ML12090A883
| ML12090A883 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/30/2012 |
| From: | On Yee Division of License Renewal |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| Shared Package | |
| ML12090A878 | List: |
| References | |
| RAS 22164, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | |
| Download: ML12090A883 (2) | |
Text
NRC000104 Submitted: March 30, 2012 Statement of Professional Qualifications On Yee, Mechanical Engineer, Aging Management of Reactor Systems and Guidance Update Branch Division of License Renewal, Office of Nuclear Reactor Regulation, U.S, Nuclear Regulatory Commission Summary Mr. Yee is a Mechanical Engineer in the Division of License Renewal, Aging Management of Reactor Systems and Guidance Update Branch, in the Office of Nuclear Reactor Regulation.
His official responsibilities include the technical, safety, and regulatory compliance reviews of a variety of mechanical engineering topics, including metal fatigue time-limited aging analyses and fatigue monitoring programs for applicants for license renewal.
Education:
B.S. Mechanical Engineering, Polytechnic University, Brooklyn, NY, 2005 Experience:
2007 - Present: Mechanical Engineer, USNRC Headquarters Qualified License Renewal Technical Auditor: September 22, 2009 Qualified Team Leader: September 22, 2009 Performed reviews of multiple license renewal applications ("LRA"), including Indian Point Energy Center, Beaver Valley Power Station, Kewaunee Power Station, Crystal River Unit 3, Wolf Creek Generating Station, Cooper Nuclear Station and Duane Arnold Energy Center. Mr.
Yee's work in the area of metal fatigue included auditing program basis documents, reviewing and assessing the relevant information in license renewal applications ("LRA"), and crafting requests for additional information when the LRA lacked information.
His review included the licensees metal fatigue time-limited aging analyses of reactor vessel internals, ASME Code Class 1, 2 and 3 components, ANSI B31.1 "Power Piping" components, reactor coolant environment effects on fatigue life of reactor coolant pressure boundary components and piping. The reviews he performed enabled the NRC to determine if how the licensees addressed metal fatigue, how the licensee proposed to address metal fatigue and the adequacy of any proposed aging management program (i.e. the fatigue management program).
He assessed how licensees used the guidance in NUREG/CR-6260, Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, NUREG/CR-5704, Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels, NUREG/CR-6583, Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels and NUREG/CR-6909, Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials. Further, his reviews also considered NUREG-1800 Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants and NUREG-1801 Generic Aging Lessons Learned (GALL) Report to determine if the LRA demonstrated that the effects of aging will be adequately managed and meet the rules in 10 C.F.R. Part 54.
His primary work products include requests for additional information, audit reports and input to the draft and final safety evaluation reports. He was also a member of the on-site audit teams which evaluated the licensee's aging management reviews and aging management programs.
The results of his reviews on metal fatigue are captured in the Staff's documents, including
NUREG-1958 Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station, NUREG-1961 Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Units 1, 2, and 3, NUREG-1930 Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3, NUREG-2101 Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station and NUREG-2102 Safety Evaluation Report Related to the License Renewal of Hope Creek Generating Station.
2005-2007: Nuclear Safety Professional Development Program Performed rotational assignments in a variety of engineering disciplines, including mechanical engineering, plant safety systems, and inspection. He reviewed relief requests for In-Service Testing Requirements required by 10 CFR 50.55a(f) to determine if the licensees proposed alternative is in accordance with 10 CFR 50.55a(a)(3)(i) (the proposed alternative provides acceptable level of quality and safety) or 10 CFR 50.55a(a)(3)(ii), (compliance with the requirements results in hardship or unusual difficulty without a compensating increase in the level of quality and safety). Assignment to the Region I Office to assist in performing regional inspections. He participated in a Component Design Basis Inspection at the James A.
Fitzpatrick Nuclear Plant that was performed in accordance with Inspection Procedure (IP) 71111.21 Component Design Bases Inspection. He reviewed design basis and severe accident venting calculations, drawings, inservice test results, applicable design basis documents, and system health reports to ensure an air operated valve (AOV) will operate during design basis events, transient and accident conditions. He also participated in a Triennial Fire Protection Inspection at the Limerick Generating Station that was performed in accordance with IP 71111.05T Fire Protection (Triennial), in which he reviewed licensee procedures and programs to assess their effectiveness in preventing fires and controlling combustible loading within limits established in the fire hazard analysis. He assessed these documents to ensure they included appropriate reviews and controls to assess plant changes for potential impacts on the fire protection program and post-fire safe shutdown analysis and procedures. His input for these inspections are documented in Inspection Report No. 05000333/2007006 for the James A. Fitzpatrick Nuclear Plant and Inspection Report No. 05000352/2007006 and 05000353/2007006 for the Limerick Generating Station