Q83 — Control Room Evacuation / EOPs and SG Pressure
T1G2 APE 68 G2.4.20 (4.3)
Given:
• BOTH Salem Control Rooms have been evacuated due to toxic gas
Per S2.OP-AB.CR-0001, Control Room Evacuation, which of the following completes both statements?
1. EOPs (1) applicable during Control Room Evacuation.
2. The "Caution" statement in Attachment 3 alerts the CRS to monitor SG pressures at the Hot Shutdown Panel to avoid (2).
• BOTH Salem Control Rooms have been evacuated due to toxic gas
Per S2.OP-AB.CR-0001, Control Room Evacuation, which of the following completes both statements?
1. EOPs (1) applicable during Control Room Evacuation.
2. The "Caution" statement in Attachment 3 alerts the CRS to monitor SG pressures at the Hot Shutdown Panel to avoid (2).
A. (1) are NOT — (2) exceeding Tech Spec RCS cooldown rate of 100 degrees F per hour
B. (1) are NOT — (2) Safety Injection on steam line differential pressure
C. (1) are — (2) exceeding Tech Spec RCS cooldown rate of 100 degrees F per hour
D. (1) are — (2) Safety Injection on steam line differential pressure
▶ Show Answer & Explanation
✓ B. Correct. Per the Note in section 2.0 Immediate Actions in S2.OP-AB.CR-0001, EOPs are NOT applicable during Control Room Evacuation. EOPs should be used for information only or as directed by the TSC while performing this procedure. The CRS will monitor SG pressures at the Hot Shutdown Panel IAW Attachment 3 step 5.0. A Caution statement in step 5.0 cautions the CRS that a steam line differential pressure SI may occur if DP exceeds 100 psi differential pressure.
✗ A. Plausible because the SRO may believe that TS limit of 100 degrees F per hour still applies in this procedure. Incorrect in that the RCS cooldown limit is 25 degrees F per hour IAW Attachment 3 step 24.0.
✗ C. Plausible because EOP-TRIP-1 is the typical procedure to enter following a reactor trip. Plausible because the SRO may believe that TS limit of 100 degrees F per hour still applies in this procedure. Incorrect in that the RCS cooldown limit is 25 degrees F per hour IAW Attachment 3 step 24.0.
✗ D. Plausible because EOP-TRIP-1 is the typical procedure to enter following a reactor trip.
Ref: S2.OP-AB.CR-0001 (R24) | LO: NOS05ABCR01-06, Obj 2 — Describe, in general terms, the actions taken in S1/S2.OP-AB.CR-0001 and the bases for the actions | Source: New | Cognitive: Comprehension/Analysis
Connections
- Related systems: Steam Generator & Blowdown, RPS/SSPS
- Related procedures: AB.CR-0001 — Control Room Evacuation, EOP-TRIP-1
- Related exam: 2023 NRC Written Exam