ML19242A559
| ML19242A559 | |
| Person / Time | |
|---|---|
| Issue date: | 06/01/1979 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19242A558 | List: |
| References | |
| REGGD-01.136, REGGD-1.136, NUDOCS 7908030135 | |
| Download: ML19242A559 (7) | |
Text
1 Revision 2 2
Draft 1 3
June 1, 1979 4
REGULATORY GUIDE 1.136 5
MATERIALS, CONSTRUCTION AND TESTING OF CONCRETE CONTAINMENTS 6
(Articles CC 1000, 2000 and 4000-7000 of the 7
" Code for Concrete Reactor Vessels and Containments"1) 8 A.
INTRODUCTION 9
General Design Criterion 1, " Quality Standards and Records for Nuclear 10 Power plants," to 10 CFR Part 50, " Domestic lincensing of Production and Utiliza-11 tion Facilities," requires, in part, that structures, systems, and components 12 important to safety be designed, fabricated, erected, and tested to quality 13 standards commensurate with the importance of the safety functions to ce performed.
14 Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Repro-15 cessing Plants," to 10 CFR Part 50 requires, in part, that measures be estab-16 lished to assure materials control and control of special procesces such as 17 welding, and that oroper testing be performed.
18 This guide describes some bases acceptable to the NRC sts implementing 19 the above requirements with regard to the materials, contruction and testing 20 of concreta containments.
21 B.
DISCUSSION 22 The Amer ican Society of Mechanical Engineers and the American Concrete 23 Institute have jointly published th' for Concrete Reactor Vessels and 24 2s 1The " Code for Concrete Reactor Vessels and Containments" is alto known either 26 as the ASME Boiler anJ Pressure Vessel Code,Section III. Division 2, 1977 27 edition or as ACI Standard 359-77.
Conies of the Code and addenda tnereto 26 may be obtained frcm the American Society of Mechnical Engir.eers, United 29 Engineering Center, 345 East 47th Street, New York, NY 10017 or the American 30 Concrete Institute, Box 19150, Detroit, MI 48219.
1.136-1 7908030 M 5;b 2S$
1 Containments,"1 which is referred to in this guide as the Code.
The Code was 2
formally issued for the first time in 1975, was reissued in 1977, and has been 3
undergoing a number of technical and editorial revisions.
Consideration will 4
be given to ardorsing the Code in the Federal Regulations after sufficient 5
experience has been accumulated with its use.
In the interim, the NRC staff 6
will be setting forth its position on the acceptability of the Code for licensing 7
purposes through the regulatory guide process.
8 This guide, originally issued addressing only Article CC-2000, " Material,"
9 of the Code, has been expanded to provide information regarding the staff's 10 position on the acceptability for NRC licensing actions of the following Articles 11 of the " Coda for Concrete Reactor Vessels and Containments"-
12 CC-1000, Introduction 13 CC-2000, Material 14 CC-4000, Fabrication and Construction 15 CC-5000, Construction Testing and Examination 16 CC-6000, Structural Integrity Test of Concrete Containment Structures 17 CC-7000, Protection Against Overpressure 18 The NRC staff has evaluated the provisions contained in the articles 19 described above, but no attempt has been made to coordinate all literature (stand-20 ards, codes, guidelines, regulations, etc.) that may be relevant to the subject 21 of this guide.
In tnose areas where the provisions of the referenced Code are 22 insufficient for licensing purposes, the staff has provided supplementary guide-d 23 lines it considers to be acceptable.
These guidelines are contained in the 24 regulatory position.
Brief reasons for recommending them are given below.
1.136-2 E.,, f 7 l '5 u
1 1.
CC-2232.1(a)2 2
Paragraph CC-2232.1(a) gives no guidance as to how conformance with the 3
concrete strength requirements is to be demonstrated.
This is clarified in 4
Regulatory Position C.1.
f, 2.
CC-2232.2(a) 6 The Code lacks tolerance limits for the maximum permitted slump and air 7
content. The limits in Regulatory Fosic. c.z are taken from Section 4.4.2 8
of ACI Standard 318-77, " Building Cc-aquiremtat) for Reinforced Concrete."3 9
3.
CC-2243.3 10 Regulatory Position C.3 su~st *Jt?s the position of Regulatory Guide 1.107,
~
11
" Qualification for Cement Grouting for Prestressing Tendons in Containment Struc-12 tures," for item CC-2243.3 with respect to the limits on deleterious substances 13 and pH.
The staff believes that these recommended limits are more conservative 14 and provide better assurance of avoiding unforeseen problems than the limits 15 given in the code.
16 4.
CC-2463.1 17 Different systems of pres.ressing may require differe-t numbers of tests 18 for tendon systems to establish their adequacy for use.
One static tensile 19 test, as required by the Code, cannot assess the influence of dimensional varia-3 20 tions of anchorages on the strength of a prestressing system.
Variations within 21 the tolerance limits of the Construction Specification in material properties 22 23 2This refers to the article number of the " Code for Concrete Reactor Vessels 24 and Containments."
2s aCcpies may be obtained from the American Concrete Institute, Box 19150, 26 Detroit, Michigan 48219.
1.136-3 3
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I and in geometry of anchorages and tendons must be realistically and adequately 2
represented in the system testing.
Therefore, Regulatory Position C.4 recommends 3
that any system of prestressing be subjected to sufficient tests to establish 4
its adequacy before it is adopted for use.
5 5.
CC-5210 6
Embedments (including supports, ties, and bracas) that are encased or 7
partially encased in concrete will displace concrete.
Therefore, to prevent a 8
reduction in structural strength or shielding effectiveness for radiation, peecau-9 tion must be taken to ensure that no embedments not included in the design are 10 left in the concrete.
11 6.
CC-6214 12 The second sentence of CC-6214 permits an option of doing nothing even 13 after studies have been made which indicate that the acceptance criteria (c) L 14 (d) of CC-6213 were still not met.
The need to select one of the followup options 15 is defined in Regulatory Position C.6.
16 C.
REGULATCRY POSITION 17 The requirements specified in Articles CC-1000, 2000 and 4000 through 7000 18 of the " Code for Concrete Reactor Vessels and Containments," ASME Boiler & Pressure 19 Vessel Code,Section III, Civision 2, 1977, (also known as ACI Standard 359) 20 through its Winter 1978 Addenda are acceptable to the NRC staff for the materi.ls, 21 construction and testing of concrete containments of nuclear power plants subject 22 to the following:
, ~;
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- Jo 1.136-4
1 1.
CC-2232.1 Introduction 2
To item CC-2232.1(a), "conformance with the concrete strength requirements" 3
should be added:
4 "as demonstrated by the strength tests of CC-2232.2."
5 2.
CC-2232.2 Strength Tests 6
To paragraph CC-2232.2(a), should be added:
7 "The range of variation allowed for the air content shall be within 0.5 8
percent and for the slump within 0.75 in. of the maximums permitted by the 9
specifications."
10 3.
CC-2243.3 Chemical Requirements 11 Instead of item CC-2243.3, the recommended limits in Regulatory Position C1.e 12 of Regulatory Guide 1.107 should be used.
13 4
CC-2463.1 Static Tensile Test 14 Instead of "CC-2463.1 Static Tensile Test.
One static tensile test...,"
15 the following sh;uld be used:
16 "CC-2463.1 Static Tensile Tests.
Static tensile tests..
17 Any system of prestressing should be subjected to sufficient tests to estab-18 lish its adequacy.
Justification for the sufficiency of tests and a description 19 of the test program should be submitted to the NRC for review and approval.
g (g
790 1.136-5 3
m -
1 5.
CC-5210 General 2
The requirements of CC-5210 should be supplemented by an inspection to make 3
sure that only the embedments (including supports, ties and braces) shown 4
on the drawings or covered by documented field changes remain in the form 5
after the concrete is placed.
6 6.
CC-6214 Retest 7
One or the other of the options permitted by the Code in the phrase in the 8
second sentence of CC-6214 "... remedial measures may be undertaken or a retest 9
may be conducted" should actually be selected if the requirements of CC-6213(c) 10 and (d) are not met.
11 D.
IMPLEMENTATION 12 This proposed guide has been released to encourage public participation 13 in its development.
Except in those cases in whicn an applicant proposes an 14 acceptable alternative method for complying with specified portions of the Commis-15 sion's regulations, the method to be described in the active guide reflecting 16 public comments will be used in the evaluation of (1) all construction permit 17 applicatior.s, (2) standard reference system preliminary design applications 18 (PDA) or Type-2 final design applications (FDA-2), and (3) licenses to manu-19 fL;ture af t ar the implementation date to be specified in the active guide, except 20 those portions of a constructior, permit application that:
21 a.
Reference an approved standard reference system preliminary or final 22 design (PDA or FDA), or applications for such approval.
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1.136-6
1 b.
Reference an approved standard duplicate plant preliminary or final 2
design (PODA or FDDA).
3 c.
Reference parts of a base plant design qualified and approved for 4
replication.
5 d.
Reference a plant design approved or under review for approval for 6
manufacture under a Manufacturing License.
7 This implementation data (to be specified in the active guide) will in no 8
case be earlier than April 30, 1980.
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