pump seal failure
~gO!oo~ Reelf8111atl8R Flew ~eRIFeI -
NOT RANDOMLY SELECTED---
204000 RWGY NOT RANDOML Y SELECTED
~~4000 RPIS NQT RANDOMLY SELECTED.
215001 Traversing In*core Probe 1
A3.03 (1 OCFR 55.41.7)
Ability to monitor automatic operations of the TRAVERSING IN-2.5 55 CORE PROBE including:
- Valve operation: Not-BWR1
-- L-____ _
L.. _
SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 18
"'E=-S-4
-:CO::c1:-,e Form ESQ~1 --:-1:-----
ES""Ol BWR Ekamlnalion Outline Form ES-401*'
Plant Systems - Tier 2JGroup 2 (RO I SRO)
Systom
- J Name K
K K
K K
K A
- A A
G KIA Toplc(s)
I.
1 2
3
- 5
- 1 2
3
- 201001 eRO Hydraulic 1
K6.04 (10CFR 55.41.7)
Knowledge of the effect that a toss or malfunction of the following 3.6 54 will have on the CONTROL ROD DRIVE HYDRAULIC SYSTEM:
- 10100.2 RMes NOT RANDOMLY SELECTED 3Q100a COM,eI RM I"i 0fW, NOT RANDOMLY SELECTED MeGh.AM OlQ1QQ4 RGes N/A for BFN - BWR 4/5 ONLY 30101;1& ACIS N/A for BFN - BWR 6 ONLY
- iQ1QQi RWM NOT RANDOMLY SELECTED 202001 Recirculation 1
A2.10 (10CFR 55.43.5 - SRO Only)
Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and (b) based on those predictions, 3.9 91 USB procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Recirculation pump s8al failure agaoga R ** ewlM!8f1 ~IQI\\tJI e8"'fOI - - - - - - - - - - -
NOT RANDOMLY SELECTED 2Q400QRWCU NOT RANDOMLY SELECTED
- 11.1>>0 RPaS NOT RANDOMLY SELECTED 215001 Traversing In-core Probe 1
A3.03 (10CFR 55.41.7)
Ability to monitor automatic operations of the TRAVERSING IN-2.5 55 CORE PROBE including:
~O n
O~-
5 Form ES401-1 ES-401 ES-401 BWR Examination Outline Form ES-401 -1 Plant Systems - Tier 2/Group 2 (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 215002 RBM 1
1 K1.02 (10CFR 55.41.6)
Knowledge of the physical connections andfor cause-effect relationships between ROD BLOCK MONITOR SYSTEM and the 3.2 56 following:
- LPRM: BWR-3,4,5 A2.05 (10CFR 55.43.5 - SRO Only)
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 those abnormal conditions or operations:
- RBM high or inoperable: BWR-3,4,5
- UiOOO NlialaaF 8eRaF IAII.
NOT RANDOML Y SELECTED 219000 RHRlLPCI: Torus/Pool 1
K2.02 (10CFR 55.41.7)
Cooling Mode Knowledge of electrical power supplies to the following:
3.1 57
- Pumps
~300~ Pfima~ G~; lAd AWII.
NOT RANDOMLY SELECTED
- aMOO1 RWRJl-PGI: GlMl' SpFay Made NOT RAN DOML Y SELECTED 230000 RWRP... PGI: ;efUe.tPeel NOT RANDOMLY SELECTED Spray Meda 233000 Fuel Pool Cooling/Cleanup 1 G2.4.35 (10CFR 55.43.5* SRO Only)
Knowledge of local auxiliary operator tasks during an emergency 4.0 93 and the resultant operational effects.
234000 I"wal WIAdllA9 iqwlpmaAI - -
NOT RANDOMLY SELECTED a3900~ ~1aIA lAd Rahaal steam NOT RANDOMLY SELECTED SRO only Kj As shown in italics 4/9/2009 - 11:06:18 AM Page 19
~E~S4~Ol~4It--------------------------------~541t o
Form ES40"'1""":-1,---------
ES-401 BWR Examination Outline Fcmn E$-401-1 Plant Systems - Tier 2/Group 2 IRO I SRO)
System., Name K
K K
K K
K A
A A
A G
KIA Toplc(s, I.
1 2
3
- 5
- 1 2
3
- 215002 RBM 1
1 Kl.02 (10CFR 55.41.6)
Knowledge of the physical connections andfor cause--effect relationships between ROO BLOCK MONITOR SYSTEM and the following:
3.2 56
- LPRM: BWR-3.4.5 A2.0S (fOCFR 55.43.5 - SRO Only)
Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 3.3 92 those abnormal conditions or operations:
- RBM high or inoperable: BWR*3,4.5
~11OOO N\\IIoI ** r IIdlr 11\\111.
NOT RANDOMLY SELECTED 219000 RHRIlPCI: TorusIPool 1
K2.02 (10CFR 55.41.7)
Cootrng Mode Knowledge of electrical power supplies to the following:
3.1 57
- Pumps a2:1OG1 P..... I)' CJ:Mr IAeI AIIII>
NOT RANDOMLY SELECTED aaiQOl RHRJ'..P(;li Cm:F S,MY NOT RANDOMLY SELECTED 2i10QQ0 RHMPCI; ~.01 NOT RANDOMLY SELECTED
- ,..
- t Mgil 233000 Fuel Pool Coohrlg/Cleanup 1 G2.4.3S (fOCFR 55.43.5 - SRO Only)
Knowledge of local auxifiary operator tasks during an emergency 4.0 93 and the resultant operational effects.
3a4000 ~w" ""AiNA. ",w,"'IAI - - -
NOT RANDOMLY SELECTED a31KlCn MilA 1M ~".. I a.,.,.,. - - - - - - - - -
NOT RANDOMLY SELECTED SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 19
ES-401 0-------
5 Form ES-401-1 ES.401 BWR Examination Outline Form ES.401-1 Plant Systems - TIer 21Group 2 (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 239003 MSIV Leakage ContrOl 1
K4.02 (10CFR 55.41,7)
Knowledge of MSIV LEAKAGE CONTROL SYSTEM design feature(s) andlor interlocks which provide for the following:
3.0 58
- Perfonnance of intended safety function following any single active component failure: BWR-4,5,6(P-Spec) 241000 ReactorlTurbine Pressure 1
A1.01 (10CFR 55.41.5) **Detalls in Kel.~rcl ')1 ::If:JE' :ted 1( '45 Regulator Ability to predict andlor monitor changes in parameters associated with operating the REACTOR / TURBINE PRESSURE 3.9 59 REGULATING SYSTEM controls including:
- Reactor pressure 245000 Main Turbine Gen. I Aux.
1 K5.07 (10CFR 55.41.5)
Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY 2.6 60 I
SYSTEMS:
I
- Generator operations and limitations 256000 Reactor Condensate 1 G2.1.30 (10CFR 55.41.7)
Ability to locate and operate components, including local controls.
4.4 61 2&.900~ ReaeteF J::88"wetef NOT RANDOMLY SELECTED 01811000 Reiweate NOT RANDOMLY SELECTED 2710000ffgas 1
A4.06 (10CFR 55.41.7)
Ability to manually operate and/or monitor in the control room:
3.3 62
- System indicating lights and alarms SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 20 0
~E=
S~
47 01~ ~------------------------------~5
~F~o-nn~E=
S~
4~
01~-7 1 -------
ES--401 BWR Examination Outline Form ES-401-1 Ptant Systems - Tier 2JGroup 2 (RO' SRO)
System" J Name K
K K
K K
K * *
- A G
KIA Topic,s)
I.
1 2
3 *
- 6 1
2 3
- 239003 MSIV Leakage Control 1
K4.02 (10CFR 55.41.7)
Knowledge of MSIV LEAKAGE CONTROL SYSTEM design feature(s) andler interlocks which provide for the following:
3.0 58
- Performance of intended safety function following any single active component failure: BWR4.5,6(P-Spec) 241000 ReactorfTurbine Pressure 1
A1.01 (10CFR 55.41.5) "Oet,ul" In Rf- :Old of Re K!!-d KtAs" Regulator Ability to predict and/or monitor changes In parameters associated wilh operaling the REACTOR I TURBINE PRESSURE 3.9 59 REGULATING SYSTEM controls including:
- Reactor pressure 245000 MaIn Turbine Gen. I AUK, 1
K5.07 (10CFR 55.41.5)
Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY 2.6 60 SYSTEMS:
- Generator operations and limitations 256OOC1 ReaClor Condensate 1 G2.1.30 (10CFR 55.41.7)
Ability to locale and operate components, including local controls, 4.4 61
~'&QO~ Rullle, fO........ '
NOT RANOOML Y SELECTED iM.OOOR.......
NOT RANOOML Y SELECTED 271000 Offgas 1
A4.0S (10CFR 55.41.7)
Ability to manually operate andlor monitor in the control room:
3.3 62
=.0
&\\
0 -
ES-401 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-40t-1 Plant Systems - Tier 21Group 2 (RO I SRO)
System'll 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
- !;aOOQ RadiatillA MIIAiteFiRIt NOT RANDOMLY SELECTED I
as&QOO IOIFe PFGteetillR NOT RANDOML Y SELECTED 288000 Planl Ventilation 1
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, use 2.6 63 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Extreme outside weather conditions: Plant-Specific 290001 Secondary CTMT 1
K3.01 (10CFR 55.41.7)
Knowledge of the effect that a loss or malfunction of the 4.0 64 SECONDARY CONTAINMENT will have on the following:
- Off-site radioactive release rates 0I9OQQ3 GIIRlfel Reem HVAG NOT RANDOMLY SELECTED---
1 290002 Reaetor Vessellntemals 1
K1.04 (10CFR 55.41.5)
Knowledge of the physical connections and/or cause-effect I
relationships between REACTOR VESSEL INTERNALS and the 3.4 65 following:
- HPCI: Plant-Specific I
KIA Category Point Totals:
2 1 1 1 1 1 1 1 1 1 1 Group Point Total: (RO) 12 I
(RO)
KIA Category Point Totals:
2 1
Group Point Total: (SRO) 3 (SRO)
SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 21
~~"~----------------~5" ES-401 Form ESQ~1-C_1:-----
ES"'Ol BWR Examination Outline Form ES... Ol -1 (RO I SRO)
System'/ Name
- * * * * * *
- A A
G KJA Topic(_)
IR I
1 2
3 4
5
- 1 2
3 4
- i~agog R.IlIaIIIlA MIIA~.Mg NOT RANDOMLY SELECTED
- iIlOOO fOl", Pl9llGtj8A NOT RANDOMLY SELECTED 288000 Plant Ventilallon 1
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. use 2.6 63 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
- Extreme outside weather conditions:
290001 SeCOndary CTMT 1
K3.01 (10CFR 55.41.7)
Knowledge of the effect that a loss or malfunction of the 4.0 64 SECONDARY CONTAINMENT will have on the following:
- Off-site radioactive release raies 38QQQ3 eeA&N1 Re_ HVAC NOT RANDOMLY SELECTED-290002 Reactor Vessellntemals 1
K1.04 (10CFR 55.41.5)
Knowledge of the physical connections andlor cause-effect relationships between REACTOR VESSEL INTERNALS and the 3.4 65 following:
- HPCI: Plant*Specific KIA Category PoInt Totals:
2 1 1 1 1 1 1 1 1 1 1 Group PoInt Total: (RO) 12 (ROI I ~R6)egoty Point Totsls:
2 1
Gt'OUp Point Total: (SRO) 3 SRO only K/ As shown in italics 4/9/2009 - 11:06:18 AM Page 21
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401*3 Facility:
Browns E~lTY NPP Date of Exam:
July 6
- 30, 2009 RO SRO-Only Category KlA#
Topic IR IR 2.1.
G2.1.39 (10CFR 55.41.10) 3.6 66 Knowledge of conservative decision making practices.
G2.1.13 (10CFR 55.43.5 - SRO Only) 3.2 94 Knowledge of facility requirements for CJ) controlling vital/controlled access.
C 0
2.1.
G2.1.6 (10CFR 55.41.10) 3.8 67
+=i m Ability to manage the control room crew during L...
Q)
Q.
.0 G2.1.4 (10CFR 55.43.2 - SRO Only) 3.B 95
~.....
Knowledge of individual licensed operator 0
responsibilities related to shift staffing, such as
-0 medical requirements, "no-solo" operation,
- l maintenance of active license status, 10CFR55,
-C etc.
C 0
~ NOT RANDOMLY SELECTED 0
~ NOT RANDOMLY SELECTED
~ NOT RAN DOML Y SELECTED
~ NOT RANDOML Y SELECTED Subtotal 2
2 2.2.
G2.2.20 (10CFR 55.41.10) 2.6 68 Knowledge of the process for managing troubleshooting activities.
G2.2.19 (10CFR 55.43.5 - SRO Only) 3.4 96 Knowledge of maintenance work order 0
requirements.
C 2.2.
G2.2.22 (10CFR 55.41.5) 4.0 69 0
Knowledge of limiting conditions for operations
()
and safety limits.
N C
G2.2.23 (10CFR 55.43.2 - SRO Only) 4.6 97 Q)
E Ability to track Technical Specification limiting Q.
conditions for \\,'./.,.<;;, auv, '0.
- J
~ NOT RANDOMLY SELECTED 0-W
~ NOT RANDOMLY SELECTED
~ NOT RANDOMLY SELECTED
~ NOT RANDOMLY SELECTED Subtotal 2
2 SRO only K/ As shown in italics 4/9/2009 - 11:13:34 AM Page 22 ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3
'1 i Ferry NPP Date of Exam:
~6-30, 201)9 RO SRO-Only Category KIA.
Topic IR IR 2.1.
G2.1.39 (10CFR 55.41.10) 3.6 66 Knowledge of conservative decision making practices.
GZ.1.13 (10CFR 55.43.5-SRO Only) 3.2 94 Knowledge of faCility requirements for VJ controfling vital/controlled access.
c:
0 2.1.
G2.1.6 (10CFR 55.41.10) 3.8 67 (lI Ability to manage the control room crew during
~
C1l Q.
. 0 GZ.1.4 (10CFR 55.43.Z - SRO Only) 3.B 95
~-
Knowledge of individual licensed operator 0
responsibilities related to shift staffing, such as medical requirements, ~no-sofo
- operation,
~
maintenance of active license status, 10CFR55,
'U etc.
c:
0
- M-,
NOT RANOOML Y SELECTED U
- M-,
NOT RANOOML Y SELECTED
~ NOT RANOOML Y SELECTED
- M-,
NOT RANOOML Y SELECTED Subtotal 2
2 2.2.
, I '
55.41.10) 2.6 68 Knowledge of the process for managing troubleshooting activities.
GZ.Z.19 (10CFR 55.43.5 - SRO Only) 3.4 96 Knowledge of maintenance work order 0
requirements.
~ -
C 2.2.
G2.2.22 (10CFR 55.41.5) 4.0 6 9 0
Knowledge of limiting conditions for operations U
and safety limits.
N C
GZ.Z.Z3 (10CFR 55.43.2 - SRO Only) 4.6 97 C1l E
Ability to track Technical Specification limiting Q.
conditions (or
~
~ NOT RANOOML Y SELECTED 0-W
~ NOT RANOOML Y SELECTED
~ NOT RANOOML Y SELECTED
~ NOT RANOOML Y SELECTED Subtotal 2
2 SRO only K/ As shown in italics 4/9/2009 - 11:13:34 AM Page 22
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401*3 Facility:
Browns Ferry NPP Date of Exam:
July 6 - 30 ~OO~
RO SRO-Only Category KlA#
Topic IR IR 2.3 G2.3.14 (10CFR 55.41.12) 3.4 70 Knowledge of radiation or contamination hazards that may arise during normal, abnormal. or emergency conditions or activities.
G2.3.11 (10CFR 55.43.4 - SRO Only) 4.3 98 Ability to control radiation releases.
2.3 G2.3.4 (1 OCFR 55.41.12) 3.2 71 0
Knowledge of radiation exposure limits under C
normal or emergency conditions.
a 3.6 99
()
G2.3.7 (10CFR 55.43.415-SRO Only)
('I') C Ability to comply with radiation work permit a
requirements during normal or abnormal
- .t:i conditions.
ro "0
2.3 G2.3.7 (10CFR 55.41.12) 3.5 72 ro c::
Ability to comply with radiation work permit requirements during normal or abnormal conditions.
~
NOT RANDOMLY SELECTED
~
NOT RANDOMLY SELECTED
~
NOT RANDOMLY SELECTED Subtotal 3
2 2.4.
G2.4.18 (10CFR 55.41.10) 3.3 73 c
Knowledge of the specific bases for EOPs.
CO 4.5 100
- a.
G2.4.B (10CFR 55.43.5 - SRO Only)
Knowledge of how abnormal operating C/'J procedures are used in conjunction with EOPs.
Q.)
~
2.4.
G2.4.26 (1 OCFR 55.41.10) 3.1 74 -
- J
'0 Knowledge of facility protection requirements Q.)
including fire brigade and portable fire fighting 0
V 0
equipment usage.
~
- a.
2.4.
G2.4.6 (1 OCFR 55.41.10) 3.7 75 -
0 Knowledge of EOP mitigation strategies.
C Q.)
~ NOT RAN DOML Y SELECTED C)
~
Q.)
~ NOT RANDOMLY SELECTED E
w
~ NOT RANDOMLY SELECTED Subtotal 3
1 Tier 3 Point Total 10 7
SRO only K/ As shown in italics 4/9/2009 - 11:13:34 AM Page 23 ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 il ~
Date of Exam:
Julv6. 30.~
RO Category KiA #
Topic IR IR 2.3 G2.3.14 (10CFR 55.41.12) 3.4 70 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
GZ.3.11 (10CFR 55.43.4-SRO Only) 4.3 98 Ability to control radiation releases.
2.3 G2.3.4 (10CFR 55.41.12) 3.2 71 0
~
Knowledge of radiation exposure limits under C
normal or emergency conditions.
0 3.6 99 0
G2.3.7 (10CFR 55.43.415-SRO Only)
(") C Ability to comply with radiation work permit 0
requirements during normal or abnormal
- 0:;
conditions.
ell 2.3 G2.3.7 (10CFR 55.41.12) 3.5 72 ell Ability to comply with radiation work permit a::
requirements during 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 55.41.10) 3.3 73 C
Knowledge of the specific bases for EOPs.
ell 4.5 100 C-GZ.4.B (10CFR 55.43.5 - SRO Only)
Knowledge of how abnormal operating If) procedures are used in conjunction with EOPs.
~
2.4.
G2.4.26 (10CFR 55.41.10)
- l 3.1 74 -
-C Knowledge of facility protection requ1rements Q) including fire brigade and portable fire fighting 0
V 0
~
C-2.4.
G2.4.6 (10CFR 55.41.10) 3.7 75 -
0 Knowledge of EOP mitigation strategies, c
Q)
~ NOT RANDOMLY SELECTED Cl
~
Q)
~ NOT RANDOMLY SELECTED E
UJ
~ NOT RANDOMLY SELECTED Subtotal 3
1 ner 3 Point Total 10 7
SRO only K/ As shown in italics 4/9/2009 - 11:13:34 AM Page 23
DRAFT ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility: !5rlwllf ~"if Date of Exam: 2 (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 2
1 1
1 1
1 7
2 1
3 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.
2 1
1 1
1 1
1 1
1 1
1 12 0 I 2
1 3
Plant 2
Systems Tier Totals 6
3 4
3 3
4 3
3 3
3 3
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
3 2
2 2
1
- 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 A TIer 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 based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 pOints.
- 3.
Systems/evolutions 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 e
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 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 selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
I I
I
- 6.
Select SRO topics for TIers 1 and 2 from the shaded systems and KIA categories.
- 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 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, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
I L~~
__ ~_
.. ~.
DRAFT I
I i
J DRAFT ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility: !5rlwllf ~"If Date of Exam: 2 oC) '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 2
1 1
1 1
1 7
2 1
3 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.
2 1
1 1
1 1
1 1
1 1
1 12 0 I 2
1 3
Plant 2
Systems Tier Totals 6
3 4
3 3
4 3
3 3
3 3
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
3 2
2 2
1
- 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 A TIer 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 based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 pOints.
- 3.
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 e
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 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 selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
I I
I
- 6.
Select SRO topics for TIers 1 and 2 from the shaded systems and KIA categories.
- 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 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, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
I L~~
__ ~_
.. ~.
DRAFT I
I i
I J
ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE KA 295001AA1.
NAME / SAFETY FUNCTION:
Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 IR RO SRO 3.3 3.3 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G 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 3.2
~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the operational implications 295004AK3.
Partial or Total Loss of DC Pwr / 6 2.9 3.3 of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3)
L---.-JL---.l~L---.-JL-JL---.-JL-J 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 0 0 0 DOD 0 0 0 ~
This is a Generic, no stem statement is associated.
295006AK2.
SCRAM / 1 3.8 3.8
[
Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) 295016G2.4 Control Room Abandonmentl7 2.7 4.1 0 [] 0 0 0 DOD 0 ~
This is a Generic, no stem statement is associated.
Page 1 of 4 FORM ES-401-1 TOPIC:
R~
Under voltage/degraded voltage effects on electrical loads.................................................
Ground isolation/fault determination..................
Knowledge of the parameters and logic used to assess the status of safety functions Reactor water level control system....................
Knowledge of events related to system operations/status that must be reported to internal orginizations or ou1side agencies.
10/2212008 10:15 AM ES-401, REV 9 KA 295001AA1.
295003AK1.
NAME / SAFETY FUNCTION:
Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 Partial or Complete Loss of AC / 6 T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.3 DOD D D 0 ~ D D D D Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/
45.6) 2.9 3.2
~ D D D D D D D D D D 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)
FORM ES-401-1 TOPIC:
R~
Under voltage/degraded voltage effects on electrical loads.................................................
295004AK3.
Partial or Total Loss of DC Pwr / 6 295005G2.4 Main Turbine Generator Trip / 3 2.9 3.3
[J D ~ D D D D D [J D Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13) 4.0 4.6 D D D D D D D D D D ~
This is a Generic, no stem statement is associated.
Ground isolation/fault determination..................
Knowledge of the parameters and logic used to assess the status of safety functions 295006AK2.
SCRAM /1 295016G2.4 Control Room Abandonment / 7 3.8 3.8 D ~ D D D D D D D D D Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8)
Reactor water level control system....................
2.7 4.1 D CJ D DDDDDD~
This is a Generic, no stem statement is associated.
Page 1 of 4 Knowledge of events related to system operations/status that must be reported to internal orginizations or ou1side agencies.
10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295018AA1.
Partial or Total Loss of CCW I 8 295019AK2.
Partial or Total Loss of Inst. Air 18 T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.4 3.5 3.5 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I 45.5 I 45.6)
~DDD Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7 I 45.7 I 45.8)
FORM ES-401-1 TOPIC:
System loads..........................................
ADS: Plant-Specific..................................
-,,~~-----.---... --.. -------~~----- --
295021G2.2 295023AA1.
295024EA2.
295025EK2.
Loss of Shutdown Cooling I 4 3.6 3.6 I~J D D
D []
D D ~
(multi-unit) Ability to explain the variations in control
~...
board layouts, systems, instrumentation and procedural Refueling Acc Cooling Mode I 8 3.4 3.7 High Drywell Pressure I 5 3.8 3.8 High Reactor Pressure I 3 3.9 4.1 This IS a Genenc, no stem statement IS actions between units at a facility.
associated.
Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5 I 45.6)
Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 I 43.5 I 45.13)
Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7 I 45.7 / 45.8)
Page 2 of 4 Radiation monitoring equipment........................
Suppression pool leveL...............................
ARI/RPTI A TWS: Plant-Specific.........................
10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295018AA1.
Partial or Total Loss of CCW I 8 T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.4 0 0 0 0 0 [J li'l Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I 45.5 I 45.6)
FORM ES-401-1 TOPIC:
System loads..........................................
~-... ----.-.. --- --_. _.. __._.. _-_._--
.~~-.~--
.~-------... -----.---... ----._---._.---
295019AK2.
Partial or Total Loss of Inst. Air 18 3.5 3.5 0 ~ 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 295023AA1.
Refueling Acc Cooling Mode I 8 3.4 3.7
[J 0 o
OLJ OOli'l This is a Generic, no stem statement is associated.
(multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
---.-~-.--~--... ----.-~-.. _
o ODOli'lDO Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5 I 45.6) o Radiation monitoring equipment........................
~--.-.--.... --._._-_.. _----_
.~--.. ---.---.-.... --.-.--.-.----
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/RPTI A 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 T1G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G 295027EK3.
29502SEK1.
295030EK3.
295031EA2.
295037G2.2 29503SEK1.
High Containment Temperature / 5 High Drywell Temperature / 5 Low Suppression Pool Wtr Lvi / 5 Reactor Low Water Level / 2 RO SRO 3.2 3.2 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFA: 41.5/41.10/45.6/
45.13) 3.5 3.7
~
3.6 3.7 4.2 4.2 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)
Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFA: 41.5/41.10/45.6/
45.13)
DD~D Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTlON):(CFA: 41.10/43.5/
45.13)
SCRAM Condition Present and Power 3.7 4.1 0 D D D D D D D ~
Above APRM Downscale or Unknown
/ 1 This is a Generic, no stem statement IS High Off-site Release Rate / 9 associated.
2.5 3.1
~ D 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 FORM ES-401-1 TOPIC:
Containment spray: Plant-Specific....................
Reactor water level measurement.......................
RCIC operation: Plant-Specific.......................
Reactor pressure...............................
Knowledge of surveillance procedures.
Biological effects of radiOisotope ingestion..........
10/221200S 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295027EK3.
High Containment Temperature / 5 29502SEK1.
High Drywell Temperature / 5 295030EK3.
Low Suppression Pool Wtr Lvi / 5 T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.2 0 0 ~ DOD 0 DOD 0 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFA: 41.5/41.10/45.6/
45.13) 3.5 3.7
~ 0 0 0 0 0 0 0 0 0 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) 3.6 3.7 0 0 ~ o o
o Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFA: 41.5/41.10/45.6/
45.13)
FORM ES-401-1 TOPIC:
Containment spray: Plant-Specific....................
Reactor water level measurement.......................
RCIC operation: Plant-Specific.......................
---.~--~--~--~~------~--~--.-----------.------~~~-~-------
.~~---~~-----.
~~-
295031EA2.
Reactor Low Water Level / 2 4.2 4.2 0 0 0 0 0 0 0 ~ 0 D 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTlON):(CFA: 41.10/43.5/
45.13)
Reactor pressure...............................
--.------~---------~----------~-.--- -------
-~-------~~-
~~----~----------~---
295037G2.2 SCRAM Condition Present and Power 3.7 4.1 0 0 0 0 0 0 0 0 ~
Knowledge of surveillance procedures.
Above APRM Downscale or Unknown
/ 1 29503SEK1.
This is a Generic, no stem statement is associated.
~----~--~----
~-------~--.. -~---.--~-------.------~~--~~--
High Off-site Release Rate / 9 2.5 3.1
~ 0 [J 0 [J DOD 0 0 0 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 Biological effects of radiOisotope ingestion..........
10/221200S 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
600000AK3.
700000AK1.
Plant Fire On Site / 8 Generator Voltage and Electric Grid Distrurbancecs T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.4 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13) 3.3 3.5
~J 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 FORM ES-401-1 TOPIC:
Actions contained in the abnormal procedure for plant fire on site Definition of the terms: volts, watts, amps, VARS, power factor 10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
600000AK3.
700000AK1.
Plant Fire On Site / 8 Generator Voltage and Electric Grid Distrurbancecs T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.4 D D ~ D D D D D D 0 [J Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13)
FORM ES-401-1 TOPIC:
Actions contained in the abnormal procedure for plant fire on site 3.3 3.5
~J D D D D D D D D 0 Definition of the terms: volts, watts, amps, VARS, power 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 factor 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295009AK2.
Low Reactor Water Level / 2 T1 G2 BWR EXAMINATION OUTLINE IRK 1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 2.6 2.6 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) o FORM ES-401-1 TOPIC:
Reactor water cleanup.................................
~
~. __________________
0" _____
~_. _ _ _
o _ _ _ _ _ _ _ _ _ _
0 295010G2.4 295012AK1.
295017AK3.
295022AA2.
295029EA1.
High Drywell Pressure / 5 4.6 4.4 0 0 0 0 0 0 0 0 0 0 ~
Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
High Drywell Temperature / 5 3.3 3.5 High Off-site Release Rate / 9 3.3 4.5 Loss of CRD Pumps / 1 3.1 3.2 High Suppression Pool Wtr Lvi / 5 3.4 3.5 This is a Generic, no stem statement is associated.
~
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)
Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13)
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13) 00 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 Pressure/temperature relationship.....................
Implementation of site emergency plan.................
CRD mechanism temperatures............................
RCIC: Plant-Specific.................................
10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295009AK2.
Low Reactor Water Level / 2 295010G2.4 High Drywell Pressure / 5 295012AK1.
High Drywell Temperature / 5 295017AK3.
High Off-site Release Rate / 9 T1 G2 BWR EXAMINATION OUTLINE IRK 1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 2.6 2.6 D r;(I Dl~DDDDDD Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) 4.6 4.4 DOD DOD D D D D ~
This is a Generic, no stem statement is associated.
3.3 3.5
~ D 0 [] 0 o
000 3.3 4.5 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)
O~O[JOOOO[10 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/
45.6/45.13)
FORM ES-401-1 TOPIC:
Reactor water cleanup.................................
Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
Pressure/temperature relationship.....................
Implementation of site emergency plan.................
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 3.5 DOD DOD ~ D DO 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 RCIC: Plant-Specific.................................
10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295036EK1.
Secondary Containment High Sump/Area Water Levell 5 T1G2 BWR EXAMINATION OUTLINE IRK 1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 2.9 3.1
~
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 FORM ES-401-1 TOPIC:
Radiation releases....................................
10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295036EK1.
Secondary Containment High Sump/Area Water Levell 5 T1G2 BWR EXAMINATION OUTLINE IRK 1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 2.9 3.1
~ 0 0 0 [J 0 0 DOD 0 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 FORM ES-401-1 TOPIC:
Radiation releases....................................
10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
203000K5.0 AHA/LPCI: Injection Mode T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 2.7 2.9 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFA: 41.5/45.7)
FORM ES-401-1 TOPIC:
Testable check valve operation
---~-.~
--~--,,~~---.~------._--
205000K2.0 Shutdown Cooling 2.5 2.7 0
~
Motor operated valves Knowledge of electrical power supplies to the foliowing:(CFA: 41.7)
--._-- -- -~--~~-----~~--------~~.
.------------~---. ---.~~----~-
.--~----
206000K4.1 HPCI 3.1 3.3 0 0 0
~ 0 [.J 0 0
0 Minimizing fission product concentration in the 207000A4.0 Isolation (Emergency) Condenser 209001 K1.1 LPCS 209002A3.0 HPCS 211000A4.0 SLC 3
3.2 condensate storage tank (valve closures on system Knowledge of (SYSTEM) deSign feature(s) initiation): BWA-2 34(P-Spec) and or interlock(s) which provide for the foliowing:(CFR: 41.7)
Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)
Primary and shell sidetemperatures: BWA-2,3 2.9 3.1
~
ECCS room coolers 3.7 3.7 4.2 4.2 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) o Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7/45.5)
Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)
Page 1 of 5 System flow: BWA-5,6 System initiation: Plant-Specific 10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
203000K5.0 AHA/LPCI: Injection Mode 205000K2.0 Shutdown Cooling 206000K4.1 HPCI 207000A4.0 Isolation (Emergency) Condenser T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 2.7 2.9 0 0 0 0 ~ 0 LJ 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFA: 41.5/45.7) 2.5 2.7 0 ~ 0 0 0 0 0000 3.1 3
3.3 Knowledge of electrical power supplies to the foliowing:(CFA: 41.7) o o
Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 3.2 ODD o
ooo~o Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)
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)
FORM ES-401-1 TOPIC:
Testable check valve operation Motor operated valves Minimizing fission product concentration in the condensate storage tank (valve closures on system initiation): BWA-2,3,4(P-Spec)
Primary and shell sidetemperatures: BWA-2,3
.~--~~~-~~-
---~--~---~~---~~-----~- --------- _._-------
.--~-------------.-.-----------~-
209002A3.0 HPCS 3.7 3.7
[J 0 0 0 0 [J 0 [J ~ [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 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)
Page 1 of 5 System initiation: Plant-Specific 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
212000K3,1 RPS 215003K4.0 IRM 215004A3.0 Source Range Monitor 215005A2.0 APRMI LPRM 217000K3.0 RCIC 217000K3.0 RCIC T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3,0 3,3 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 2.9 2.9 0 3,2 3.2 3.2 3.4 3,6 3.6 3.6 3.6 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41,7)
Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7/45,5)
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 I 43.51 45.31 45.13)
Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)
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 FORM ES-401-1 TOPIC:
Recirculation system Varying system sensitivity levels using range switches Meters and recorders Recirculation flow channels flow mismatch Adequate core cooling
---~~-~.--.
~~-.-.~~-.---~~--
Reactor vessel pressure 10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
212000K3,1 RPS 215003K4.0 IRM 215004A3.0 Source Range Monitor T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.3 D D ~ D D D D D D [J D Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 2.9 2.9 D D D ~ D DOD 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41,7) 3,2 3.2 000000
~DD Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7/45,5)
~--.. ----.. ---------------.
FORM ES-401-1 TOPIC:
Recirculation system Varying system sensitivity levels using range switches Meters and recorders 215005A2.0 APRM 1 LPRM 3.2 3.4 0 [J 0 DDD~ o Recirculation flow channels flow mismatch 217000K3.0 RCIC 217000K3.0 RCIC 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) 3,6 3.6 0 0 ~ D D DOD 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 3.6 3.6 0 0 ~ 0 D [J 0 0 0 0 0 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 Adequate core cooling Reactor vessel pressure 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
21S000K1.0 ADS
~ 0 00 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 o
223002K1.1 239002A1.0 259002G2.4 261000K6.0 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)
PCIS/Nuclear Steam Supply Shutoff 2.7 2.9
~ 0 o
SRVs Reactor Water Level Control SGTS 3.3 3.4 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)
Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/
45.5) 4.1 4.3 n II il n Il n II n n n
~
3.1 3.3 This is a Generic, no stem statement is associated.
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 FORM ES-401-1 TOPIC:
Low pressure core spray: Plant-Specific Plant ventilation Traversing in-core probe system Tail pipe temperature Ability to prioritize and interpret the significance of each annunciator or alarm.
Primary containment high pressure: Plant-Specific 10/221200S 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
21S000K1.0 ADS
~ 0 0 0 0 0 0 0 [J 0 0 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 223002K1.1 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)
PCIS/Nuclear Steam Supply Shutoff 2.7 2.9
~ 0 00000 00 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)
FORM ES-401-1 TOPIC:
Low pressure core spray: Plant-Specific Plant ventilation Traversing in-core probe system
.-.-------------.-~~-- --_._----_._----_._.
~--
--.----~-
-.----~--.. ---------.--
239002A1.0 SRVs 259002G2.4 Reactor Water Level Control 261000K6.0 SGTS 3.3 3.4 0 [] 0 D 0
~ 0 0 D 0 Tail pipe temperature 4.1 4.3 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/
45.5) 000000 ooo~
This is a Generic, no stem statement is associated.
Ability to prioritize and interpret the significance of each annunciator or alarm.
~--------------.~---.-.~--~-~-.---
~---
.~- ----- ---------
3.1 3.3 0 OO[J~OO 00 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 Primary containment high pressure: Plant-Specific 10/221200S 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
262001G2.2 AC Electrical Distribution 262002K6.0 UPS (AC/DC) 262002K6.0 UPS (AC/DC) 263000A2.0 DC Electrical Distribution 264000KS.0 EDGs 300000K2.0 Instrument Air T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.9 4.S D D D DOD D D ~
This is a Generic, no stem statement is associated.
Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.71 4S.7) 2.7 2.9 D
2.8 3.2 3.4 3.4 2.8 2.8 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.71 4S.7)
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)
Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.S 1 4S.7)
~DDD Knowledge of electrical power supplies to the foliowing:(CFR: 41.7)
Page 4 of S TOPIC:
Knowledge of less than one hour technical specification action statements for systems.
D.C. electrical power Static inverter Grounds Paralleling A.C. power sources Instrument air compressor 10/2212008 10:1S AM ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:
RO SRO 262001G2.2 AC Electrical Distribution 3.9 4.S 000000 oo~
This is a Generic, no stem statement is associated.
Knowledge of less than one hour technical specification action statements for systems.
262002K6.0 UPS (AC/DC) 2.8 3.1 00 O~D[JOOO Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.71 4S.7)
D.C. electrical power
~--..... -_._--.. _-_.----.. _------ ---_
262002K6.0 UPS (AC/DC) 2.7 2.9 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 264000KS.0 300000K2.0 DC Electrical Distribution 2.8 3.2 0
0 0 lJ 0 ~ 0 lJ Grounds EDGs Instrument Air 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) 3.4 3.4 0 0 0 0 ~ 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.S 1 4S.7) 2.8 2.8 0 ~ 0 0 0 0 o
00 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7)
Page 4 of S Paralleling A.C. power sources Instrument air compressor 10/2212008 10:1S AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
400000A1.0 Component Cooling Water (I
T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 2.8 0 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 FORM ES-401-1 TOPIC:
CCW flow rate 10/2212008 1 0: 15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
400000A1.0 Component Cooling Water T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 2.8 0 0 0 0 0 0 ~ 0 0 0 0 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 FORM ES-401-1 TOPIC:
CCW flow rate 10/2212008 1 0: 15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
201001K6.0 CRD Hydraulic 201004A1.0 RSCS 21S001A3.0 Traversing In-core Probe T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.6 3.7 3.3 3.3 2.S 2.6 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/ 4S.7)
Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.S /
4S.S) ooooo~
Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/ 4S.S)
FORM ES-401-1 TOPIC:
RPS Reactor manual control system: BWR-4,S Valve operation: Not-BWR1 21S002K1.0 RBM 3.2 3.1
~ 0 0 [J 0 0 0
0 [I LPRM: BWR-3,4,S 219000K2.0 RHA/LPCI: Torus/Pool Cooling Mode 3.1 3.3 239003K4.0 MSIV Leakage Control 3
3.4 24S000KS.0 Main Turbine Gen. / Aux.
2.6 2.9 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)
Knowledge of electrical power supplies to the foliowing:(CFR: 41.7)
DO [J ~ 0000 o Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 00 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.S / 4S.7)
Page 1 of 2 Pumps Performance of intended safety function following any single active component failure: BWR-4,S,6(P-Spec)
Generator operations and limitations 10/2212008 10:1S AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
201001K6.0 CRD Hydraulic 201004A1.0 RSCS T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.6 3.7 ODD o~ooooo Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/ 4S.7) 3.3 3.3 0 0 0 0 0 0 ~ D [J o
Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.S /
4S.S)
--~~-~.-.. -.~_
.. ~.-.. ---~~------.-~.--~--.~---~-.--.~~~-
21S001A3.0 21S002K1.0 219000K2.0 239003K4.0 24S000KS.0 Traversing In-core Probe RBM 2.S 2.6 DOD 0 0 0 0 0 ~ 0 D Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/ 4S.S) 3.2 3.1
~ 0 0 [J 0 0 o
DO 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)
RHA/LPCI: Torus/Pool Cooling Mode 3.1 3.3 0 ~ 0 DO o
MSIV Leakage Control Main Turbine Gen. / Aux.
3 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 3.4
[J [J [J ~ 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 2.6 2.9 0 [] [] 0 ~ o DOD Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.S / 4S.7)
Page 1 of 2 FORM ES-401-1 TOPIC:
RPS Reactor manual control system: BWR-4,S Valve operation: Not-BWR1 LPRM: BWR-3,4,S Pumps Performance of intended safety function following any single active component failure: BWR-4,S,6(P-Spec)
Generator operations and limitations 10/2212008 10:1S AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
256000G2.1 Reactor Condensate 271000A4.0 Offgas 288000A2.0 Plant Ventilation 290001K3.0 Secondary CTMT 290002K1.0 Reactor Vessel Internals
()
T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.4 4.0 n il n I-I n n II n Il n
~
3.3 3.2 2.6 2.7 4.0 4.4 This is a Generic, no stem statement is associated.
D~D Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)
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)
Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 3.4 3.5
~ 0 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 FORM ES-401-1 TOPIC:
Ability to locate and operate components, including local controls.
System indicating lights and alarms Extreme outside weather conditions: Plant-Specific Off-site radioactive release rates HPCI: Plant-Specific 10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
256000G2.1 Reactor Condensate 271000A4.0 Offgas T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.4 4.0 D [l D This is a Generic, no stem statement is associated.
3.3 3.2 D D D D D D C U D ~ D Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)
FORM ES-401-1 TOPIC:
Ability to locate and operate components, including local controls.
System indicating lights and alarms 288000A2.0 Plant Ventilation 290001K3.0 Secondary CTMT 2.6 2.7 DOD D DOD ~ D D 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)
Extreme outside weather conditions: Plant* Specific D D D D D D D Off*site radioactive release rates 4.0 4.4 D D ~
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 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 T3 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO G2.1.39 Conduct of operations 3.6 4.3 000 OO~
~---~ --_
G2.1.6 Conduct of operations 3.8 4.8 0
~
-- --_._-- - -------------.-------.----~ -- ----- ----
---~----------
G2.2.20 Equipment Control 2.6 3.8 0
~
G2.2.22 Equipment Control 4.0 4.7
~
G2.3.14 Radiation Control 3.4 3.8 Ii']
FORM ES-401-1 TOPIC:
Knowledge of conservative decision making practices
~ ---------
Ability to manage the control room crew during plant transients.
Knowledge of the process for managing troubleshooting activities.
Knowledge of limiting conditions for operations and safety limits.
Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities
-- -- --- ---.-._----- -- -~----- ------------------------- ------_.---------._----
G2.3.4 Radiation Control 3.2 3.7 II II rl n rl n I-l 0 0
~
Knowledge of radiation exposure limits under normal and G2.3.7 Radiation Control 3.5 3.6 0 Page 1 of 2
~
emergency conditions Ability to comply with radiation work permit requirements during normal or abnormal conditions 10/2212008 10:15 AM 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:
RO SRO G2.1.39 Conduct of operations 3.6 4.3 000 oo~
Knowledge of conservative decision making practices
~
--~---
~-----
~ -
~--~
G2.1.6 Conduct of operations 3.8 4.8 0 0 0 0 0 0 0 0 0 ~
Ability to manage the control room crew during plant G2.2.20 Equipment Control 2.6 3.8 0 o
000 G2.2.22 Equipment Control 4.0 4.7 0 [l 0 o
o G2.3.14 Radiation Control 3.4 3.8
[J 0 0 0 0 0 o
G2.3.4 Radiation Control 3.2 3.7 0 0000 o
G2.3.7 Radiation Control 3.5 3.6 0 0 0 0 OOD Page 1 of 2 o
o transients.
Knowledge of the process for managing troubleshooting activities.
Knowledge of limiting conditions for operations and safety limits.
---~-~-------
Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of radiation exposure limits under normal and emergency conditions Ability to comply with radiation work permit requirements during normal or abnormal conditions 10/2212008 10:15 AM
(t ES-401, REV 9 T3 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO G2.4.18 Emergency Procedures/Plans 3.3 4.0 D~
~---
G2.4.26 Emergency Procedures/Plans 3.1 3.6
~
-~----- -
~-
~-
G2.4.6 Emergency Procedures/Plans D~
Page 2 of 2 FORM ES-401-1 TOPIC:
Knowledge of the specific bases for EOPs.
Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
Knowledge symptom based EOP mitigation strategies.
10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.4.18 Emergency Procedures/Plans G2.4.26 Emergency Procedures/Plans T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 3.3 4.0 DlJDlJDDD 3.1 3.6 0 0 0 0 DOD 0 0 0 ~
FORM ES-401-1 TOPIC:
Knowledge of the specific bases for EOPs.
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 Knowledge symptom based EOP mitigation strategies.
Page 2 of 2 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295003G2.4.50 Partial or Complete Loss of AC / 6 295016G2.4.3 Control Room Abandonment / 7 295018AA2.01 Partial or Total Loss of CCW / 8 295023AA2.01 Refueling Acc Cooling Mode / 8 295025EA2.01 High Reactor Pressure / 3 295027EA2.01 High Containment Temperature / 5 SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.0 C.J D D D DOD D D ~
This is a Generic, no stem statement is associated.
FORM ES-401-1 TOPIC:
Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.7 3.9 0
D D D D D D
~
Ability to identify post-accident instrumentation.
3.3 3.4 This is a Generic, no stem statement is associated.
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13) 3.6 4.0 D
4.3 4.3 3.7 3.7 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
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 Component temperatures................................
Area radiation levels.................................
Reactor pressure......................................
Containment temperature: Mark-ilL.................
10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295003G2.4.50 Partial or Complete Loss of AC / 6 295016G2.4.3 Control Room Abandonment / 7 295018AA2.01 Partial or Total Loss of CCW / 8 SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.0 00 OOODOOO~
This is a Generic, no stem statement is associated.
3.7 3.9 0 OOOOD o
This is a Generic, no stem statement is associated.
3.3 3.4 0 o
OOO~O o Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
FORM ES-401-1 TOPIC:
. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Ability to identify post-accident instrumentation.
Component temperatures................................
... ----~-.. ----.------_._----------._-_. ----.-----.. -~----------.. _---._----------------------
295023AA2.01 Refueling Acc Cooling Mode / 8 3.6 4.0 0 D
O[JO~O o 295025EA2.01 High Reactor Pressure / 3 295027EA2.01 High Containment Temperature / 5 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13) 4.3 4.3 0 o
OOO~OOO Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13) 3.7 3.7 0 [1 0 [J 0 0 0 ~ 0 0 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 Area radiation levels.................................
Reactor pressure......................................
Containment temperature: Mark-ilL.................
10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
700000G2.4.31 Generator Voltage and Electric Grid Distrurbancecs SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 4.2 4.1 D
D~
This is a Generic, no stem statement is associated.
Page 2 of 2 FORM ES-401-1 TOPIC:
Knowledge of annunciators alarms, indications or response procedures 10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
700000G2.4.31 Generator Voltage and Electric Grid Distrurbancecs SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 4.2 4.1 o DODD DDD~
This is a Generic, no stem statement is associated.
Page 2 of 2 FORM ES-401-1 TOPIC:
Knowledge of annunciators alarms, indications or response procedures 10/2212008 10:15 AM
ES-401, REV' 9 KA NAME I SAFETY FUNCTION:
295012G2.4.34 High Drywell Temperature / 5 295013AA2.02 High Suppression Pool Temp. /5 295033EA2.03 High Secondary Containment Area Radiation Levels / 9 SRO T1G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.1 0 0 0 0 0 0 [J 0 0 ~
This is a Generic, no stem statement is associated.
3.2 3.5 0 0 o
D~
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
FORM ES-401-1 TOPIC:
Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Localized heating/stratification......................
~~-.---.~~-----.-----.--.--~
.. ----~------
~.. --- _._----_
3.7 4.2 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 Cause of high area radiation.........................
10/2212008 10:15 AM ES-401, REV' 9 KA NAME I SAFETY FUNCTION:
295012G2.4.34 High Drywell Temperature / 5 295013AA2.02 High Suppression Pool Temp. /5 295033EA2.03 High Secondary Containment Area Radiation Levels / 9 SRO T1G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.1 DDDDD D[JDD~
This is a Generic, no stem statement is associated.
3.2 3.5 D D D [1 D D~DD 3.7 4.2 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/
45.13)
D DDD
~DDD 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 FORM ES-401-1 TOPIC:
Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Localized heating/stratification......................
Cause of high area radiation.........................
10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
206000A2.16 HPCI 212000A2.20 RPS
,---,--.. -------~------.~---.-
217000G2.4.41 RCIC 239002G2.4.45 SRVs 261000A2.11 SGTS SRO T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4
4.1 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) 4.1 4.2 0 2.9 4.6 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 DIi'l This is a Generic, no stem statement is associated.
4.1 4.3 11 11 n 11 n i-I n n n n
~
This is a Generic, no stem statement is associated.
3.2 3.3 0 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 FORM ES-401-1 TOPIC:
High drywell pressure: BWR-2,3,4 Full system activation (full-SCRAM)
Knowledge of the emergency action level thresholds and classifications.
Ability to prioritize and interpret the significance of each annunciator or alarm.
High containment pressure 10/2212008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
206000A2.16 HPCI 212000A2.20 RPS 217000G2.4.41 RCIC 239002G2.4.45 SRVs 261000A2.11 SGTS SRO T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4
4.1 0 0
[] 0 ~ 0 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) 4.1 4.2 0 0 OljDO~OO 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)
FORM ES-401-1 TOPIC:
High drywell pressure: BWR-2,3,4 Full system activation (full-SCRAM)
~-.. -
2.9 4.6 o
[JOOl]O OO~
This is a Generic, no stem statement is associated.
4.1 4.3 0 0 0 0 0 [] 0 0 0 0 ~
This is a Generic, no stem statement is associated.
3.2 3.3 0 [1 00
~OOO 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 Knowledge of the emergency action level thresholds and classifications.
Ability to prioritize and interpret the significance of each annunciator or alarm.
High containment pressure 10/2212008 10:15 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
202001 A2.1 0 Recirculation SRO T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.5 3.9 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)
FORM ES-401-1 TOPIC:
Recirculation pump seal failure
.~~~-.--.------~~~--.---.~-----------~-~---~-.--.--.-------------... --- --~.-----.--
215002A2.05 RBM 3.2 3.3 II 1"1 r-l n Ii D D ii'I D D D RBM high or inoperable: BWR-3,4,5 233000G2.4.35 Fuel Pool Cooling/Cleanup 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) 3.8 4.0 i-I n n II n n n n I-I rl ii'I This is a GeneriC, no stem statement is associated.
Page 1 of 1 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 10122/2008 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
202001 A2.1 0 Recirculation 215002A2.05 RBM 233000G2.4.35 Fuel Pool Cooling/Cleanup SRO T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.5 3.9 0 0 0 0 0 0 0 ~ 0 D D 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) 3.2 3.3 D D [J D lJ D D ~ D D D 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)
FORM ES-401-1 TOPIC:
Recirculation pump seal failure RBM high or inoperable: BWR-3,4,5
.~----~~-'~-----'-~---'-'--'-.--.-'-- ----.. -
.. --... ~---.
3.8 4.0
[J D DOD D D DOD ~
This is a Generic, no stem statement is associated.
Page 1 of 1 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 10/22/2008 10:15 AM
ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO G2.1.13 Conduct of operations 2.5 3.2
~
---~~ ------ ------ -.----,,------ _.. _------- --
~-------.------
G2.1.4 Conduct of operations 3.3 3.B 0 D D
D D D D ~
G2.2.19 Equipment Control 2.3 3.4 D
~
G2.2.23 Equipment Control 3.1 4.6 D~
FORM ES-401-1 TOPIC:
Knowledge of facility requirements for controlling vital /
controlled access.
Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license statur, 10CFR55 etc.
Knowledge of maintenance work order requirements.
Ability to track Technical Specification limiting conditions for operations.
G2.3.11 Radiation Control 3.B 4.3 D
DU~
Ability to control radiation releases
-.---------------------------~-.-------.------------ ---.-~-----.----
G2.3.7 Radiation Control 3.5 3.6 D D D D [J D D D D [~
Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.B Emergency Procedures/Plans 3.B 4.5 D
Page 1 of 1 D~
Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
10/221200B 10:15 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.13 Conduct of operations G2.1.4 Conduct of operations SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 3.2 0 0 OC]OOD 3.3 3.B 0 0 o
000 FORM ES-401-1 TOPIC:
Knowledge of facility requirements for controlling vital /
controlled access.
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 0 0 0 0
~
Knowledge of maintenance work order requirements.
G2.2.23 Equipment Control
.-------.---::---c-----
G2.3.11 Radiation Control G2.3.7 Radiation Control 3.1 4.6 o
DO OO~
Ability to track Technical Specification limiting conditions for operations.
.... _----- -- -----------.. -------------.-.-.. -~-
3.B 4.3 0 0 0 0 0 COO ~
Ability to control radiation releases 3.5 3.6 000 o [J D 0 0 0
[~
Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.B Emergency Procedures/Plans 3.B 4.5 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
10/221200B 10:15 AM