ML092110125
| ML092110125 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/30/2009 |
| From: | Justin Poole Plant Licensing Branch III |
| To: | Jim Costedio, Hale S Florida Power & Light Co, Point Beach |
| Poole Justin/DORL/LPL3-1/ 301-415-2048 | |
| References | |
| Download: ML092110125 (2) | |
Text
From:
Poole, Justin Sent:
Thursday, July 30, 2009 9:46 AM To:
'Steve_Hale@fpl.com'; COSTEDIO, JAMES
Subject:
Electrical questions for today's call Sorry its late but at least you will have something to look at.
Justin C. Poole Project Manager NRR/DORL/LPL3-1 U.S. Nuclear Regulatory Commission (301)415-2048 email: Justin.Poole@nrc.gov
- 1. Provide the loading sequence for each emergency diesel generator (EDG) at Point Beach Nuclear Plant (PBNP). In your response, describe the changes that have been made to the EDG loading sequence to support this license amendment request (LAR).
- 2. Describe how the loads being added to the PBNP EDGs (i.e., control room emergency filtration system and primary auxiliary building ventilation system (VNPAB) components) affect the capability and capacity of the EDGs (e.g., describe the impact of the proposed change on the EDG ratings).
- 3. Given that the VNPAB is a non-safety related system, describe how this system will be electrically separated from the safety-related system (i.e., provide a detailed discussion on how a fault on the non-Class 1E electrical circuit will not propagate to the Class 1E electrical circuit). Also describe the independence (e.g., electrical and physical separation) and redundancy of these systems.
- 4. Describe how the CREFS and VNPAB meet the single failure criterion.
- 5. Describe how the operators will be notified in the event that either the CREFS or the VNPAB would become inoperable (e.g., control room annuciators).
- 6. Provide a list and description of components being added to your 10 CFR 50.49 program due to this LAR. Confirm that these components are qualified for the environmental conditions they are expected to be exposed to.
- 7. The licensee proposed utilizing the containment spray (CS) during the sump recirculation phase, if required due to radiological conditions and/or core damage. In addition, the licensee proposed modifying the CS and residual heat removal (RHR) systems to provide throttling capability of CS and RHR during the emergency core cooling system (ECCS) recirculation phase. Describe the impact of the above proposed actions on environmental conditions (such as temperature, pressure) and any impact on equipment qualification (EQ).
- 8. The licensee has submitted EPU and AFW modification submittals. Describe any impact of these submittals on AST LAR.
- 9. The licensee stated that the radiation monitors actuation signals are diverse and that the radiation monitors are of augmented quality status. The licensee also stated that VNPAB components credited for AST will be upgraded to an augmented quality status. Explain, what is meant by augmented quality status?
- 10. The licensee stated that boron concentration in the RWST is conservatively assumed to be 3500 ppm. Explain the basis for this assumption. In your response describe the change in chemical composition of the chemical spray and its impact on EQ.
E-mail Properties Mail Envelope Properties ()
Subject:
Electrical questions for today's call Sent Date: 7/30/2009 9:45:29 AM Received Date: 7/30/2009 9:46:00 AM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:
Steve_Hale@fpl.com ('Steve_Hale@fpl.com')
Tracking Status: None JAMES.COSTEDIO@nexteraenergy.com (COSTEDIO, JAMES)
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 14409 7/30/2009 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: