ML101031000
| ML101031000 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/14/2010 |
| From: | Harris B License Renewal Projects Branch 1 |
| To: | Division of License Renewal |
| Harris B | |
| References | |
| Download: ML101031000 (4) | |
Text
April 14, 2010 MEMORANDUM TO:
File FROM:
Brian K. Harris, Project Manager
/RA/
Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation
SUBJECT:
DOCKETING OF APRIL 6, 2010, NUCLEAR REGULATORY COMMISSION TELECONFERENCE NOTES PERTAINING TO THE LICENSE RENEWAL OF THE DUANE ARNOLD ENRGY CENTER This memorandum makes the following enclosed correspondence publicly available:
NRC License Renewal Teleconference - April 6, 2010 Docket No. 50-331
Enclosure:
As stated
Ml101031000 OFFICE LA:DLR PM:RPB2:DLR NAME IKing BHarris DATE 04/14/10 04/14/10
ENCLOSURE Summary of Discussion Date: 4/6/2010 Time: 2:00 EST Location: Telephone
Participants:
NRC FPLE/DAEC Brian Harris Ken Putnam On Yee Clara Rushworth Allen Hiser Topic: License renewal questions from the U.S. Nuclear Regulatory Commission (NRC) review of the license renewal application (LRA)
References:
None Main Points of Discussion:
Metal Fatigue of Reactor Vessel Coolant Pressure Boundary Program Based on a teleconference with the NRC Staff on April 6, 2010, the following is provided as clarification to the Duane Arnold Energy Center (DAEC) response to RAI 4.3.4-3, Item 2.
The numbers of vessel thermal and pressure transient cycles are tracked via a surveillance test procedure that is performed on a cyclic basis. Cycles that are inputs to the vessel fatigue evaluations are manually counted to ensure that the actual numbers of these cycles are less than the numbers used to determine the usage factors. This ensures that the usage factors remain below the calculated values and that design limits on fatigue usage are not exceeded. If the number of transient cycles approaches the number of cycles used in the fatigue calculation, the fatigue calculation would be evaluated and revised as needed.
As shown in LRA Table 4.3.6-1, Summary of EAF Evaluation Results for DAEC, the Recirculation Inlet Nozzle Safe End, Feedwater Nozzle Safe End, and Core Spray Nozzle Safe End are Nickel Alloy components. In the future, if the environmental fatigue calculations for these three Safe Ends are revised or updated, Fen data for Nickel Alloy from the methodology that is described in NUREG/CR-6909 will be used in the determination of usage factors.
Item No.
- System, Component or Program Commitment Section Schedule 51 Metal Fatigue of Reactor Vessel Coolant Pressure Boundary Program Future revisions/updates to the environmental fatigue calculations for the Recirculation Inlet Nozzle Safe End, Feedwater Nozzle Safe End, and Core Spray Nozzle Safe End will use Fen data for Nickel Alloy from the methodology that is described in NUREG/CR-6909 in the determination of usage factors.
18.2.2 Upon calculation revision.