ML11263A204
| ML11263A204 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/20/2011 |
| From: | Jason Paige Plant Licensing Branch II |
| To: | Hale S Florida Power & Light Co |
| References | |
| Download: ML11263A204 (3) | |
Text
1 NRR-PMDAPEm Resource From:
Paige, Jason Sent:
Tuesday, September 20, 2011 12:12 PM To:
Hale, Steve Cc:
Tiemann, Philip; Abbott, Liz
Subject:
Turkey Point EPU - Reactor Systems (SRXB) Requests for Additional Information - Round 2.3 (Part 3)
Steve, Below are follow-up requests for additional information (RAIs) regarding the Turkey Point Extended Power Uprate license amendment request. On September 19, 2011, the Nuclear Regulatory Commission (NRC) staff and Florida Power & Light Company (FPL) discussed draft RAIs to gain a common understanding of the questions. The below RAIs reflect the questions discussed during the September 19, 2011, call. FPL agreed upon providing its responses within 30 days of the date of this email. If you have any questions, feel free to contact me.
SRXB-2.3.1 In the Turkey Point Nuclear (PTN) Final Safety Analysis Report (FSAR) Chapter 3, Reactor, Section 3.1, Design Basis, it is stated, the Reactor Control and Protection System is designed to actuate a reactor trip for any anticipated combination of plant conditions, when necessary, to ensure a minimum Departure from Nucleate Boiling (DNB) ratio greater than or equal to the DNBR limit of the applicable DNB correlation.
The equation for the overtemperature delta-T (OTT) trip setpoint includes a differential pressure compensation term, which adjusts the trip setpoint based on deviations from the nominal reactor pressure. The setpoint is lowered when the reactor pressure is less than nominal, because a lower pressure decreases the subcooling margin. It is necessary to validate the DNB-protective function against both transients that increase the reactor heat flux, such as rod cluster control assembly withdrawal errors, and transients that reduce reactor pressure, such as a spurious power-operated relief valve or safety valve opening.
While in your response to RAI SRXB-1.3.29 asserts that the OTT trip provides the requisite protection, it is without a valid safety analysis on which to base this assertion. Demonstrate that this claim is true. A supporting analysis is necessary in order to conclude that the trip setpoint proposed for TS 2.2, Functional Unit 5, has been so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded, consistent with the requirement promulgated by 10 CFR 50.36(c)(1)(ii)(A).
SRXB-2.3.2 Licensing Report §2.8.5.2.4, Feedwater System Pipe Breaks Inside and Outside Containment, states that feedwater system pipe breaks are not required to be analyzed per the PTN current licensing basis.
Generally, the feedwater line break (FWLB) analysis results are used to:
(1) determine the performance requirements of the auxiliary feedwater system, as a post-trip decay heat removal system, under the conditions/configuration that would exist following a FLWB, (2) set the low steam generator water level reactor trip setpoint, (3) determine the error allowance, on the low steam generator water level reactor trip setpoint, needed to compensate for the hostile environment that could be created by the break flow from a FWLB occurring inside containment,
2 (4) verify the capability to establish and maintain natural circulation cooling by showing that saturation conditions are not created inside the reactor coolant system, by a FWLB, and (5) show that the core remains covered and that the integrity of the reactor coolant system pressure boundary is maintained during a FWLB (i.e., when there is water relief though the pressurizer safety valves).
For the Turkey Point units, provide this information, from the results of a FLWB analysis, or from another, equivalent source/method.
Jason Paige, Turkey Point Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: (301) 415-5888
Hearing Identifier:
NRR_PMDA Email Number:
152 Mail Envelope Properties (Jason.Paige@nrc.gov20110920121100)
Subject:
Turkey Point EPU - Reactor Systems (SRXB) Requests for Additional Information - Round 2.3 (Part 3)
Sent Date:
9/20/2011 12:11:47 PM Received Date:
9/20/2011 12:11:00 PM From:
Paige, Jason Created By:
Jason.Paige@nrc.gov Recipients:
"Tiemann, Philip" <Philip.Tiemann@fpl.com>
Tracking Status: None "Abbott, Liz" <Liz.Abbott@fpl.com>
Tracking Status: None "Hale, Steve" <Steve.Hale@fpl.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3802 9/20/2011 12:11:00 PM Options Priority:
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