ML17069A406: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(2 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML17069A406
| number = ML17069A406
| issue date = 02/09/2017
| issue date = 02/09/2017
| title = Calvert Cliffs Op Test Retake - Final Outlines (Folder 3)
| title = Op Test Retake - Final Outlines (Folder 3)
| author name =  
| author name =  
| author affiliation = Constellation Energy Group, Inc
| author affiliation = Constellation Energy Group, Inc
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:ES-301 Administrative Topics Outline Form ES-301-1 Facility:
{{#Wiki_filter:ES-301                             Administrative Topics Outline                                       Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant                                     Date of Examination: February 2017 Exam Level: SRO-I                                                                           Operating Test No.: 2017 Type Administrative Topic (see Note)                                     Describe activity to be performed Code*
Calvert Cliffs Nuclear Power Plant Exam Level: SRO-I Date of Examination:
Review and approve a completed Surveillance Test Procedure.
February 2017 Operating Test No.: 2017 Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures I Plan Type Code* N,R M,R D,R N,R M,R Describe activity to be performed Review and approve a completed Surveillance Test Procedure.
SRO-Adm in- I: Perform the initial review of a completed STP 210.003.
SRO-Adm in-I: Perform the initial review of a completed STP 210.003. 2.1. 7 -Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.  
Conduct of Operations                      N,R 2.1. 7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (4.7)
(4.7) Verify Estimated Critical Position SRO-Admin-2:
Verify Estimated Critical Position SRO-Admin-2: Review and Approve an Estimated Critical Conduct of Operations                      M,R      Condition using approved plant procedures ..
Review and Approve an Estimated Critical Condition using approved plant procedures  
2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (4.2)
.. 2.1.25 -Ability to interpret reference materials, such as graphs, curves, tables, etc. (4.2) Establish Initial Conditions for STP 0-8A-I SRO-Admin-3:
Establish Initial Conditions for STP 0-8A-I SRO-Admin-3: Establish initial plant conditions for and approve Equipment Control                          D,R performance of an STP 210.001 2.2.12 Knowledge of surveillance procedures (4.1)
Establish initial plant conditions for and approve performance of an STP 210.001 2.2.12 Knowledge of surveillance procedures (4.1) Review and approve a gaseous waste discharge permit. SRO-Admin-4:
Review and approve a gaseous waste discharge permit.
Determine adequacy and quality of waste discharge permit. 2.3.11 Ability to control radiation releases.  
SRO-Admin-4: Determine adequacy and quality of waste Radiation Control                          N,R discharge permit.
(4.3) Determine the appropriate emergency response actions per the ERP IP SRO-Admin-5:
2.3.11 Ability to control radiation releases. (4.3)
Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions 204.097 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.  
Determine the appropriate emergency response actions per the ERP IP SRO-Admin-5: Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant Emergency Procedures I Plan                M,R conditions 204.097 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (4.4)
(4.4) 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.
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, (S)imulator, or Class(R)oom (D)irect from bank (:S 3 for ROs; :S 4 for SROs & RO retakes) l actual (N)ew or (M)odified from bank I) 4 actual (P)revious 2 exams (:S 1; randomly selected) 0 actual ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
* Type Codes & Criteria:               (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:S 3 for ROs; :S 4 for SROs & RO retakes)         l actual (N)ew or (M)odified from bank (~ I)       4 actual (P)revious 2 exams (:S 1; randomly selected)       0 actual
Calvert Cliffs Nuclear Power Plant Date of Examination:
 
Feburary 2017 Exam Level: SRO-I Operating Test No.: 2017 Control Room Systems@ (7 for SRO-I) System I JPM Title Type Safety Code* Function a. Sim-I: Dropped CEA during S/U 00 I .A2.03 Ability to predict impact of malfunction and use procedures to control or mitigate a ANSL I misaligned CEA (3.5, 4.2) b. Sim-2: Override shut a PORV ADSL 002.A2.0I Loss of coolant inventory (4.3, 4.4) 2 c. Sim-3: Depressurize RCS to fill PZR in EOP-5 ANS 0 I 0.A4.0 I Ability to manually operate and/or monitor PZR Spray valves (3 .7, 3.5) EN 3 d. Sim-4: Loss of SR W pump 076.A4.0I Ability to manually operate and/or monitor in the control room the SRW pumps. (2.9, ANS 4 (Secondary) 2.9) e. Sim-5: Respond to a Faulted SIG DS 4 (Primary) 035.A2.0I Faulted or ruptured S/Gs (4.5, 4.6) f. Sim-6: Shift I3 IRU Power Supply 027 A4.0I Ability to manually operate and/or monitor in the control room the IRU controls.  
ES-301                     Control Room/In-Plant Systems Outline                                 Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant                               Date of Examination: Feburary 2017 Exam Level: SRO-I                                                                     Operating Test No.: 2017 Control Room Systems@ (7 for SRO-I)
(3.3, NS EN 5 3.3) g. Sim-7: Energize a 480V Load Center 062.A4.0 I Ability to manually operate and/or monitor 480V breakers from the Control Room (3.3, NS 6 3.1) In-Plant Systems@ 3 for SRO-I h. Plant-I: Control Steam Flow from ADV's locally 039.A2.04 Ability to predict and use procedures to control or mitigate malfunctioning steam EN 4 (Primary) dump(3.4, 3.7) I. Plant-2: Locally control AFW flow during EOP-7 E06 EA I. I Ability to operate and/or monitor components and functions of control and safety EN 4 (Secondary) systems as they apply to the Loss of Feedwater (4.0, 3.9) j. Plant-3: Fill SR W and CC Head Tanks during CR Evacuation EDR 8 008.A2.02 Ability to predict the impact oflow CCW surge tank level and based on those predictions, use procedures to correct, or mitigate the consequences of those malfunctions (3.2,3.5)
Type        Safety System I JPM Title Code*       Function
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for SRO-I Required Actual (A)ltemate path 4-6 4 (C)ontrol room -0 (D)irect from bank :SS 3 (E)mergency or abnormal in-plant 2: I 3 (EN)gineered safety feature -2 (L)ow-Power I Shutdown 2: I 2 (N)ew or (M)odified from bank including I(A) 2: 2 7 (P)revious 2 exams ::; 3 (randomly selected) 0 (R)CA 2: 1 I (S)imulator  
: a. Sim-I: Dropped CEA during S/U 00 I .A2.03 Ability to predict impact of malfunction and use procedures to control or mitigate a         ANSL           I misaligned CEA (3.5, 4.2)
-7}}
: b. Sim-2: Override shut a PORV 002.A2.0I Loss of coolant inventory (4.3, 4.4)                                                           ADSL          2
: c. Sim-3: Depressurize RCS to fill PZR in EOP-5                                                             ANS 3
0 I 0.A4.0 I Ability to manually operate and/or monitor PZR Spray valves (3 .7, 3.5)                       EN
: d. Sim-4: Loss of SR W pump 076.A4.0I Ability to manually operate and/or monitor in the control room the SRW pumps. (2.9,             ANS   4 (Secondary) 2.9)
: e. Sim-5: Respond to a Faulted SIG DS     4 (Primary) 035.A2.0I Faulted or ruptured S/Gs (4.5, 4.6)
: f. Sim-6: Shift I3 IRU Power Supply 027 A4.0I Ability to manually operate and/or monitor in the control room the IRU controls. (3.3,         NS EN         5 3.3)
: g. Sim-7: Energize a 480V Load Center 062.A4.0 I Ability to manually operate and/or monitor 480V breakers from the Control Room (3.3,             NS           6 3.1)
In-Plant Systems@ 3 for SRO-I
: h. Plant-I: Control Steam Flow from ADV's locally 039.A2.04 Ability to predict and use procedures to control or mitigate malfunctioning steam                 EN     4 (Primary) dump(3.4, 3.7)
I. Plant-2: Locally control AFW flow during EOP-7 E06 EA I. I Ability to operate and/or monitor components and functions of control and safety               EN   4 (Secondary) systems as they apply to the Loss of Feedwater (4.0, 3.9)
: j. Plant-3: Fill SR W and CC Head Tanks during CR Evacuation 008.A2.02 Ability to predict the impact oflow CCW surge tank level and based on those                     EDR          8 predictions, use procedures to correct, or mitigate the consequences of those malfunctions (3.2,3.5)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                  *Type Codes                                                       Criteria for SRO-I Required                               Actual (A)ltemate path                                                                 4-6                                     4 (C)ontrol room                                                                     -                                     0 (D)irect from bank                                                               :SS                                     3 (E)mergency or abnormal in-plant                                                 2: I                                     3 (EN)gineered safety feature                                                       -                                     2 (L)ow-Power I Shutdown                                                           2: I                                     2 (N)ew or (M)odified from bank including I(A)                                     2: 2                                     7 (P)revious 2 exams                                                   ::; 3 (randomly selected)                           0 (R)CA                                                                           2: 1                                     I (S)imulator                                                                       -                                     7}}

Latest revision as of 06:54, 30 October 2019

Op Test Retake - Final Outlines (Folder 3)
ML17069A406
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/09/2017
From:
Constellation Energy Group
To:
NRC Region 1
Shared Package
ML16326A203 List:
References
U01967
Download: ML17069A406 (2)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: February 2017 Exam Level: SRO-I Operating Test No.: 2017 Type Administrative Topic (see Note) Describe activity to be performed Code*

Review and approve a completed Surveillance Test Procedure.

SRO-Adm in- I: Perform the initial review of a completed STP 210.003.

Conduct of Operations N,R 2.1. 7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (4.7)

Verify Estimated Critical Position SRO-Admin-2: Review and Approve an Estimated Critical Conduct of Operations M,R Condition using approved plant procedures ..

2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (4.2)

Establish Initial Conditions for STP 0-8A-I SRO-Admin-3: Establish initial plant conditions for and approve Equipment Control D,R performance of an STP 210.001 2.2.12 Knowledge of surveillance procedures (4.1)

Review and approve a gaseous waste discharge permit.

SRO-Admin-4: Determine adequacy and quality of waste Radiation Control N,R discharge permit.

2.3.11 Ability to control radiation releases. (4.3)

Determine the appropriate emergency response actions per the ERP IP SRO-Admin-5: Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant Emergency Procedures I Plan M,R conditions 204.097 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (4.4)

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, (S)imulator, or Class(R)oom (D)irect from bank (:S 3 for ROs; :S 4 for SROs & RO retakes) l actual (N)ew or (M)odified from bank (~ I) 4 actual (P)revious 2 exams (:S 1; randomly selected) 0 actual

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: Feburary 2017 Exam Level: SRO-I Operating Test No.: 2017 Control Room Systems@ (7 for SRO-I)

Type Safety System I JPM Title Code* Function

a. Sim-I: Dropped CEA during S/U 00 I .A2.03 Ability to predict impact of malfunction and use procedures to control or mitigate a ANSL I misaligned CEA (3.5, 4.2)
b. Sim-2: Override shut a PORV 002.A2.0I Loss of coolant inventory (4.3, 4.4) ADSL 2
c. Sim-3: Depressurize RCS to fill PZR in EOP-5 ANS 3

0 I 0.A4.0 I Ability to manually operate and/or monitor PZR Spray valves (3 .7, 3.5) EN

d. Sim-4: Loss of SR W pump 076.A4.0I Ability to manually operate and/or monitor in the control room the SRW pumps. (2.9, ANS 4 (Secondary) 2.9)
e. Sim-5: Respond to a Faulted SIG DS 4 (Primary) 035.A2.0I Faulted or ruptured S/Gs (4.5, 4.6)
f. Sim-6: Shift I3 IRU Power Supply 027 A4.0I Ability to manually operate and/or monitor in the control room the IRU controls. (3.3, NS EN 5 3.3)
g. Sim-7: Energize a 480V Load Center 062.A4.0 I Ability to manually operate and/or monitor 480V breakers from the Control Room (3.3, NS 6 3.1)

In-Plant Systems@ 3 for SRO-I

h. Plant-I: Control Steam Flow from ADV's locally 039.A2.04 Ability to predict and use procedures to control or mitigate malfunctioning steam EN 4 (Primary) dump(3.4, 3.7)

I. Plant-2: Locally control AFW flow during EOP-7 E06 EA I. I Ability to operate and/or monitor components and functions of control and safety EN 4 (Secondary) systems as they apply to the Loss of Feedwater (4.0, 3.9)

j. Plant-3: Fill SR W and CC Head Tanks during CR Evacuation 008.A2.02 Ability to predict the impact oflow CCW surge tank level and based on those EDR 8 predictions, use procedures to correct, or mitigate the consequences of those malfunctions (3.2,3.5)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for SRO-I Required Actual (A)ltemate path 4-6 4 (C)ontrol room - 0 (D)irect from bank :SS 3 (E)mergency or abnormal in-plant 2: I 3 (EN)gineered safety feature - 2 (L)ow-Power I Shutdown 2: I 2 (N)ew or (M)odified from bank including I(A) 2: 2 7 (P)revious 2 exams  ::; 3 (randomly selected) 0 (R)CA 2: 1 I (S)imulator - 7
Retrieved from "https://kanterella.com/w/index.php?title=ML17069A406&oldid=2010163"