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Category:Legal-Exhibit
MONTHYEARIR 05000271/20120082012-04-20020 April 2012 Official Exhibit - NYS000462-00-BD01 - IR 05000271-12-008; 1/9 - 13, 1/23 - 27, and 3/19 - 20/2012; Vermont Yankee Nuclear Power Station; Post Approval Site Inspection for License Renewal 1P71003. ML15331A1572011-12-23023 December 2011 Official Exhibit - NYS000460-00-BD01 - Commitment Charge Process. IR 05000271/20110112011-12-22022 December 2011 Official Exhibit - NYS000459-00-BD01 - IR 05000271-11-011; 10/17/2011 - 12/11/2011; Vermont Yankee Nuclear Power Station; Review of License Renewal Activities. ML0825303982008-09-14014 September 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-28-VY, VY EPRI Checworks Wear Rate Analysis Results Cycles 20 & 21 (2001) ML0825303092008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-16-VY, INPO Report OE-17654 (Clinton) ML0823406802008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-UW_02, Curriculum Vitae of Ulrich Witte ML0825303082008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-15-VY, INPO Report OE-20246 (Clinton) ML0825303072008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-15-VY, INPO Report OE-20246 (Clinton) ML0825303062008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-13-UY, INPO Report OE-17412 (Clinton) ML0825302762008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-06-VY, VY Procedure EN-DC-315 ML0825302732008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-03-VY, Fitzpatrick Cv BVY 04-058, 2008-08/12-Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E3-04-VY Attachment 2 to Supplement 8 to VY EPU Application2008-08-12012 August 2008 2008-08/12-Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E3-04-VY Attachment 2 to Supplement 8 to VY EPU Application BVY 05-084, Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E3-05-VY, Attachment 6 to Supplement 33 to VY EPU Application2008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E3-05-VY, Attachment 6 to Supplement 33 to VY EPU Application ML0825301682008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E3-02-VY, Hoffman Cv ML0825200232008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E2-06-VY, NUREG/CR-6583 ML0823304162008-08-12012 August 2008 Entergy Exhibit List - Appendix a, Entergy Nuclear Vermont Yankee LLC and Entergy Nuclear Operations Inc. July 2008 Evidentiary Hearing ML0823304192008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing, New England Coalition Exhibit List ML0824904732008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E2-29-VY, List of Drawings Provided to NEC in Discovery ML0823304172008-08-12012 August 2008 NRC Staff Exhibit List - Vermont Yankee Nuclear Power Station July 2008 Evidentiary Hearing ML0824904142008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E2-02-VY, Fitzpatrick Jc ML0823304982008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH_35, NRC, Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 229 to Facility Operating License No. DPR-28 Entergy Nuclear Vermont... ML0823407342008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-UW_20, Vermont Yankee Nuclear Power Station, PP7028: Piping FAC Inspection Program - FAC Inspection Program Records for 2005 Refueling Outage. (Corrected) ML0823407332008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-UW_15, L. E. Hochreiter, Data Collection of Pipe Failures Occurring in Stainless Steel and Carbon Steel Piping, Nuce 597D - Project 1 (April 2005) (Corrected) ML0825303102008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-17-VY, INPO Report OE-21421 (Dresden 3) ML0825303452008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-08-VY, Flow-Accelerated Corrosion in Power Plants ML0823406782008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-RH_02, Curriculum Vitae of Rudolf Hausler ML0825303692008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-18-VY, NRC Exhibit NEC-JH_18 LRA A3 Fdw 02 at Lph Ppb ML0825303702008-08-12012 August 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-19-VY, Effects of Chemistry on Corrosion-Erosion of Steels in Water and Wet Steam ML0825303182008-07-31031 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Application Exhibit E4-43-VY, Dr. Horowitz'S Checworks Presentation ML0823305252008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH_43, PP7028 FAC Inspections 2004 Refueling Outage. ML0824904812008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E2-39-VY, Vermont Yankee Transient Counting Status ML0825304702008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-14-VY, INPO Report OE-18478 (Clinton) ML0825303752008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-29-VY, EPRI Checworks Wear Rate Cycle 22B (2003) ML0825301692008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E3-03-VY, Lukens C V ML0825303722008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-22-VY, Heat and Mass Transfer Downstream of Abrupt Nozzle Expansion in Turbulent Flow ML0825302722008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-02-VY, Horowitz Cv ML0825302742008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-04-VY, Section B.1.13 of VY LRA ML0825303212008-07-23023 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-39-VY, Checworks v1.0G_Enhancements ML0823406772008-07-21021 July 2008 Vermont Yankee July 2008 Evidentiary Hearing-Intervenor Exhibit NEC-JH_71, Bignold, G.J. Et Al, Paper 1, Water Chemistry II, Bnes (1980): 5-18 ML0823304232008-07-21021 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH_02, Curriculum Vitae of Joram Hopenfeld ML0825504092008-07-21021 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E2-36-VY, Transcript of ACRS Meeting 03/06/08 (Excerpt) ML0825303632008-07-21021 July 2008 Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-21-VY, INPO Report OE-20127 (Calvert Cliffs) ML0823200362008-06-0202 June 2008 Vermont Yankee July 2008 Evidentiary Hearing - Staff Exhbit B, Approved Applications for Power Uprates -www.NRC.gov/reactors/operating/licensing/power-uprates/approved-applications.html ML0823406792008-06-0202 June 2008 Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-RH_05, Rudolf Hausler, Flow Assisted Corrosion (FAC) and Flow Induced Localized Corrosion: Comparison and Discussion ML0823809422008-05-31031 May 2008 2008/05/31-Vermont Yankee July 2008 Evidentiary Hearing - Staff Exhibit 1, NUREG-1907 Safety Evaluation Related to the License Renewal of Vermont Yankee Nuclear Power Station - Volume 1 (ML081430057) & Volume 2 (ML081430109) Combined (May 2 ML0823809412008-05-31031 May 2008 2008/05/31-Vermont Yankee July 2008 Evidentiary Hearing - Staff Exhibit 1, NUREG-1907 Safety Evaluation Related to the License Renewal of Vermont Yankee Nuclear Power Station - Volume 1 (ML081430057) & Volume 2 (ML081430109) Combined (May 2 ML0813501622008-05-13013 May 2008 Vermont Yankee - Exhibit List of NRC Staff Initial Statement of Position on NEC Contentions 2A, 2B, 3 and 4 ML0817500382008-05-12012 May 2008 Exhibits to Entergy'S Direct Testimony on NEC Contention 4 - Flow-Accelerated Corrosion Includes Exhibits E4-02 Through E4-29, Volume 1 ML0817500362008-05-12012 May 2008 Exhibits to Entergy'S Direct Testimony on NEC Contention 2 - Environmentally Assisted Fatigue - Includes Exhibits E2-02 Through E2-20, Volume 1 ML0823200192008-05-12012 May 2008 Vermont Yankee July 2008 Evidentiary Hearing - Staff Exhibit 2, Affidavit of Kenneth C. Chang 2012-04-20
[Table view] |
NEC-JH_23 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001 April 11, 2008 NRC REGULATORY ISSUE SUMMARY 2008-10
FATIGUE ANALYSIS OF NUCLEAR POWER PLANT COMPONENTS
ADDRESSEES
All holders of operating licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.
INTENT
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
to inform licensees of an analysis methodology used to demonstrate compliance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)
fatigue acceptance criteria that could be nonconservative if not correctly applied.
BACKGROUND INFORMATION
Title 10 of the Code of FederalRegulations (10 CFR) Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," requires that applicants for license renewal perform an evaluation of time-limited aging analyses relevant to structures, systems, and components within the scope of license renewal. The fatigue analysis of the reactor coolant pressure boundary components is an issue that involves time-limited assumptions. In addition, the staff has provided guidance in NUREG-1800, Rev. 1, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," issued September 2005.
NUREG-1 800, Rev. 1, specifies that the effects of the reactor water environment on fatigue life be evaluated for a sample of components to provide assurance that cracking because of fatigue will not occur during the period of extended operation. Since the reactor water environment has a significant impact on the fatigue life of components, many license renewal applicants have performed supplemental detailed analyses to demonstrate acceptable fatigue life for these components.
10 CFR 50.55a, "Codes and Standards," specifies the ASME Code requirements for operating reactors. Some operating facilities may have performed supplemental detailed analysis of components because of new loading conditions identified after the plant began operation.
ML08DOogPL5 I USNRC
August 12, 2008 (11:00am)
OFFEREDby: ApplicantI/censeeclnpor OFFICE OF SECRETARY
RULEMAKINGS AND NR9Sta -
ADJUDICATIONS STAFF
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SUMMARY OF ISSUE
The staff identified a concern regarding the methodology used by some license renewal applicants to demonstrate the ability of nuclear power plant components to withstand the cyclic loads associated with plant transient operations for the period of extended operation. This particular analysis methodology involves the use of the Green's function to calculate the fatigue usage during plant transient operations such as startups and shutdowns.
The Green's function approach involves per-forming a detailed stress analysis of a component to calculate its response to a step change in temperature. This detailed analysis is used to establish an influence function, which is subsequently used to calculate the stresses caused by the actual plant temperature transients. This methodology has been used to perform fatigue calculations and as input for on-line fatigue monitoring programs. The Green's function methodology is not in question. The concern involves a simplified input for applying the Green's function in which only one value of stress is used for the evaluation of the actual plant transients.
The detailed stress analysis requires consideration of six stress components, as discussed in ASMVE Code,Section III, Subsection NB, Subarticle NB-3200. Simplification of the analysis to consider only one value of the stress may provide acceptable results for some applications;
however, it also requires a great deal of judgment by the analyst to ensure that the simplification still provides a conservative result.
The staff has requested that recent license renewal applicants that have used this simplified Green's function methodology per-form confirmatory analyses to demonstrate that the simplified Green's function analyses provide acceptable results. The confirmatory analyses retain all six stress components. To date, the confirmatory analysis of one component, a boiling-water reactor feedwater nozzle, indicated that the simplified input for the Green's function did not produce conservative results in the nozzle bore area when compared to the detailed analysis.
However, the confirmatory analysis still demonstrated that the nozzle had acceptable fatigue usage.
Licensees may have also used the simplified Green's function methodology in operating plant fatigue evaluations for the current license term. For plants with renewed licenses, the staff is considering additional regulatory actions if the simplified Green's function methodology was used.
BACKFIT DISCUSSION
This RIS informs addressees of a potential nonconservative calculation methodology and reminds them that the ASME Code fatigue analysis should be performed properly. For license renewal, metal fatigue is evaluated as a time-limited aging analysis in accordance with
10 CFR 54.21(c). The associated staff review guidance appears in Section 4.3, "Metal Fatigue Analysis," of NUREG-1800, Rev. 1. For operating reactors, the ASME Code requirements appear in 10 CFR 50.55a. This RIS does not impose a new or different regulatory staff position.
It requires no action or written response and, therefore, is not a backfit under 10 CFR 50.109,
"Backfitting." Consequently, the NRC staff did not perform a backfit analysis.
FEDERAL REGISTER NOTIFICATION
A notice of opportunity for public comment on this RIS was not published in the FederalRegister because the RIS is informational.
CONGRESSIONAL REVIEW ACT
The NRC has determined that this RIS is not a rule as designated by the Congressional Review Act (5 U.S.C. §§801-808) and; therefore, is not subject to the Act.
PAPERWORK REDUCTION ACT STATEMENT
This RIS does not contain information collection requirements that are subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
.1
CONTACT
Please direct any questions about this matter to the technical contacts listed below.
IRA/
Michael J. Case, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Technical Contacts: Kenneth C. Chang, NRR John R. Fair, NRR
301-415-1913 301-415-2759 E-mail: kxc2t)Nrc..qov E-mail: irf(@nrc.qov Note: The NRC's generic communications may be found on the NRC public Web site, http://www.nrc.qov, under Electronic Reading Room/Document Collections.
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RIS 2008-03, Return/Reuse of Water Containing Previously Discharged Radioactive Effluents from Operating Nuclear Power Plants | 13 February 2008 | Ultimate heat sink Offsite Dose Calculation Manual Backfit | RIS 2008-04, Discontinuation of Two Performance Indicators Associated with the Security Reactor Oversight Process | 28 February 2008 | Significance Determination Process Backfit | RIS 2008-05, Lessons Learned to Improve Inspections, Tests, Analyses, and Acceptance Criteria Submittal | 27 February 2008 | Hydrostatic Backfit | RIS 2008-06, Protection Against the Malevolent Use of Vehicles When Utilizing Landform Obstacles | 6 March 2008 | Backfit | RIS 2008-08, Voluntary Submission of Performance Indicator Data | 19 February 2009 | Backfit | RIS 2008-10, Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH 23, NRC, NRC Regulatory Issue Summary 2008-10 Fatigue Analysis of Nuclear Power Plan Components (April 11, 2008) | 11 April 2008 | License Renewal Backfit | RIS 2008-10, Fatigue Analysis of Nuclear Power Plant Components | 11 April 2008 | License Renewal Backfit | RIS 2008-12, Considerations for Extended Interim Storage of Low-Level Radioactive Waste By Fuel Cycle and Materials Licensees | 9 May 2008 | License Renewal Backfit | RIS 2008-12, Enclosure 1: Information That NRC Staff May Require To Authorize Extended Interim Storage of Low-Level Radioactive Waste | 9 May 2008 | Decommissioning Funding Plan Earthquake | RIS 2008-12, Enclosure 3 - Bibliography | 9 May 2008 | | RIS 2008-12, Enclosure 4: List of Recently Issued FSME Generic Communications | 9 May 2008 | | RIS 2008-12, Enclosure 2: List of Low-Level Radioactive Waste Compacts and Unaffiliated States | 9 May 2008 | | RIS 2008-15, NRC Staff Position on Crediting Mitigating Strategies Implemented in Response to Security Orders in Risk-informed Licensing Actions and in the Significance Determination Process | 25 June 2008 | Probabilistic Risk Assessment Significance Determination Process Backfit | RIS 2008-16, Withdrawn NRC Regulatory Issue Summary 2008-16: Preparation and Scheduling of Operator Licensing Examinations | 27 June 2008 | Generic Fundamentals Examination Backfit | RIS 2008-19, Lessons-Learned from Recent 10 CFR Part 70 License-Transfer Application Reviews | 28 August 2008 | Tornado Missile Protection Exemption Request Backfit Affidavit | RIS 2008-20, Redesignation of Safeguards Advisory for Operating Power Reactors (SA-05-02) | 20 August 2008 | Backfit | RIS 2008-21, Issuance of LIC-109, Acceptance Review Procedures. | 2 September 2008 | Backfit | RIS 2008-22, Notification of Licensees Regarding Aircraft Threats | 6 October 2008 | Backfit | RIS 2008-24, Security Responsibilities of Service Providers and Client Licensees | 3 October 2008 | | RIS 2008-25, Primary Water Stress Corrosion Cracking of Dissimilar Metal Butt Welds in Pressurized Water Reactor Primary Coolant System Piping Welds | 22 October 2008 | Boric Acid Weld Overlay Incorporated by reference Stress corrosion cracking Dissimilar Metal Weld Backfit | RIS 2008-26, Clarified Requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(Y) When Implementing 10 CFR Section 50.54(x) to Depart from a License Condition or Technical Specification | 29 October 2008 | Safeguards Contingency Plan Backfit | RIS 2008-27, Staff Position on Extension of the Containment Type a Test Interval Beyond 15 Years Under Option B of Appendix J to 10 CFR Part 50 | 8 December 2008 | Integrated leak rate test Backfit | RIS 2008-28, Endorsement of Nuclear Energy Institute Guidance for Reactor Vessel Head Heavy Load Lifts | 1 December 2008 | Control of Heavy Loads Backfit | RIS 2008-30, Fatigue Analysis of Nuclear Power Plant Components | 16 December 2008 | License Renewal Backfit | RIS 2008-32, Interim Low Level Radioactive Waste Storage at Reactor Sites | 30 December 2008 | Backfit |
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