ML19221B075
| ML19221B075 | |
| Person / Time | |
|---|---|
| Issue date: | 11/24/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-05.2.1., NUREG-75-87, NUREG-75-87-5.2.1., SRP-05.02.01.01, SRP-5.02.01.01, NUDOCS 7907120358 | |
| Download: ML19221B075 (4) | |
Text
NU R EG-75/087
/pa arcqs o4 U.S. NUCLEAR REGULATORY COMMISSION
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dO')*5i STANDARD REVIEW PLAN o
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OFFICE OF NUCLEAR REACTOR GEGULATION SECTION 5.2.1.l*
COMPLI ANCE WITH 10 CFR > 50.55a REVIEW PESPO',SIBILITIES Prirary - Auxiliary Systems Branch (ASB) l Secondary - Mechanical Engineerinq Eranch (MEB)
Materials Engineering Cranch (MTEB)
I.
AREAS OF REVIEW In order to establish that pressure-retaining corponents of the reactor coolant pressure toundary of water-cooled nuclear power plants are in compliance with 10 CFR c 50.55a, an applicant is required to provide a table in his safety analysis report (S AR) identi fying pressure vessels, piping, pumps and valves and the component code, code edition, applicable addenda, and component order date (where applicable) of each such component. Pressure-retaining components of the reactor coolant pressure boundary are designated as Class !
components under the ALerican Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III (hereaf ter the Code). 10 CFR 50.55a requires that these co,-
ponents reet the requirenents for Class I components under the Code.
For construction permit (CP) a.
operating license (CL) applicati ins, the ASB will deter-l 9
r ine the acceptability of the inharmation presented in the 5%R, to assure that the appli-cant is in corpliance with the rules of Section 50.55a.
In the esent there are cases where conforrance to Section 50.5S3 would result in hardships or unusual difficulties without a ccepensating increase in the level of safety and quality, the applicant rust provide a cerplete description of tne circumstances and the basis for proposed alternate require ents The applicant must describe hcw an equivalent and accept-able level of safety and quality will be provided by the proposed alternate requirerents.
When required, the MEB and MTES will provide assistance in establishing acceptability in the event an applicant inckes the " hardship" clause, and does not conforn in all respects with Section 50.553.
II.
ACCEPTANCE CRITERI A l.
10 CFR Part 50, Appendix A, General Design Criterion 1.
This criterion requires that structures, systers, and corponents irportant to sa fety shall be designed, fabricated.,
Forrall y 5.2.1.3 USNHC STANDARD REVIEW PLAN
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erected, and tested to quality standards commensurate with the importance of the safety function to be performed.
2.
10 CFR 3 50.55a. This rule establishes mininum quality standards for the design, fabrication, erection, construction, testing, and inspection of certain components within the reactor coolant pressure boundary of boilinq and pressurized water reactor nuclear power plants by requiring conformance with appropriate editions of specified published industry codes and standards.
3.
10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Peprocessing Plants." This appendix establishes quality assurance requirenents for the design, construction, and operation of those structures, systems, and components of nuclear pcwer plants that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public.
III. REVIEW PROCEDURES The table provided by the applicant identifying pressure vessel components, piping, pumps and valves, and the c arresponding component code, code edition, applicable addenda, and, when required, the co.mc ent order date of each Code Section III, Class 1 component within the reactor coolant pressure boundary, is checked for compliance with Section 50.55a of 10 CFR Part 50.
Thi! review is applicable to CP and OL applications.
For those components within the reactor coolant pressure boundary not in compliance with the rules of Section 50.55a, a review of the code and code addenda is performed, to identi fy the speci fic sectiens with which the component does not comply. A decision to accept a component which is not fully in compliance with the rules is based on a judgnent of the relative inportance of the specific provisions in the code or code addenda not complied with, and a deternination that any noncompliance will not result in an unacceptable level of safety and quality If the staff's concerns are not resolved in a satisfactory n3nner, a staff position is taken requiring conforrance with the rules of Section 50.55a.
IV.
EVALUATION FINDINGS The reviewer should veri fy that suf ficient information is contained in the SAR arid amend-rents and that his evaluation supports conclusions of the following type, which are to be included in the staf f's safety evaluation report:
"The components of the reactor c';olant pressure boundary, as defined by the rules of 10 CFR > 50.55a, have been properly identified and classified as ASME Code Section III Class I components. These comoor.ents will be constructed in accordance with the requirements of the applicable codes and addenda as specified by the rules of 10 CFR s 50.55a.
5.2.1.1-2 Ren 1 147 046
"The staff concludes that construction of the components of the reactor coolant pres-sure boundary in conformance witi, these codes provides assurance that component quality will be comnensurate with the importance of the safety function of the re-actor coolant pressure boundary and is acceptable."
V.
REFERENCES 1.
10 CFR Part 50, Appendix A, General Design Criterion 1, " Quality Standards and Records."
2 10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants."
3.
10 CFR '; 50.55a, " Codes and Standards Rule."
4 ASME Boiler and Pressure Vessel Code,1977 Edition,Section III, " Nuclear Power elant Components." Anerican Society of Mechanical Engineers (1977).
147 047 5.2.1.1-3 pey, 1