ML100560319
| ML100560319 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-024, DPR-027) |
| Issue date: | 02/25/2010 |
| From: | Justin Poole Plant Licensing Branch III |
| To: | Jim Costedio, Hale S Point Beach |
| Poole Justin/DORL/LPL3-1/ 301-415-2048 | |
| References | |
| Download: ML100560319 (3) | |
Text
From:
Poole, Justin Sent:
Thursday, February 25, 2010 11:26 AM To:
'Hale, Steve'; COSTEDIO, JAMES
Subject:
DRAFT - Request for Additional Information RE: EPU Steve By letter to the U.S. Nuclear Regulatory Commission (NRC) dated April 7, 2009 (Agencywide Documents Access and Management System Accession No. ML091250564), FPL Energy Point Beach, LLC, submitted a request to increase each units licensed core power level from 1540 megawatts thermal (MWt) to 1800 MWt reactor core power, and revise the technical specifications to support operation at this increased core thermal power level.
The Containment and Ventilation Branch has reviewed the information provided and determined that in order to complete its evaluation, additional information is required. We would like to discuss the questions, in draft form below, with you in a conference call.
This e-mail aims solely to prepare you and others for the proposed conference call. It does not convey a formal NRC staff position, and it does not formally request for additional information.
Justin C. Poole Project Manager NRR/DORL/LPL3-1 U.S. Nuclear Regulatory Commission (301)415-2048 email: Justin.Poole@nrc.gov
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DRAFT RAI SCVB-1: Bypass valves are occasionally installed across large isolation valves to permit pressure equalization prior to opening the larger valve. The staff has determined that startup bypass valves installed around the new Main Feedwater Isolation Valves should be included in Technical Specification (TS) 3.7.3. Are MFIV bypass valves being installed with the new MFIVs?
RAI SCVB-2: TS Surveillance Requirement (SR) 3.7.3.2 is being revised to verify MFIV, main feedwater regulating valve (MFRV), and MFRV bypass valve isolation time is within limits.
Provide justification or indicate where the justification has been previously submitted why the required closing time limits are not included in the surveillance requirement acceptance criteria.
RAI SCVB-3: Point Beach Nuclear Plant (PBNP) general design criterion (GDC) 57 requires that the capability shall be provided to the extent practical for testing functional operability of valves and associated apparatus essential to the containment function for establishing that no failure has occurred and for determining that valve leakage does not exceed acceptable limits.
In order to mitigate the consequences of a design basis main steam line break (MSLB) in containment at EPU conditions, FPL Energy Point Beach determined isolation of feedwater (FW) to the faulted steam generators is required to minimize the mass and energy released to containment. To reduce the mass and energy releases, a new Main Feedwater Isolation Valve (MFIV) with an automatically actuated operator is being added to each main feedwater line outside containment. The new MFIVs are designed to fully close in < 5 seconds to meet the
containment integrity steam line break safety analysis requirements. Provide a discussion or indicate where a justification has been previously submitted why MFIV leakage limits are not verified by a TS surveillance requirement.
RAI SCVB-4: Attachment 5, EPU Licensing Report, of the licensing action request, refers to the new MFIVs as safety-grade. Is safety-grade the same as safety-related? Are their design, procurement, and installation being performed under the PBNP 10 CFR 50 Appendix B Quality Assurance Program?
RAI SCVB-5: Provide a discussion regarding the effect of a shock or pressure wave from a large break loss-of-coolant accident (LOCA) with EPU on the structural capability of the containment ventilation system with and without a loss of offsite power. What is the maximum pressure differential across the housing?
RAI SCVB-6: Provide a discussion regarding the effect of a shock or pressure wave from a large break LOCA with EPU on the containment ventilation fan. Is there any potential to over speed the fan?
RAI SCVB-7: Section 2.6.1.2.4 of attachment 5, EPU Licensing Report, of the licensing action request, states the limiting containment pressure case for the EPU is a large double-ended rupture of the main steam line break initiated from 30% power with a single failure of the feedwater isolation valve. What is the peak containment pressure and temperature for the EPU with a large double-ended rupture of the main steam line initiated at 100% power with a single failure of the feedwater isolation valve?
DRAFT