ML19212A213
| ML19212A213 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/09/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19207B153 | List: |
| References | |
| REGGD-01.094, REGGD-1.094, NUDOCS 7908230490 | |
| Download: ML19212A213 (5) | |
Text
.';
L-kf E.:-
PRELI!1! NARY VALUE/ IMPACT STATEMENT ON QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION, INSPECTION, AND TESTING 0F STRUCTURAL CONCRETE, STRUCTURAL STEEL, SOILS AND FOUNDATIONS DURING THE CCNSTRUCTION PHASE OF NUCLEAR POWER PLANTS I.
The Prcoosed Action A.
Description The applicant for a permit to construct a nuclear power plant is required oy t:m Commission's regulations to estaolish and implemant a quality assurance program.
The proposed action will provide updated guidance on quality assurance program requirements for structural concrete, structural stael, soils and foundations for nuclear power plants.
B.
Need for the Procosed Action Existing guidance on quality assurance require.$ents for structural concrete and structural steel is contained in Regulatory Guide 1.94,
" Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants", Revision 1 dated April 1976 and Regulatory Guide 1.55, " Concrete Placement in Category I Structures" dated June 1973.
Regulatory Guide,1.,94, Revision 1 endorses ANSI /ASME Standard N45.2.5-1974.
Re 'a htory Guide 1.55 contains general requirements concerning quality 1
'.6128[5 3908230ffd'
assurance for concrete p1 3 cement.
Regulatory Guide 1.94 contains acre specific require;.ents for concrete placement.
Revision 1 to ANSI /ASME N45.2.5-1974 has been approvcd by ANSI anc designated ANSI /ASME N45.2.5-1978.
The revision provides more detailed guidance reflecting additional experience with quality issurance requirements for structural steel and structural concrete and includes requirements for soils, earthwork and foundation inspection.
Current NRC guidance should be updated to reflect experience in the use of the guidance and to establish an NRC position on the approved national standard.
Consistent with cast NRC practice, promulgation of this guidance should be in t.4e form of a regulatory guide endorsing the revised national star 'ard.
t C.
Valt /Imoact of the Prooosed Action 1.
NRC The NRC staff has been involved in the development, review, and approval of the revised national standard.
The proposed action will establish an NRC position by taking advantage of previous staff effort in conjunction with approval of the revised national standard and therefore will have minimal i.apact.
2
'g&12Si.=
2.
Other Gover..ent Agencies Not applicable, unless the government agency is an applicant, such as TVA.
3.
Industry The proposed action establishes an NRC position to an existing national standard and therefore reduces uncertainty as to what the staff considers acceptable in the area of quality assurance requirements for structural concrete, structural steel, soils and foundations during the construc-tion phase of nuclear power plants.
Most of the impact on industry has already been accomplished in conjunction with development, review and approval of the national standard.
Additional i,;act associated with NRC endorsement of the standard sho,id be minimal.
4.
Workers (relative to ALARA)
Not applicable.
5.
Public No impact on the public can be foreseen.
Rege' story Position 1 providas an NRC staff position concerning maxi-mum allowable concreta delivery and placement times and has minimal impact.
3
- 5 '-
Regulatory Position 2 clarifies guidance concerning tne calibration of measuring and test equipment and has no impact.
Regulatory Position 3 provides additional guidance concerning place-ment inspections and has minimal impact.
Regulatory Position 4 clarifies guidance concerning calibration of torque wrenches and has no impact.
Regulatory Position 5 provides information to the user of the guide concerning applicablity of referenced standards and has no impact.
D.
Decision on the Procosed Action As previously stated, guidance should be issued on the revised quality assurance requirements for structural con rete, structural steel, soils and foundations during the construction phase of nuclear power plants.
II.
Technical Acoroach This section is not applicible to this value/ impact statement since the proposed action is an endorsement of a recently approved and issued The technical issues have been previously discussed:
national standard.
III. Procedural Acoroach Previously discussed.
4
?S4288
IV.
Statutory Considerations A.
NRC Authority This guide would fall under the authority and safety requirements of the Atomic Energy Act.
In particular, Criterion II of Appendix B to 10 CFR Part 50 requires, in part, that an applicant (licensee) of a nuclear power plant establish a quality assurance program.
B.
Need for NEPA Assessment The proposed action is not a major action, as defined by 10 CFR Part 51.5(a)(10), and does not require an environmental impact statement.
V.
Relationshio to Other Existino or Procosed Reculations or Policies No conflicts. or overlaps with requirements promulgated by other agencies are foreseen.
Implementation of'the proposed action is discussed in Section D of the proposed guide.
VI.
Summary and Conclusions The proposed revision to Regulatory Guide 1.94 on suppleme'tary quality assurance requirements for installation, inspection and testing of structural concrete, structural steel, soils and founcations during the construction phase of nuclear power plants should be issued.
5
'a'd'l4383