ML17069A406

Op Test Retake - Final Outlines (Folder 3)

ML17069A406
Person / Time
Site:	Calvert Cliffs
Issue date:	02/09/2017
From:	Constellation Energy Group
To:	NRC Region 1
Shared Package
ML16326A203	List: IR 05000317/2017301 ML17034A384 ML17069A403 ML17069A404 ML17069A405 ML17069A406 ML17069A407 ML17072A398 ML17090A364
References
U01967
Download: ML17069A406 (2)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Calvert Cliffs Nuclear Power Plant Exam Level: SRO-I Date of Examination:

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. 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 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 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 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 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) 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.

(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)

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

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