ML22250A674

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Form 3.2-1 Admin Topics Outline DC-Cook 2022
ML22250A674
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/30/2022
From: Ted Wingfield
NRC/RGN-III/DRS/OLB
To:
Indiana Manufacturing, Indiana Michigan Power Co
Wingfield T
Shared Package
ML21263A038 List:
References
Download: ML22250A674 (3)


Text

Form 3.2-1 Administrative Topics Outline ES-3.2 Facility: DC Cook Date of Examination:

7/2022 Examination Level: RO SRO Operating Test Number:

Cook 2022 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations Perform Boron Volume Determination for RCS Temperature Change per 02-OHP-4021-005-002.

KA 2.1.43 / 4.1, Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion P-D-R Conduct of Operations Perform 1/M Plot of data from Reactor Start up KA 2.1.07 / 4.4, Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation N-R Equipment Control Determine the Requirements for Isolating a PAC Cooler NESW Leak KA 2.2.13 / 4.1, Knowledge of tagging and clearance procedures D-R Radiation Control Determine Locked High Radiation Area (LHRA)

Entry Requirements KA 2.3.12 / 3.2, Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters D-R Emergency Plan

Form 3.2-1 Administrative Topics Outline ES-3.2 Facility: DC Cook Date of Examination:

7/2022 Examination Level: RO SRO Operating Test Number:

Cook 20200 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations Review Reactor Vessel Void Time Calculation KA 2.1.25 / 4.2, Ability to interpret reference materials, such as graphs, curves, and tables (reference potential)

D-R Conduct of Operations Determine if Core Alterations Can Continue KA 2.1.40 / 3.9, Knowledge of refueling administrative requirements P-D-R Equipment Control Review Unit 2 LTOP Verification KA 2.2.42 / 4.6, Ability to recognize system parameters that are entry-level conditions for TS D-R Radiation Control Review and Authorize a Waste Gas Release Permit K/A 2.3.6 / 3.8 Ability to approve liquid or gaseous release permits D-R Emergency Plan Determine if PAR required and determine PAR KA 2.4.44 / 4.4, Knowledge of emergency plan implementing procedures protective action recommendations M-R

ES-3.2 Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

Topic Number of JPMs

  • Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics part of the operating test (with a waiver or excusal of the other portions).

RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.
3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams (D)irect from bank (no more than three for ROs, no more than four for senior reactor operators (SROs) and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)