ML20009E050

Reg Guide 1.136,Revision 2, Matls,Const & Testing of Concrete Containments

ML20009E050
Person / Time
Issue date:	06/30/1981
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
Shared Package
ML17192A228	List: ML20009E050 ML20009E051
References
TASK-OS, TASK-SC-814-5 REGGD-01.136, REGGD-1.136, NUDOCS 8107270031
Download: ML20009E050 (4)

Text

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Revision 2' f

U.S. NUCLEAR REGULATCRY COMMIS$10N June 1981 o'd g\\ n...i REGULATORY GU DE OFFICE OF NUCLEAR REGULATORY RESEARCH R EGULATORY GUIDE 1.136 (Task SC 814-5)

MATERIALS, CONSTRUCTION, AND TESTING OF CONCRETE CONTAINMENTS (Articles CC-1000,-2000, and -4000 through 6000 of the

" Code for Concrete Reactor Vessels and Containments"3 )

l A. INTRODUCTION formally issued for the first time in 1975, was reissued in 1977, and again in 1980. This revision to the guide endorses General Design Criterion 1, " Quality Standards and the following articles of the 1980 edition of the Code:

Records," of Appendix A, " General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, " Domestic CC-1000, Introduction, Licensing of Production and Utilization Facilities," requires, CC-2000, Material, in part, that structures, systems, and mmponents important CC-4000, Fabrication and Construction, to safety be designed, fabricated, erected, and tested to CC-5000, Construction, Testing, and Examination, and quality standards commensurate with the importance of CC-6000, Structural Integrity Test of Concrete Contain-the safety functions to be performed. Appendi; B," Quality ment Structures.

Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 requires, in part, Consideration will be given to referencing the Code in that measures be established to ensure materials control the Code of Federal Regulations after sufficient experience and control of special processes, such as welding, and that has been accumulated with its use. In the interim, the NRC proper testing be performed.

staff will set forth its position on the acceptability of l

the Code for licensing purposes in regulatory guides.

g This guide describes bases acceptable to the NRC staff (j}

for implementing the above requirements with regard to the The NRC staff has evaluated the protisions contained in

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materials, construction, and testing of concrete cmtainments.

the articles listed above, but has made no attempt to coordinate allliterature (standards, codes, guidelines,regula-The Advisory Committee on Reactor Safeguards has tions, etc.) that may be relevant to the subject of this guide.

been consulted concerning this guide and has concurred in the regulatory position.

The referenced Code incorporates the recommendations of several regulatory guides in an acceptable manner. Ilence, B. DISCUSSION with the issuance of thisrevision to Regulatory Guide 1.136, the regulatory guides listed below will be withdrawn:

The American Society of Mechanical Engineers and the American Concrete Institute have jointly published the 1.10 Mechanical (Cadweld) Splices in Reinforcing

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" Code for Concrete Reactor Vessels and Containments,"3 Bars of Category 1 Concrete Structures, which is referred to in this guide as the Code. The Code was l.15 Testing of Reinforcing Bars for Catepry I Concrete Structures,

. The substantial number of changes in this revision from the October 1978 inwe has made it impractical to indicate the changes with lir.rs in the margin.

1.18 Structural Acceptance Test for Concrete Primary I The " Code for Concrete Reactor Vessels and Containments" is also knnu either as the ASM E Doiler and Pressure Vessel Code, section III, Dnision 2,1980 Edition, or as ACI Standard 3s9-80.

1.19 Nondestructive Lxamination of Primary Contain-Copees of the Code and addenda thereto may be obtained from the American Society of Mechanical Engineers, United Engine. cin g ment Liner weids, Center, 345 E. 47th Street, New York, New York 10017, er the American Concre te instit u te, Box 19150, Detroit, machigan 48289.

I.55 Concrete Placement in Category I Structures, and USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, wishington, O.C. 20555, Regulatory Guides are issued to describe and make available to the Attention: Docket 6ng and Service Branch, pu blic methoris acceptable to the rJRC staff of implementing speciric parts of the Commission's regulations, to delineate tech.

The guides are issued in the following ten broad divisions:

/"'N f

niques used by the staff in evaluating specific problems or postu-lated accidents or to provide guidance to applicants. Regulatory

1. Power Reactors

6. Products I t Guides are no substitutes for regulations, and cornpliance with

2. Research and Test Reactors

7. Transportation

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them as not required. Methods and solutions dif ferent from those set

3. Fuels and Materials Facilities

8. Occupational Health b/

out in the guides will be acceptable if they provide a basis for the

4. Environmental and Siting

9. Antitrust and Financial Review findings reaufsite to the issuance or continuance of a permit or

5. Materials and plant Protection 10. General license by the Commission.

Copies of issued guides may be purchased at the current Govsrnment This guide was issued af ter consideration of comments received from Printing Of f ace price. A subscription service for future gulaes in spe-the public. Comments and suggestions for improvements in these cif 6c divisions is available through the Governrnent Print 6ng Office.

9uides are encouraged at all times and guides will be revised, as Information on the subscription service and current GPO prices may apoecsrlate, to accommodate comrnents and to reflect new informe-be obtained by writing the U.S. Nuclear Regulatory Commission, tion or experlene Washington, D.C. 20555, Attention: Publications Sales Manager.

PDR REGGD 01.136 R PDR

1.103 Post-tensioned Prestressing Systems for Concrete

5. CC-2441(g)- Tendon Ducts, Channels, Trumpets, and Reactor Vessels and Containments.

Transition Cones Because tne Code provisions continue to change, the SubparagraphCC-2441(g) addresses only the susceptibil-NRC staff plans to periodically update this guide to accom-ity of ducts to leakage under pressure. Ilowever, duct joints modate new and revised provisions of the Code.

are more susceptible to leakage under pressure than the ducts. The recornmended prequalification of ducts and In those areas where the provisions of the referenced duct joints in Regulatory Position C.5 would eliminate the Code are insufficient for licensing purposes, the staff has potential for gresse (or grout) leakage under maximum provided supplementary guidelines it considers to be pressures.

needed. These guidelines are contained in the regulatory positMn. Brief reasons for recommending them are given

6. CC-2463.1 - Static Tensile Test belos..

1)ifferent systems of prestressing may require different 2

1. CC-2232.2(a)- Strength Tests numbers of tests for tendon systems to establish their adequacy for use. Variations within the tolerance limits of The average strength of a design mix based on mean the construction specification in material properties and rather than maximum allowable values of air content and in geometry of anchorages and tendons must be realistically slump is not conservative relative to standard building con-and adequately represented in the systera testing.Therefore, struction practice. The limits in Regulatory Position C.I Regulatory PositiowC6 recommends that any system of are taken from Section 4.4.2 of ACI Standard 318-77, prestressing be subjected to a sufficient number of tests to

" Building Code Requirements for Reinforced Concrev."3 establish its adequacy before it is adopted for use.

2. CC-2243 - Cement Grout for Grouted Tendon Systems

7. CC-4240 - Curing Regulatory Position C.2 recommends using the guidance The 1980 version of the Code eliminates a specific in Regulatory Guide l.107," Qualification for cement Grout-requirement for curing concrete at temperatures higher ing for Prestressing Tendons in Containment Structures,"

than 40* E The guide recommendation is in accordance I

rather than paragraph CC-2243 with respect to grouting of with ACI 308-71, " Recommended Practice for Curing prestressing tendons. The staff believes that the guide recom-Concre te."3 mendations provide needed assurance for the integrity of grouted tendons that cannot be directly ir spected during

8. CC-4333 4.2 - Splice Samples the life of the containment.

The 1980 edition of the Code, in CC-4333.4.3, requires

3. CC-24 33.2.3 - Acceptance Standards only a production-splice tcsting program, while the previous prognm permitted productien-and sister-splice testing. As Experience with the use of alloy steel materials for anchor a result, CC-4333.4.2 now contradicts CC-4333.4.3. Regula-blocks and wedge blocks (such as AISI'l40) indicates ti.at tory Position C.8 provides guidance consistent with the a high degree of hardness of these materials is a factor ia requirements of CC-4333.4.3.

causing cracking (presumably cress-corrosion) under certain inevitable environments. Also it is necessary to control the

9. CC-4352 - Splices uniformity of hardness of these materials. A thorough surface examination and proper protection before and after Mechanical splices are considered to be weak links in the installation of these materials and a close control in the performance of reinforcing bars.Thus, staggering of mechan-amount and uniformity of hardness in.hese materials may ical splices in areas of high stress is being reemphasized in climinate cracking.

order to avoid a concentration of splices on one plane in such areas that may result in (I) unacceptable cracking and 4.

Protection of Prestressing Materials from towTerrverature (2) increased steel congestion that has adverse effects on Effects concrete placement. In addition, this recommendation is consistent with ACI 349-76. " Code Requirements for Nuclear lhe testing of prestressing nuterials to qualify them against Safety-Related Concrete Structures."3 loss in ductility during cold temperatures is needed; therefore, the guidance in Regulatory Position C.4 is recommended.

10. CC-44 64.1 - Procedure 2

1his alrhanumeric citing identifies the article.and paragraph if appbcable, or the " Code for Concrete Reactor Veuels and Contain-the American Concrete Institute (Section 18.18 of ACI ments" t'eins ducussed.

31g.77), s to allow the discrepancy levd of 5% instead of 3

amed w w me. m ge recommenaation copies may t$e obtained from the American Concrete Institute, Nn 198 s0, Detroit, Michigan 48219.

is for 15%.

1.136-2

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I1. CC-4522.1 Tolerances for Liner Sheus and Heads

3. CC-2433.2.3 - Acciptancs Stand rds

,O The non-mandatory guidelines of Appendix F to the code In addition to the requirementsin subparagra!MX'-2433.2.3,

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are acceptable to the NRC staff although some of the guide-the following guidance should be used:

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Enes are relaxed from the previous requirements of the 1977 edition of the Code.

• • The maximum hardness for material of anchor head assemblies and wedge blocks shall not exceed that of Appendix F, paragraph F-1220(c), establishes non-cumukitive Rockwell C40. To maintain uniformity in hardness, the toler-plumbness tolerances for liner shells. Cumulative toleranes ance on a designated hardness i. umber shall not exceed 12."

may be controlled in most cases by the out of-roundness tolerances of paragraph F 1220(a). Ilowever, to ensure that a maximum cumulative plumbness tolerance is established

4. Protection of Prestressing Materials frcan Low Temperature for different containment configurations, an explicit Effects recommendation is provided in Regulatory Position C.11.

In addition to the requirements in CC-2434, " Wedges

12. CC 5210 General and Anchor Nuts," the following guidance should oc used:

f The locations of all major embedments, such as plaw,

" Materials for allload bearingcomponentsof prestressmg embedded piping penetration sleeves, major structural

.ystems should be selected so that they can withstand the framings, and anchor bolts, should be preplanned, identified anticipated low-temperature effects without loss in their on the design drawings, and documented on field changes ductility. Methods and prosedures similar to those used thereto. This would permit verification that embedments for materials of liners in CC-2520, ' Fracture Toughness

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have been placed with full consideration given to the Requirements for Materials,' are acceptable for qualifying i

resulting reduction in structural strengths, radiation shielding the materials. Additionally, it should be demonstrated by effectiveness, and hindrance to the placement and consolida-suitable tests that with the maximum allowable flaw tion of concrete.

size (cracked buttonheads, wedges, and anchor nuts), the specific components will exhibit the required strength and l

13. CC.6214 Retest ductility under the lowest anticipated temperatures."

The second sentence of CC-6214 permits ti.e licensee the option of doing nothing even after studies have been made

5. CC-2441(a) Tendon Ducts, Channels, Trumpets, and I

t, that indicate that acceptance criteria (c) and (d) of CC-6213 Transition Cones were still not met. The need to select one of the followup options in paragraph CC-6214 is defined in Regulatory Instead of "CC-2441(g) Ducts...," the following should Position C.13.

be used:

"CC-2441(g) Ducts and duct joints."

C. REGULATORY POSITION

6. CC-2463.1 Static Tensile Test The requirements specified in Articles CC-1000. 2000, and -4000 through-60000f the " Code for Concrete Reactor Instead of "CC-2463.1 Static Tensile Test. Two or more Vessels and Containraents," ASME Boiler and Pressure Vessel static tensile tests...," the follow'ng should be used:

Code,Section III, Division 2,1980 Edition,(also known as ACI Standard 359-80) are acceptable to the NRC staff for "CC-2463.1 Static Tensile Tests. Static tensile tests.. "

the materials, co+.truction, and testing cf concrete contain-ments of nuclear power plants subject to the following:

Any system of prestressing should be subjected to a suffi-cient number of tests to establish its adequacy. Justification

1. CC-2232.2(a)- Strength Tests that a sufficient number of tests have been per' armed as wellasa description of the test program should be submned When following the requirements in the second sentence to the NRC for review and approval, of CC-2232.2(a), the word " maximum" should be used for the word "mean" w henever it appears,and "io.751n." should

7. CC-4240 Curing be used instead of "10.75%."

In addition to the requirements for curing concrete in

2. CC 2243 - Cement Grout for Grouted Tendon Systems subsubarticle CC-4240(d), the following guidance should be used:

Regulatory Guide 1.107, " Qualification for Cement Grcuting for Prestressing Tendms in Containment Structures,"

"When the mean daily outdoor temperature is 40* F or should be used for guidance on quahfying grout for grouted higher, the minimum period of curing should be 7 days

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tendon systems.

a'ter placing concrete."

1.136-3

8. CC-4333.4.2 Splice Samples such as rebar supports and ferm ties), or covered by docu-mented field changes and later placed on the as built Instead of the requirementsin subparagraph CC-4333.4.2, d, wings, remain in the form after the concrete is placed.

the following guidance should be used:

Aaditionally, the inspection should ensure that hollow tubes and pipe sections used as support systems or for other

" Splice samples shall be production sphws (cut directly construction convenience, ifleft embedded in the concrete, from in-place reinforcement)."

are filled with concrete or grout as appropriate.

9. CC-4352 - Splices

13. CC-6214 Retest In addition to the requirements in paragraph CC-4352, There are two options permitted by the Code in the phrase the following guidance should be used:

in the second sentence of CC-6214 ".. remedial measures may be undertaken or a retest may be conducted.. "; one

" Mechanical splices located in areas of high stresses should be selected if the requirements of CC-6213(c) and (maximum computed tensile stress :t 0.5 F ) should have (d) are not met.

y alternate bars spliced or adjacent splices staggered. If tests for slip (or internal plastic deformation)of the splice demon-strate that the slip is low (i.e., not to exceed 50% of the D. IMPLEMENTATION elongation of the unspliced bar along the spliced length), at 0.9 F, the adjacent splices need not be staggered."

The purpose of this section is to provide information to y

applicants regarding the NRC staff's plans for 3 sing this

10. CC-4464.1 Procedure regulatory guide.

Discrepancies of elongation of tendonsshould not exceed Except in those cases in which an applicant proposes an "15%" of the discrepancies calculated instead of the "110%"

acceptable alternative method for complying with specified as discussed in the last two sentences of subparagraph portions of the Commission's regulations, the method CC-4464.1.

described herein will be used in the evaluation of the following applications that are docketed after May 1981.

I1. CC-4522.1 - Tolerances for Liner Shells and IIcads

1. Preliminary Design Approval (PDA) applications and Pre-The NRC staff will use the guidelines of the non-mandatory liminary Duplicate Design Approval (PDDA) applications.

Appendix F to the Code for the purpose of review and inspection.

2. Final Design Approval, Type 2, (FI)A 2).pplications and Final Duplicate Design Approva!, T,

', (FDDA-2)

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A maximum cumulative deviation of the liner shell plumb-applications ness of 6" or a 1 in 200 ratio, whichever is less, should be used.

3. Manufacturing License (ML) applications.

12. CC-5210 General

4. Construction Permit (CP) applicatwns except for those portions of CP applications that reference standard The requirements of CC-5210 should be supplemented designs (i.e., PDA, FDA-1, FDA-2, PDDA, FDDA-1, by an inspection to ensure that only those embedments FDDA-2, or ML) or that reference qualified base plant shown on the design 6mgs (except minor embedments designs under the replication option.

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