ML19259C785
| ML19259C785 | |
| Person / Time | |
|---|---|
| Issue date: | 06/01/1979 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19248D251 | List: |
| References | |
| REGGD-01.136, REGGD-1.136, NUDOCS 7908150167 | |
| Download: ML19259C785 (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 Centainments"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 ccmponents 12 important to safety be designed, fabricated, erected, and tested to quality 13 standards cocmensurate 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 11shed to assure materials control and control of special processes such as 17 welding, and that proper testing be performed.
18 This guide describes scme bases acceptable to the NRC staff for implementing 19 the above requirements with regard to the materials, contruction and testing 20 of concrete containments.
21 E.
C : 5 :U3 S I C."
22 The American Society of Mechanical Engineers and the American Concrete 23 Instituce nave jointly published the "Coce ;w Co..cieLJ Reactor Vesseis and 24 2s
- The " Code for Concrete Reactor Vessels and Containments" is also known either 26 as the AS"E Eciler and Pressure Vessel Ccce.Section III, Division 2, 1977 27 ecitic c ' as ACI Stancard 355 ~~
Copic: c' t: 2 Ccde a-d addend: ct:
28 may bc ccccin2d frca the Americ_.
cciet;. cf. =c nical Engineers, t'ni ce:
29 Engineering Center, 345 East 47th Street, N c,. York, NY 10017 or t.e Amer.can 30 Concrete Institute, Box 19150, Detroit, MI 43219.
, c_
L Cr,,.N d 1 c
1.125-1 7 9 0 8 I 5 0 M 'I
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 raissued in 1977, and has been 3
undergoing a number of technical and ad':torial revisions.
Consideration will be given to endorsinc the Code in the Federal Regulations after sufficient 4
5 experience has been accumulated with its use.
In the interim, the NRC staff 6
will be setting forth i*.s position on the acceptability of the Code for licensing 7
purposes througn the reculatory guide process.
This guide, originally issued addressing only Article CC-2000, " Material,"
8 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 " Code 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 uvaluated the provisions contained in the articles 19 described above, but ro attem;t has been made to coordinate all literature (stand-ards, ceces, guicelir as, re;_' Itions, etc. ) that may be relevant to the subjc;t 21 of tnis guide.
In these areas where tne provisions of the referenced Code are 2:
insarficient for licensing purposes, the staff has provided supplementary guice-23
'ines it considers to be acccotable.
These guidelines are contained in the Ca eegul atory pos i ti on.
Brief reasons for recommending them are given below.
ba.> C _L W;>
n - rsr 1.136-2
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.
5 2.
CC-2232.2(a) 6 The Code lacks tolerance limits for the maximum permitted slu.mp and air 7
content.
The limits in Regulatory Position C.2 are taken from Section 4.4.2 8
of ACI Standard 318-77, " Building Code Requirements for Reinforced Concrete."3 9
3.
CC-2243.3 10 Regulatory Position C.3 substitutes the position of Regulatory Guide 1.107, 11 "0ualification 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 l'
and provide better assurance of avoiding unforeseen problems than the limits 15 given in the code.
15 4
CC-2463.1 l'
Cifierent sys tems cf pres;res aing maj equire ciffe.' ant numtars of tests 1.
for tencca systams to establish their acequacy for use.
One stat.c tensile 19 test, as recuired by the Coce, car. cot assess the influence of dimensional varia-2 tions of anchorages on the strength of a prestressing system.
Variations within 21 the tolerance limits of the Construction Specification in maternal properties 5
'This r:rers to tne article nu-ter of tr.e "Ccce for Concrete Reactor Vessels and Containments."
2 3Ccpies may be obtained from the American Concrete Institute, Box 19150, 25 Detroit. Michigan 48219.
1.136-3
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1 and in geomet.y 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 bcfore it is ad pted f,or use.
5 5.
CC-5210 6
Embedments (including suppc-ts, ties, and braces) that are encased or 7
partially encased in concrete will displace concrete.
Therefore, to prevent a 8
reduction in structural strergth or shielding effectiveness for radiation, precau-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-E214 permits an option of doing nothing even 13 af ter studies have been made which indicate that the acceptance criteria (c) &
14 (d) of CC-6213 were still not met.
The need to select one of the followup cptions 15 is defined in Regulatory Position C.6.
16 C.
REGULATORY POSITICN 17 ine recul. nent: 3;;cified in Articles CC-1CCC, 2000 and ACC0 tn-cu;n 7000 13 cf the "Ccce for Concrete Reacter Vessels and Centainments," ASME Eciler E Pressure 19 Vessel C:ce,Section III, Civision 2,1977, (also known as ACI Standard 259)
CD through ics h' inter 1978 Acdenda are acceptable to the NRC staff for the materials, 21 construction and testing of concrete containments of nuclear pcwer plants subject 22 to the fcilc~ing:
1.136-4 a J ;;. h..e n o-l JG
1 1.
CC-2232.1 Introduction To item CC-2232.1(a), "conformance with the concrete strength requirements" 2
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:
0.5 7
"The range of variation allowed for the air content shall be within 8
percent and for the slump within 0.75 in. of the maximums permitted by the 9
speci f icati ons. "
10 3.
CC-2243.3 Chemical Requirements Instead of item CC-2243.3, the reccmmended limits in Regulatory Position C1.e 11 12 of Regulatory Guide 1.107 should be used.
13 4.
CC-2a63.1 Static Tensile Test 14 Instead of "CC-2463.1 Static Tensiie Test.
One static tensile test...,"
15 the folicwing should be used:
16 "CC-2263.1 Static Tensile Tests.
5::;ic tensiis tests.
17 Any system of prestressing should ce subjected to sufficient tests to estab-1S lish its adequacy.
Justificatien for tho suffic(ency of tests and a description 19 of th: test program should be submitted to the NRC far review end approval.
,,-c8 s
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- 1. ~. 7 5 - 5
1 S.
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 on the drc.eings or covered by docu$ented field changes remain in the form 5
after the concrete is placed.
6 6.
CC c214 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-621?(c) 10 and (d) are nct met.
11 D.
IMPLEMENTATION 12 This proposed guide has been released to encourage public participation 13 in its development.
Except in those cases in which 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 applicaticos, (2) standard ref erence system preliminary cesign applications i c.
(?:;,' or Type-2 final design applications (FDA-2), and (3) licenses to manu-1.
f 2::. -e after the implementitien date to be specifie: in the active guide, exce::
20 those portions of a construction permit application that:
Reference an approved standard reference syster preliminary or final 21 c.
22 cesi;n (PDA or FDA), or applications for such approvcl.
- 2. J u z Q*
- a or a
1.136-6
1 b.
Reference an approved standard duplicate plant preliminary or final 2
design (PDDA or FDDA).
3 c.
Reference parts of a base plant design qualified and epproved for 4
replication.
5 d.
Reference a plant cesign approved or under review for approval for 6
manufacture under a Manufacturing License.
7 This implementation data (to be specified in the active guie3) will in no 8
case be earlier than April 30, 1980.
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