ML17069A406

From kanterella
Jump to navigation Jump to search
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)


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