Text

3.2-2 Control Room In-Plant Systems Outline
	ML23038A153
Person / Time
Site:	Perry
Issue date:	01/12/2023
From:	; NRC/RGN-III/DORS/OB
To:	;
	Greg Roach
Shared Package
ML21188A232	List: ML23038A143; ML23038A145; ML23038A148; ML23038A151; ML23038A153; ML23038A155; ML23038A156;
References
	Download: ML23038A153 (12)
	v • d • e

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: Perry Date of Examination: 12/12/2022 Operating Test Number: 2022-1 Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems

a. OT-3701-B33_505_RO - Restart FCV B HPU 202002 Recirculation Flow Control System: A4 - Ability to manually operate and/or monitor in the control room: A4.02 -

Hydraulic power unit (BWR 5, 6) IR: RO 3.4 and A4.11 -

System lockups/lockouts. IR: RO 3.8 A, N, S 1

b. OT-3701-E51_503_RO - Reinitiate RCIC 217000 RCIC Reactor Core Isolation Cooling: K3 - Knowledge of the effect that a loss or malfunction of the Reactor Core Isolation Cooling System will have on the following systems or system parameters: K3.01 - Reactor water level. IR: RO 4.2 and A4 - Ability to manually operate and/or monitor in the control room: A4.02 - Turbine trip throttle valve reset. IR: RO 4.0 A, E, L, N, S 2

c. OT-3701-B21_008_RO - Slow Close MSIV 239001 Main and Reheat Steam System: A4 - Ability to manually operate in the control room: A4.01 - MSIVs.

IR: RO 4.4.

D, S 3

d. OT-3701-E12_507_RO - Shift RHR Loop A from Cont Spry to Supp Pool Cooling 203000 RHR/LPCI: Injection Mode: A2 - Ability to (a) predict the impacts of the following on the RHR/LPCI: Injection Mode and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: A2.02 - Pump trips. IR: RO 4.0 Perry 2021 Exam A, D, E, EN, L, P, S 4

e. OT-3701-G43_001_RO - Initiate SPMU per EOP-SPI 3.2 295030 Low Suppression Pool Water Level: EA1 - Ability to operate and/or monitor the following as they apply to Low Suppression Pool Water Level: EA1.04 - Suppression pool make-up system(s). IR: RO 3.5 D, E, EN, L, S 5

f. OT-3701-R10_002_RO - Energize Buses L10 and TH21 295003 Partial or Complete Loss of AC Power: AA1 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: AA1.01 - A.C.

electrical distribution system. IR: 4.0 C, D 6

g. OT-3701-C71_003_RO - Bypass RPS Channels A/C & B/D automatic scrams 212000 RPS Reactor Protection System: K4 - Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following: K4.12 - Bypassing SCRAM signals. IR: RO 3.8 D, L, S 7

h. OT-3701-M25_502_RO - Shift Control Room Ventilation to Normal from Emergency Recirc 290003 Control Room Ventilation: A2 - Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.03 - Initiation/reconfiguration failure. IR: RO 3.5 A, D, EN, S 9

In-Plant Systems

i.

OT-3701-C41_008_RO - Perform Alternate Boron Injection into RPV per EOP-SPI 1.8 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: EA1 - Ability to operate and/or monitor the following as they apply to Scram Condition Present And Reactor Power Above APRM Downscale Or Unknown. EA1.10 - Systems used for alternate boron injection. IR: RO 3.7 D, E, L, R 1

j.

OT-3701-E22B_001_RO - Place Div. 3 Starting Air System in single compressor operations 264000 Emergency Generators: K6 - Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Emergency Generators: K6.01

- Starting air components. IR: RO 3.8 D, E 6

k. OT-3701-P54_505_RO - Manually Initiate Div. 1 DG Room CO2 286000 Fire Protection System: A2 - Ability to (a) predict the impacts of the following on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.08 - Failure to actuate when required.

IR: RO 3.7 A, D, E, R 8

Form 3.2-2 Instructions for Control Room/In-Plant Systems Outline

1. Determine the number of control room system and in-plant system job performance measures (JPMs) to develop using the following table:

License Level Control Room In-Plant Total Reactor Operator (RO) 8 3

11 Senior Reactor Operator-Instant (SRO-I) 7 3

10 Senior Reactor Operator-Upgrade (SRO-U) 2 or 3 3 or 2 5

2. Select safety functions and systems for each JPM as follows:

Refer to Section 1.9 of the applicable knowledge and abilities (K/A) catalog for the plant systems organized by safety function. For pressurized-water reactor operating tests, the primary and secondary systems listed under Safety Function 4, Heat Removal from Reactor Core, in Section 1.9 of the applicable K/A catalog, may be treated as separate safety functions (i.e., two systems, one primary and one secondary, may be selected from Safety Function 4). From the safety function groupings identified in the K/A catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicants license level (see the table in step 1).

For RO/SRO-I applicants: Each of the control room system JPMs and, separately, each of the in-plant system JPMs must evaluate a different safety function, and the same system or evolution cannot be used to evaluate more than one safety function in each location. One of the control room system JPMs must be an engineered safety feature.

For SRO-U applicants: Evaluate SRO-U applicants on five different safety functions.

One of the control room system JPMs must be an engineered safety feature, and the same system or evolution cannot be used to evaluate more than one safety function.

3. Select a task for each JPM that supports, either directly or indirectly and in a meaningful way, the successful fulfillment of the associated safety function. Select the task from the applicable K/A catalog (K/As for plant systems or emergency and abnormal plant evolutions) or the facility licensees site-specific task list. If this task has an associated K/A, the K/A should have an importance rating of at least 2.5 in the RO column. K/As that have importance ratings of less than 2.5 may be used if justified based on plant priorities; inform the NRC chief examiner if selecting K/As with an importance rating less than 2.5.

The selected tasks must be different from the events and evolutions conducted during the simulator operating test and tasks tested on the written examination. A task that is similar to a simulator scenario event may be acceptable if the actions required to complete the task are significantly different from those required in response to the scenario event.

Apply the following specific task selection criteria:

Form 3.2-2 Instructions for Control Room/In-Plant Systems Outline (continued)

At least one of the tasks shall be related to a shutdown or low-power condition.

Four to six of the tasks for RO and SRO-I applicants shall require execution of alternative paths within the facility licensees operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensees operating procedures.

At least one alternate path JPM must be new or modified from the bank.

At least one of the tasks conducted in the plant shall evaluate the applicants ability to implement actions required during an emergency or abnormal condition.

At least one of the tasks conducted in the plant shall require the applicant to enter the radiologically controlled area. This provides an excellent opportunity for the applicant to discuss or demonstrate radiation control administrative subjects.

If it is not possible to develop or locate a suitable task for a selected system, return to step 2 and select a different system.

4. For each JPM, specify the codes for type, source, and location:

Code License Level Criteria RO SRO-I SRO-U (A)lternate path 4-6 4-6 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 (for control room system) 1 1

1 (L)ow power/shutdown 1

1 1

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 2 2

1 (P)revious two exams (randomly selected) 3 3

2 (R)adiologically controlled area 1

1 1

(S)imulator