ML23079A177
| ML23079A177 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/17/2022 |
| From: | NRC/RGN-III/DORS/OB |
| To: | Exelon Generation Co |
| Theodore Wingfield | |
| Shared Package | |
| ML22125A065 | List: |
| References | |
| Download: ML23079A177 (1) | |
Text
Form 3.2-2 Control Room/In-Plant Systems Outline Facility: Quad Cities Date of Examination: 1/30/2023 Operating Test Number: ILT 21-1 Exam Level: RO SRO-I
~ SRO-U System/JPM Title Type Code Safety Function Control Room Systems
- a. Uncoupled Control Rod During CRD Weekly Exercise A,N,S 1
[Control Rod and Drive Mechanism 201003 A2.02 4.4/4.1]
- b. Place the FWLC System in Local Single Element Control N,S 2
[Feedwater System 259001 A4.04 3.4]
- c. Adjust Turbine Generator Load Set D,S 3
[Reactor/Turbine Pressure Regulating System 241000 A4.15 3.7]
- d. Control Reactor Pressure with RCIC A,D,S 4
[Reactor Core Isolation Cooling System 217000 A4.03 3.8]
- e. Energize 480 VAC Bus 15 with a Failure of the Normal Feed A,N,S 6
Breaker using the Bus 15 to Bus 16 Tie ACB
[A.C. Electrical Distribution 262001 A4.01 3.7]
- f. IRM Detector NOT FULL IN Position Rod Block Functional N,L,S 7
Test
[Intermediate Range Monitor System 215003 A4.06 3.4]
- g. Perform SBGT Monthly Operability Test with a Heater Failure A,D,EN,S 9
after Shutdown
[Standby Gas Treatment System 261000 A3.04 3.1]
In-Plant Systems
[SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: 295037 EK3.07 4.2]
[Control Room Ventilation 290003 2.1.20 4.6/4.6]
- k. Energize B RPS with Normal Power D
7
[Reactor Protection System 212000 2.1.30 4.4/4.0]
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- 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 7
3 10 (SRO-I)
Senior Reactor Operator-Upgrade 2 or 3 3 or 2 5
(SRO-U)
- 2. Select safety functions and systems for each JPM as follows:
Refer to Section 1.9 of the applicable knowledge and abilities (Kl 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 KIA 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 KIA catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicant's 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 KIA catalog (KIAs for plant systems or emergency and abnormal plant evolutions) or the facility licensee's site-specific task list. If this task has an associated KIA, the KIA should have an importance rating of at least 2.5 in the RO column. Kl 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 Kl 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:
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 licensee's operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensee's 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 applicant's 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (for control room svstem)
(L)ow power/shutdown (N)ew or (M)odified from bank (must apply to at least one alternate path JPM)
(P)revious two exams (randomly selected)
(R)adiologicallv controlled area (S)imulator RO 4-6 S9
.!: 1
.!: 1
.!: 1
.!: 2 S3
.!: 1 License Level Criteria SRO-I SRO-U 4-6 2-3 sa S4
.!: 1
.!: 1
.!: 1
.?: 1
.!: 1
.!: 1
.!:2
.?: 1 s 3 s 2
.!: 1
.?: 1