Rev 1, Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials| ML12145A013 |
| Person / Time |
|---|
| Issue date: |
04/30/1977 |
|---|
| From: |
NRC/OSD |
|---|
| To: |
|
|---|
| Kirk M |
| References |
|---|
| RG-1.099, Rev 1 |
| Download: ML12145A013 (7) |
|
|
|---|
Category:Regulatory Guide
MONTHYEARRegulatory Guide 1.1481981-03-31031 March 1981
Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants.
Regulatory Guide 1.1441980-09-30030 September 1980
Auditing of Quality Assurance Programs for Nuclear Power Plants.
Regulatory Guide 1.581980-09-30030 September 1980
Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel.
ML0607300551980-09-0101 September 1980
Proposed Revision 1 to Regulatory Guide 1.23, Meteorological Programs in Support of Nuclear Power Plants. for Comment
Regulatory Guide 1.1461980-08-31031 August 1980
Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants.
Regulatory Guide 8.251980-08-31031 August 1980
Calibration and Error Limits of Air Sampling Instruments for Total Volume of Air Sampled
ML12220A2591980-05-31031 May 1980
Draft Regulatory Guide Oh 902-1, Instruction Concerning Risk from Occupational Radiation Exposure
ML12208A3431980-02-28028 February 1980
Draft Regulatory Guide Oh 940-4 Personnel Neutron Dosimeters.
ML12298A1221979-09-30030 September 1979
Draft Regulatory Guide Rs 908-5, Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations During the Construction Phase of Nuclear Power Plants.
Regulatory Guide 1.1451979-08-31031 August 1979
Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants
Regulatory Guide 3.351979-07-31031 July 1979
Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant
ML12191A0121979-05-31031 May 1979
Draft Regulatory Guide (SG 909-4), Entry/Exit Control to Protected Areas, Vital Areas, and Material Access Areas
ML12298A1141979-04-30030 April 1979
Draft Regulatory Guide Sc 807-4, Determining Prestressing Forces for Inspection of Prestressed Concrete Containments
ML12298A1151979-04-30030 April 1979
Draft Regulatory Guide Sc 810-4, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments.
Regulatory Guide 3.431979-04-30030 April 1979
Nuclear Criticality Safety in the Storage of Fissile Materials
Regulatory Guide 10.81979-01-31031 January 1979
Guide for the Preparation of Applications for Medical Programs
Regulatory Guide 1.721978-11-30030 November 1978
Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin
Regulatory Guide 1.91978-11-30030 November 1978
Selection, Design, and Qualification of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants
ML0407503341978-05-31031 May 1978
Draft Regulatory Guide 1.139, Guidance for Residual Heat Removal.
Regulatory Guide 1.1181977-11-30030 November 1977
Rev. 1, Periodic Testing of Electric Power and Protection Systems.
Regulatory Guide 1.1081977-08-31031 August 1977
Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants
Regulatory Guide 1.1301977-07-31031 July 1977
Design Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports
Regulatory Guide 3.411977-05-31031 May 1977
Validation of Calculational Methods for Nuclear Criticality Safety.
ML12145A0131977-04-30030 April 1977
Rev 1, Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials
Regulatory Guide 1.1261977-03-31031 March 1977
an Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification
Regulatory Guide 1.1251977-03-31031 March 1977
Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants
Regulatory Guide 1.951977-01-31031 January 1977
Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release
Regulatory Guide 1.681977-01-31031 January 1977
Regulatory Guide 1.68.1, Revision 1, Preoperational and Initial Startup Testing of Feedwater and Condensate System for Boiling Water Reactor Power Plants
Regulatory Guide 1.881976-10-31031 October 1976
Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records
Regulatory Guide 1.1231976-10-31031 October 1976
Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants
Regulatory Guide 1.71976-09-30030 September 1976
Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident
Regulatory Guide 10.51976-09-30030 September 1976
Guide for the Preparation of Applications for Type a Licenses of Broad Scope for Byproduct Material
Regulatory Guide 1.1211976-08-31031 August 1976
Bases for Plugging Degraded PWR Steam Generator Tubes
Regulatory Guide 2.41976-07-31031 July 1976
Review of Experiments for Research Reactors
Regulatory Guide 4.111976-07-31031 July 1976
Terrestrial Environmental Studies for Nuclear Power Stations
Regulatory Guide 10.31976-07-30030 July 1976
Guide for the Preparation of Applications for Special Nuclear Material Licenses of Less than Critical Mass Quantities
Regulatory Guide 10.41976-07-30030 July 1976
Guide for the Preparation of Applications for Licenses to Process Source Material
ML0412800551976-06-30030 June 1976
Enclosure 2: Regulatory Guide 6.7, Preparation of Environmental Report to Support a Rule Making Petition Seeking an Exemption for a Radionuclide-Containing Product
Regulatory Guide 1.1191976-06-30030 June 1976
Surveillance Program for New Fuel Assembly Designs
Regulatory Guide 1.1201976-06-30030 June 1976
Fire Protection Guidelines for Nuclear Power Plants
Regulatory Guide 10.21976-03-31031 March 1976
Guidance to Academic Institutions Applying for Specific Byproduct Material Licenses
Regulatory Guide 1.1001976-03-31031 March 1976
Seismic Qualification of Electric Equipment for Nuclear Power Plant.
Regulatory Guide 1.1141976-02-29029 February 1976
Guidance on Being Operator at the Controls of a Nuclear Power Plant.
Regulatory Guide 1.291976-02-28028 February 1976
Seismic Design Classification
Regulatory Guide 1.1041976-02-28028 February 1976
Overhead Crane Handling Systems for Nuclear Power Plants
Regulatory Guide 1.971975-12-31031 December 1975
Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident
Regulatory Guide 1.131975-12-31031 December 1975
Spent Fuel Storage Facility Design Basis
Regulatory Guide 1.1031975-11-30030 November 1975
Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments.
Regulatory Guide 6.71975-10-31031 October 1975
Preparation of an Environmental Report to Support a Rule Making Petition Seeking an Exemption for a Radionuclide-Containing Product
Regulatory Guide 1.1071975-10-31031 October 1975
Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures.
1981-03-31
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
Retype of Next Page (1.99-3) Due to Text Illegibility C. REGULATORY POSITION (3) The expression for A is given in terms of fluence as measured by units of n/cm² (E > I MeV)
- 1. When credible surveillance data from the reactor however, the expression may be used in terms of in question are not available, prediction of fluence as measured by units of neutron damage fluence, 2
neutron radiation damage to the beltline of reactor provided the constant 1019 n/cm (E > l vessels of light water reactors should be based on the MeV) is changed to the corresponding value of following procedures. neutron damage fluence.
- a. Reference temperature should be adjusted as (4) Application of these procedures to a function of fluence and residual element content in materials having chemical content beyond that accordance with the following expression, within the represented by the current data base should be limits below and in paragraph l.c. justified by submittal of data.
A = [40 + 1000(% Cu - 0.08) 2. When credible surveillance data from the reactor
+ 5000 (% P -0.008)] [f/1019]1/2 in question become available, they may be used to represent the adjusted reference temperature and the where Charpy upper-shelf energy of the beltline materials at the fluence received by the surveillance specimens.
A = predicted adjustment of reference temperature, °F. a. The adjusted reference temperature of the beltline materials at other fluences may be predicted 2
f = fluence, n/cm (E>1 MeV). by:
(1) extrapolation to higher or lower fluences
% Cu = weight percent of copper. from credible surveillance data following the slope of If % Cu < 0.08. use 0.08. the family of lines in Figure 1 or
% P = weight percent of phosphorus . (2) a straight-line interpolation between credible If % P < 0.008. use 0.008. data on a logarithmic plot.
- b. To predict the decrease in upper-shelf energy If the value of A obtained by the above expression of the beltline materials at fluences other than those exceeds that given by the curve labeled "Upper Limit" in received by the surveillance specimens, procedures Figure I, the "Upper Limit" curve should be used. If % similar to those given in paragraph 2.a may be followed Cu is unknown, the "Upper Limit" curve should be used. using Figure 2.
- 3. For new plants, the reactor vessel beltline materials should have the content of residual elements such as copper, phosphorus, sulfur, and vanadium controlled to low levels. The levels should be such that the predicted adjusted reference temperature at the 1/4 T
- b. Charpy upper-shelf energy should be as- position in the vessel wall at end of life is less than sumed to decrease as a function of fluence and copper 200°F.
content as indicated in Figure 2. within the limits listed in paragraph 1.c. Interpolation is permitted. D. IMPLEMENTATION The purpose of this section is to provide information
- c. Application of the foregoing procedures to applicants and licensees regarding the NRC should be subject to the following limitations:
staffs plans for utilizing this regulatory guide (1) The procedures apply to those grades of This guide reflects current regulatory practice.
SA-302, 336, 533, and 508 steels having minimum Therefore, except in those cases in which the applicant specified yield strengths of 50,000 psi and under and proposes an acceptable alternative method for to their welds and heat-affected zones. complying with specified portions of the Commission's regulations, the positions described in this (2) The procedures are valid for a nominal guide will be used by the NRC staff as follows:
irradiation temperature of 550°F. Irradiation below 525°F should be considered to produce greater
- 1. The method described in regulatory positions C.1 damage and irradiation above 575°F may be considered and C.2 of this guide will be used in evaluating all to produce less damage. The correction factor used predictions of radiation damage called for in Appendices should be justified.
G and H to 10 CFR Part 50 submitted on or 1.99-3