Regulatory Guide 1.35: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML12305A260
| number = ML031500241
| issue date = 02/05/1973
| issue date = 01/31/1976
| title = Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures.
| title = Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/OSD
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.035
| document report number = RG-1.035, Rev. 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 3
| page count = 4
}}
}}
{{#Wiki_filter:2/5/73 U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:._. ._-. U.S. NUCLEAR REGULATORY
COMMISSION
j REGULATORY
GUIDE Revision 2 January 1976 OFFICE OF STANDARDS
DEVELOPMENT
REGULATORY  
REGULATORY  
GI DIRECTORATE
OF REGULATORY
STANDARDS REGULATORY
GUIDE 1.35 INSERVICE  
GUIDE 1.35 INSERVICE  
SURVEILLANCE
INSPECTION
OF UNGROUTED  
OF UNGROUTED  
TENDONS IN PRESTRESSED  
TENDONS IN PRESTRESSED  
CONCRETE CONTAINMENT  
CONCRETE CONTAINMENT  
STRUCTURES
STRUCTURES
JIDE


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion  
General Design Criterion  
53, "Provisions for Containment Testing and Inspection" of Appendix A to 10 CFR Part 50, "General Design Criteria for Nuclear Power Plants," requires, in part, that the reactor containment be designed to permit (1) periodic inspection of all important areas and (2) 'an appropriate surveillance program. This guide describes an acceptable basis for developing an appropriate surveillance program for ungrouted tendons in prestressed concrete containment structures of light-water-cooled reactors.
53, "Provisions for Contain-ment Testing and Inspection," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires in part that the reactor containment be designed to permit (1) periodic inspection of all important areas and (2) an appropriate surveillance program. This guide describes a basis acceptable to the.NRC staff for developing an' appropriate inservice inspection and surveillance program for ungrouted ten-dons in prestressed concrete containment structures of light-water-cooled reactors.


The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.


==B. DISCUSSION==
==B. DISCUSSION==
This guide is applicable to "typical" prestressed concrete containments with ungrouted tendons only, for which the number of tendons does not exceed: 200 in the dome (either three families of tendons 600 apart or two families of tendons 900 apart), 200 vertical (in wall), and 500 complete hoops (in wall).For containments that differ from the "typical" containment described above, the model program presented in this guide should serve as the basis for development of a comparable surveillance program.Surveillance of ungrouted wire and strand tendons of all sizes (up to an ultimate strength of approximately
* l This revision is the result of comments received on Revision 1, June 1974, and additional staff review.The recommendations of this guide are applicable to"typical" prestressed concrete containnents having a shallow-domed roof on cylindrical walls about 150 feet in diameter, an overall height of about 200 feet, and the following tendons: approximately
1300 tons) and types should be considered (e.g., tendons with parallel wires, with one or several strands, and with different systems of anchors).  
200 in the dome (either three families of tendons 600 apart or two families of tendons 90° apart), 200 vertical in the wall, and 500 hoop tendons in the wall. In addition, these recommendations are applicable to containments having a hemispherical dome-shaped roof on cylindrical walls about 150 feet in diameter, an overall height ranging from 200 to 240 feet, and the following tendons: 70 to*Lines indicate substantive changes from previous issue.90 inverted U tendons' arranged in two families of tendons 900 apart and 150 to 180 hoop tendons in the cylinder and dome.Inservice inspection of ungrouted wire and strand tendons of all sizes (up to an ultimate strength of approximately  
Materials for all components should satisfy the requirements of applicable American Society for Testing and Materials (ASTM) material standards.
1300 tons) and all types should be performed (e.g., tendons with parallel wires, with one or several strands, and with different systems of anchors).Materials for all components should satisfy the require-ments of applicable American Society for Testing and Materials (ASTM) material standards.


The surveillance program should cover the anchor hardware and the corrosion- preventing filler (grease).  
The inservice in-spection program should cover the anchor hardware and the corrosion-preventing filler (grease).  
To the fullest extent practical, it should also cover the ducts that contain the tendons.Such a surveillance program is necessary because generally there is no permanent instrumentation installed in the containment that could continuously monitor its structural behavior.When developing a surveillance program, the total containment tendon population should be divided into homogeneous subgroups, i.e., tendons having approximately the same probability of corrosion and a similar function in the overall structural capabilities and properties of the structure.
To the fullest extent practical, it should also cover the ducts that contain the tendons. Such an inservice inspection pro-gram is necessary because generally there is no perma-nent instrumentation installed in the containment that could continuously monitor its structural behavior.When an inservice inspection program is being devel-oped, the total containment tendon population should be divided into homogeneous subgroups consisting of tendons having approximately the same probability of corrosion and similar functions in the overall structural capabilities and properties of the structure.


Thus, for each structure the surveillance program. should consider separately the groups of vertical, hoop, and dome tendons.Consideration of homogeneous tendon subgroups (i.e., vertical, hoop, and dome) establishes a sampling base for determining loss of prestress, the main characteristic checked by the surveillance program.If some tendons are expected to be subject to greater prestress losses than the rest, this should be taken into account in selecting samples..The prestressing force in a tendon may :be 'checked by a liftoff or other equivalent test., One of the main objectives of the test is to discover any brittle, damaged, or broken wires. Any eventual decrease in the prestressing force is due to the simultaneous interaction of several time-dependent factors such as: a. Stress relaxation in the wire;b. Temperature variation of the wire;c. Shrinkage, creep, and temperature stresses in concrete;d. Differential thermal expansion
Thus, for each structure the inservice inspection program should consider separately the groups of vertical, inverted U, hoop, and dome tendons. This will permit a sampling.base to be established for determining loss of prestress, the main characteristic checked by the inservice inspec-tion program.IA tendon, both ends of which are anchored at the bottom of the base of the cylindrical walls and which approximately follows the configuration of the containment in the vertical plane passing through the anchor point
' or contraction between the concrete and the tendon; and e. -Eventual deterioration of the wires (corrosion).
USAEC REGULATORY
GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention:
Director of Regulatory Standards.


Comments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of improvements in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20545, evaluating specific problems or postulated accidents, or to provide guidance to Attention:
====s. USNRC REGULATORY ====
Chief, Public Proceedings Staff.applicants.
GUIDES Comments should be sent to the Secretary of the Commission.


Regulatory Guides are not substitutes for regulations and compliance with them is not required.
U.S. Nuclear Regulatory Commission.


Methods and solutions different from those set out in The guides are issued in the following ten broad divisions:
Washington.
the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.


1,. Power Reactors 6. Products 2. Research and Test Reactors
D.C. 20555. Attention:
Docketing and Regulatory Guides are issued to describe end make available to the pubic Service Section methods acceptable to the NRC staff of implementing specific parts of the S n Commission's regulations, to delineate techniques used by the staff in avalu. The guides are issued in the following ten broad divisions:
ating specific problems or postulated accidents, or to provide guidance to appli-cants. Regulatory Guides are not substitutes for regulations.


===7. Transportation===
and compliance
3. Fuels and Materials Facilities
1. Power Reactors 6. Products with them is not required.
8. Occupational Health Published guides will be revised periodically, as apprupriate, to accommodate
4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience.


5. Materials and Plant Protection
Methods and solutions different from those set out in 2. Research end Test Reactors 7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Facilities
10. General A liftoff test does not separate the effects of these factors, and corrosion, the factor of greatest concern, cannot be isolated.
8. Occupational Health the issuance or continuance of a permit or license by the Commission.


Therefore, tolerance limits for the loss of prestressing force, including the effects of possible corrosion, should be established, and the surveillance procedure oriented toward verifying that these limits are not exceeded.
4. Environmental and Siting 9. Antitrust Review Comments and suggestions for improvements in these guides are encouraged S. Materials and Plant Protection
10. General at all times. and guides will be revised, as appropriate, to accommodate com-ments and to reflect new information or e.perience.


However, it should be noted that only gross deterioration of the prestressing system can be detected.Many hoop tendons are anchored on buttresses partially located inside the auxiliary building adjacent to the containment.
This guide was revised as a Copies of published guides may be obtained by written fequest indicating the result of substantive comments received from the public and additional staff divisions desired to the U.S. Nuclear Regulatory Commission Washington.


Since these anchors are not easily accessible, especially during operation of the facility, they present a special problem for liftoff tests. The original layout of tendons should address itself specifically to this problem. Any anchor architectural treatment or environmental protection should be removable without damage to the anchor.Defects that an inspector might uncover during visual inspection of the anchorage assembly should be separated into three groups: a. Defects that can be found when the tendon is in its normally stressed condition;
D.C.review. 20555. Attention:  
b. Defects that can be found only after the tendon is tensioned to a higher value than the existing prestressing force; and c. Defects that can be found only after the tendon is detensioned.
Director.


If the limits provided in C.5. and C.6. are exceeded or if abnormal material behavior is detected pursuant to inspection in accordance with C.7., then abnormal degradation of the containment structure, a boundary designed to contain radioactive materials, is indicated.
Office of Standards Development.


In such cases, the reporting provisions of Safety Guide 16,"Reporting of Operating Information," should apply.Included in the report should be a description of the condition of the concrete (especially at tendon anchorages), the surveillance procedure, the tolerances on cracking, and the measures to be used when tolerances are exceeded.C. REGULATORY
If some tendons are expected to be subject to greater 3. Defec prestress losses than the rest, this should be taken into detensionec account in selecting samples.The inservice inspection programs outlined in this guide are applicable to all containments with ungrouted prestressing systems regardless of plant geographical
POSITION 1. This guide should be applied to "typical" prestressed concrete containments having a shallow-domed roof on cyclindrical walls about 150 feet in diameter, an overall height of about 200 feet, and for which the number of tendons does not exceed: 200 in the dome (either three families of tendons 600 apart or two families of tendons 90' apart), 200 vertical (in wall), and 500 complete hoops (in wall). For containments that differ from the "typical" containment described above, this guide should serve as the basis for development of a comparable surveillance program, which will be evaluated on a case-by-case basis.2. Each containment structure should be inspected in accordance with this guide independently from containments at any other site. Where identical containment structures are located on one site, where no environmental or other differences are apparent, and where they were constructed by the same contractor in the same manner at the same time (continuous construction), then every second containment structure need only be visually inspected in accordance with C.7.3. Containments should be designed so that the prestressing anchor hardware is accessible for periodic inspection.
1 Gene location.The prestressing force in a tendon may be checked by 1.1 The a liftoff or other equivalent tests. One of the main this guide objectives of the test is to discover any brittle, damaged, prestressed or broken wires. Any eventual decrease in the pre-stressing force is due to the simultaneous interaction of 1.1.1 several time-dependent factors such as: shallow-doi in diameter 1. Stress relaxation in the wire; following
1 (either thr 2. Temperature variation of the wire; families of and 500 h 3. Shrinkage, creep, and temperature deformations in ("typical")
concrete;1.1.2 4. Differential thermal expansion or contraction hemispheric between the concrete and the tendon; and about 150 from 200 t 5. Reduction in cross section of the wires, including
90 inverte possible fracture, due to corrosion.


4. The surveillance measures identified in C.5., C.6.and C.
tendons 90 cylinder ar A liftoff test does not separate the effects of these dome").-factors, and corrosion, the factor of greatest concern, cannot be isolated.


===7. should be performed ===
Therefore, tolerance limits for the 1.2 For loss of prestressing force, including the effects of types, the possible corrosion, should be established, and the inser- for the dew vice inspection program should be oriented toward tion prograr determining whether these limits are exceeded.
1, 2, and 3 years after the initial containment structural integrity test and every 5 years thereafter.


5. Selected tendons should be periodically subjected to liftoff or other equivalent tests to monitor loss of prestress.
However, it should be noted that only gross deterioration of the 1.3 All prestressing system can be detected.
 
dons should Many hoop tendons are anchored on buttresses partially located inside the auxiliary building adjacent to the containment.
 
Since these anchors are not easily accessible, especially during operation of the facility, they present a special problem for liftoff tests. In the original layout of tendons, this problem should be specifically considered.
 
Any architectural treatment or environmental protection of the anchors should be removable without damage to the anchor.Defects that an inspector might uncover during visual inspection of the anchorage assembly should be sepa-rated into three groups: 1. Defects that can be found when the tendon is in its normally stressed condition;
2. Defects that can be found only after the tendon is the existing prestressing
; ~~tensioned to a igher value than force; and l:'..-; -.~~~~~cts that can be found only after the tendon is 1.C. REGULATORY
POSITION inservice inspection program described in is applicable to the following types of concrete containment structures:
Prestressed concrete containments having a ned roof on cylindrical walls about 150 feet , an overall height of about 200 feet, and the tendons: 2 approximately
200 in the dome ee families of tendons 60° apart or two tendons 900 apart), 200 vertical in the wall, oop tendons in the wall (herein designated and Prestressed concrete containments having a ial dome-shaped roof on cylindrical walls feet in diameter, an overall height ranging o 240 feet, and the following tendons: 70 to I U tendons' arranged in two families of°apart and 150 to 180 hoop tendons in the id dome (herein designated "hemispherical containments that differ from these two program described should serve as the basis relopment of a comparable inservice inspec-iM.containment structures with ungrouted ten-I be inspected in accordance with this guide.However, if it can be shown by the applicant that identical containment structures are located on one site, that no environmental or other differences are apparent, and that they were constructed by the same contractor in the same manner at the same time (continuous construction), every second containment structure need only be visually inspected as described in regulatory position C.3.1.4 Containments should be designed so that the prestressing anchor hardware is accessible for periodic examination.
 
1.5 The inservice inspection should be performed
1, 3, and 5 years after the initial containment structural integrity test and every 5 years thereafter.
 
2 For the purpose of this guide, a tendon is defined as a separate continuous multiwire or multistrand tensioned element anchored at both ends to an end anchorage assembly.1.35-2 Q
2. Sample Selection 2.1 Samples for the inspection at 1, 3, and 5 years should be selected as follows: 2.1.1 "Typical" containments:
2.1.1.1 Six dome tendons, two located in each 60° group (i.e., three families of tendons) and randomly distributed to provide representative sampling, or three located in each 900 group (i.e., two families of tendons).2.1.1.2 Five vertical tendons, randomly but representatively distributed.
 
2.1.1.3 Ten hoop tendons randomly but repre-sentatively distributed.
 
2.1.2 "Hemispherical dome" containments:
2.1.2.1 4% of the U tendon population with the result rounded off to the nearest integral number of tendons, but no less than four.2.1.2.2 4% of the hoop tendon population with the result rounded off to the nearest integral number of tendons, but no less than nine.2.2 If the inspections described in regulatory posi-tion C.2.1 indicate that there are no problems with prestressing tendons in containment structures, the samples for the subsequent inspections may be selected as follows: 2.2.1 "Typical" containments:
2.2.1.1 If there are three dome groups, one from each group; if there are two dome groups, one from each dome group plus one additional dome tendon selected at random: 2.2.1.2 Three vertical tendons randomly but representatively distributed.
 
2.2.1.3 Three hoop tendons randomly but representatively distributed.
 
2.2.2 "Hemispherical dome" containments:
2.2.2.1 2% of the U tendon population with the result rounded off to the nearest integral number of tendons, but no less than two.2.2.2.2 2% of ie hoop tendon population with the result rounded off to the nearest integral number of tendons, but no less than three.2.3 If some tendons are subject to greater prestress losses than others, this should be considered in the sample selection.
 
For each inspection, the tendons should again be selected on a random but representative basis so the sample group will change somewhat each time. However, to develop a history and for correlating the observed data, one tendon from each group may be kept unchanged after the initial selection.
 
3. Visual Inspection Tendon anchorage assembly hardware (such as bearing plates, stressing washers, sims, wedges, and buttonheads)
of all tendons selected as described in regulatory position C.2 should be visually examined.
 
For those containments for which only visual inspections need be performed, tendons selected as described in regulatory position C.2 should be visually examined to the extent practical without dismantling load-bearing components of the anchorage.
 
The surrounding concrete should also be checked visually for indications of abnormal material behavior.
 
The visual examination of the concrete should be scheduled during integrated leakage testing while the containment is at its maximum test pressure.The method used for removing grease in order to permit visual examination of the stressing washers, shims, wedges, and bearing plates should neither increase the effects of corrosion nor damage the steel (for instance, scratch it) and should be usable under oper-ating conditions.
 
4. Prestress Monitoring Tests Tendons selected as described in regulatory position C.2 should be subjected to liftoff or other equivalent tests to monitor loss of prestress during each inspection.


These tests should include the following:
These tests should include the following:
a. Properly calibrated jacks and the simultaneous measurement of elongation and jacking force. Allowable elongations and jacking loads, allowable tolerances, and the effects of influences such as temperature should be established prior to the tests.b. A maximum test liftoff force greater than the maximum inservice prestressing force. The liftoff test should include an unloading cycle going down to essentially complete detensioning of the tendon to identify broken or damaged wires or strands.c. Selected numbers and types of tendons periodically tested for loss of prestress:
4.1 The simultaneous measurement of elongation and jacking force with properly calibrated jacks. Allow-able elongations, jacking loads, allowable tolerances, and the effects of influences such as temperature should be established prior to the tests.4.2 The maximum test liftoff force should be greater than the maximum inservice prestressing force. The liftoff test should include an unloading cycle going down to essentially complete detensioning of the tendon to identify broken or damaged wires or strands.5. Tendon Material Tests and Inspections
(1) Six dome tendons; two located in each 600 group (i.e.., three families of tendons) and distributed to provide representative, sampling, or three located in each 900 group (i.e., two families of tendons), *(2) Five vertical tendons, randomly but representatively distributed, (3) Ten hoop tendons (where more than one tendon comprises the total hoop, one tendon may represent the hoop), randomly but representatively distributed.
5.1 Previously stressed tendon wires or strands from one tendon of each type (i.e., for "typical" contain-ments, one dome, one vertical, and one hoop tendon; for"hemispherical dome" containments, one U tendon and one hoop tendon) should be removed for testing and examination over the entire length to determine if evidence of corrosion or other deleterious effects is 1.35-3 0 I.I
present. At each successive inspection, the samples should be selected from different tendons.5.2 Tensile tests should be made on at least three samples cut from each removed wire or strand (one at each end and one at mid-length;
the samples should be the maximum.length practical for testing).  
If frequent stress cycling is suspected, tests simulating this condition should be conducted.
 
Similarly, where the inservice inspection program indicates the possibility of a poten-tially corrosive atmosphere, accelerated corrosion tests should be made.6. Inspection of Filler Grease The method used for checking the presence of sheathing filler grease should account for (1) the minimum grease coverage needed for different parts of the anchorage system including, for example, button-heads; (2) the influence of temperature variations, especially the lowest temperature likely to occur between two successive inspections;
(3) the procedure used to uncover possible voids in grease in the trumpet;and (4) requirements imposed by grease specifications, qualification tests, and acceptability tolerances.


d. A measurement of the prestress force for each tendon tested in C.5.c., with acceptable limits being defined as not less than the predicted lower bound nor greater than the predicted upper bound forces at the time of the test.e. An allowable limit of not more than one defective tendon out of the total sample population.
7. Acceptance Criteria 7.1 The prestress force measured for each tendon in the tests described in regulatory position C.4 should be within the limits predicted for the time of the test.7.2 There should be no more than one defective tendon in the total sample population.


If one sample tendon is defective, an adjacent tendon on each side of the defective tendon should also be checked. If both of these tendons are acceptable as defined in C.5.d., then the surveillance program should proceed considering the single deficiency as unique and acceptable.
If one sample tendon is defective, an adjacent tendon on each side of the defective tendon should also be checked. If both of these tendons are acceptable as defined in regulatory position C.7.1, the inservice inspection program should proceed considering the single deficiency as unique and acceptable.


However, if either adjacent tendon is defective or if more than one tendon out of the original sample population is defective, abnormal degradation of the containment structure is indicated, and the Commission should be notified in accordance with C.8.1.35-2
However, if efither adjacent tendon is defec-tive or if more than one tendon out of the original sample population is defective, the occurrence should be considered as unacceptable.
6. The physical condition of the tendon material should be checked as noted below.a. Previously stressed tendon wires or strands from one dome tendon and two wall tendons (one from a vertical tendon and one from a hoop tendon) should be removed for testing and examination over the entire length to determine if evidence of corrosion or other deleterious effects are present. At each successive inspection the samples should be selected from different tendons.b. Tensile tests should be made on at least three samples cut from each removed wire or strand (one at each end and one at mid-length;
the samples being of a maximum length practical for testing).
If frequent stress cycling is suspected, tests simulating his condition should be conducted.


Similarly, where as a result of the surveillance program a potentially corrosive atmosphere is suspected, accelerated corrosion tests should be made.c. Failure below the guaranteed ultimate strength of any one of the three tendon material sample tests should be considered an indication of abnormal degradation of the containment structure, and the Commission should be notified in accordance with C.8.7. Tendon anchorage assembly hardware (such as bearing plates, stressing washers, shims, wedges, and buttonheads)
UNITED STATES NUCLEAR REGULATORY
of all tendons inspected pursuant to C.5.and C.6. should be visually inspected.
COMMISSION
WASHINGTON, D. C. 20555 OFFiCIAL BUSINESS PENALTY FOR PRIVATE USE. 300 7.3 Failure in the tensile test should not occur at a strength value less than the guaranteed ultimate strength of the tendon material.


For those containments for which only visual inspections need be performed, as noted in C.2., the same numbers and types of tendons as noted in C.5.c. should be visually inspected to the extent practical without dismantling load-bearing components of the anchorage.
Failure below this value in any tendon material sample should be considerea as unaccep-table.8. Reporting to the Commission If the acceptance criteria of regulatory position C.7 are not met or if abnormal material behavior is detected as described in regulatory positions C.3 and C.6, a possible abnormal degradation of the containment struc-ture (a boundary designed to contain radioactive mate-rials) is indicated.


The surrounding concrete should also be checked visually for indications of abnormal material behavior.
Such an occurrence should be reported to the Commission.


If the entire containment is pressurized for leak testing purposes, the visual inspection should be scheduled, if possible, to coincide with the leak test.The method used for checking the presence of sheathing filler grease should account for: (1) the minimum grease coverage needed for different parts of the anchorage system including, for example, buttonheads;
The'report should include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the I inspection procedure, the tolerances on cracking, and the measures to be used when tolerances are exceeded.
(2) the influence of temperature variations, especially the lowest temperature likely to occur between two successive inspections;
(3) the procedure used to uncover possible voids in grease in the trumpet;and (4) requirements imposed by grease specifications, qualification tests, and acceptability tolera'nces.


The method used for removing grease in order to permit visual inspection of the stressing washers, shims, wedges, and bearing plates should neither increase the effects of corrosion nor damage the steel (for instance, scratch it)and should be usable even under unfavorable conditions so as not to conflict with operational requirements.
==D. IMPLEMENTATION==
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide.This guide reflects current NRC practice.


8. Any significant or critical deterioration of the containment revealed by the inservice surveillance program should be reported to the Commission as an abnormal occurrence in accordance with Safety Guide 16, "Reporting of Operating Information," except that the initial report may be made within 10 days of the completion of the tests, and the detailed report may follow within 90 days of the completion of the tests.1.35-3}}
Therefore, except in those cases in which the applicant proposes an acceptable alternative method for complying with speci-fied portions of the Commission's regulations, this guide will be used by the NRC staff in evaluating construction permit and operating license applications for plants whose construction permits are docketed after the date of publication of the guide.3The report to the Commission should be made in accordance with the reporting program summarized in Regulatory Guide 1.16, "Reporting of Operating Information  
-Appendix A Technical Specification." POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORY
COMMISSION
S .}}


{{RG-Nav}}
{{RG-Nav}}

Revision as of 21:32, 29 October 2018

Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures
ML031500241
Person / Time
Issue date: 01/31/1976
From:
NRC/OSD
To:
References
RG-1.035, Rev. 2
Download: ML031500241 (4)


._. ._-. U.S. NUCLEAR REGULATORY

COMMISSION

j REGULATORY

GUIDE Revision 2 January 1976 OFFICE OF STANDARDS

DEVELOPMENT

REGULATORY

GUIDE 1.35 INSERVICE

INSPECTION

OF UNGROUTED

TENDONS IN PRESTRESSED

CONCRETE CONTAINMENT

STRUCTURES

A. INTRODUCTION

General Design Criterion 53, "Provisions for Contain-ment Testing and Inspection," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires in part that the reactor containment be designed to permit (1) periodic inspection of all important areas and (2) an appropriate surveillance program. This guide describes a basis acceptable to the.NRC staff for developing an' appropriate inservice inspection and surveillance program for ungrouted ten-dons in prestressed concrete containment structures of light-water-cooled reactors.

The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION

  • l This revision is the result of comments received on Revision 1, June 1974, and additional staff review.The recommendations of this guide are applicable to"typical" prestressed concrete containnents having a shallow-domed roof on cylindrical walls about 150 feet in diameter, an overall height of about 200 feet, and the following tendons: approximately

200 in the dome (either three families of tendons 600 apart or two families of tendons 90° apart), 200 vertical in the wall, and 500 hoop tendons in the wall. In addition, these recommendations are applicable to containments having a hemispherical dome-shaped roof on cylindrical walls about 150 feet in diameter, an overall height ranging from 200 to 240 feet, and the following tendons: 70 to*Lines indicate substantive changes from previous issue.90 inverted U tendons' arranged in two families of tendons 900 apart and 150 to 180 hoop tendons in the cylinder and dome.Inservice inspection of ungrouted wire and strand tendons of all sizes (up to an ultimate strength of approximately

1300 tons) and all types should be performed (e.g., tendons with parallel wires, with one or several strands, and with different systems of anchors).Materials for all components should satisfy the require-ments of applicable American Society for Testing and Materials (ASTM) material standards.

The inservice in-spection program should cover the anchor hardware and the corrosion-preventing filler (grease).

To the fullest extent practical, it should also cover the ducts that contain the tendons. Such an inservice inspection pro-gram is necessary because generally there is no perma-nent instrumentation installed in the containment that could continuously monitor its structural behavior.When an inservice inspection program is being devel-oped, the total containment tendon population should be divided into homogeneous subgroups consisting of tendons having approximately the same probability of corrosion and similar functions in the overall structural capabilities and properties of the structure.

Thus, for each structure the inservice inspection program should consider separately the groups of vertical, inverted U, hoop, and dome tendons. This will permit a sampling.base to be established for determining loss of prestress, the main characteristic checked by the inservice inspec-tion program.IA tendon, both ends of which are anchored at the bottom of the base of the cylindrical walls and which approximately follows the configuration of the containment in the vertical plane passing through the anchor point

s. USNRC REGULATORY

GUIDES Comments should be sent to the Secretary of the Commission.

U.S. Nuclear Regulatory Commission.

Washington.

D.C. 20555. Attention:

Docketing and Regulatory Guides are issued to describe end make available to the pubic Service Section methods acceptable to the NRC staff of implementing specific parts of the S n Commission's regulations, to delineate techniques used by the staff in avalu. The guides are issued in the following ten broad divisions:

ating specific problems or postulated accidents, or to provide guidance to appli-cants. Regulatory Guides are not substitutes for regulations.

and compliance

1. Power Reactors 6. Products with them is not required.

Methods and solutions different from those set out in 2. Research end Test Reactors 7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Facilities

8. Occupational Health the issuance or continuance of a permit or license by the Commission.

4. Environmental and Siting 9. Antitrust Review Comments and suggestions for improvements in these guides are encouraged S. Materials and Plant Protection

10. General at all times. and guides will be revised, as appropriate, to accommodate com-ments and to reflect new information or e.perience.

This guide was revised as a Copies of published guides may be obtained by written fequest indicating the result of substantive comments received from the public and additional staff divisions desired to the U.S. Nuclear Regulatory Commission Washington.

D.C.review. 20555. Attention:

Director.

Office of Standards Development.

If some tendons are expected to be subject to greater 3. Defec prestress losses than the rest, this should be taken into detensionec account in selecting samples.The inservice inspection programs outlined in this guide are applicable to all containments with ungrouted prestressing systems regardless of plant geographical

1 Gene location.The prestressing force in a tendon may be checked by 1.1 The a liftoff or other equivalent tests. One of the main this guide objectives of the test is to discover any brittle, damaged, prestressed or broken wires. Any eventual decrease in the pre-stressing force is due to the simultaneous interaction of 1.1.1 several time-dependent factors such as: shallow-doi in diameter 1. Stress relaxation in the wire; following

1 (either thr 2. Temperature variation of the wire; families of and 500 h 3. Shrinkage, creep, and temperature deformations in ("typical")

concrete;1.1.2 4. Differential thermal expansion or contraction hemispheric between the concrete and the tendon; and about 150 from 200 t 5. Reduction in cross section of the wires, including

90 inverte possible fracture, due to corrosion.

tendons 90 cylinder ar A liftoff test does not separate the effects of these dome").-factors, and corrosion, the factor of greatest concern, cannot be isolated.

Therefore, tolerance limits for the 1.2 For loss of prestressing force, including the effects of types, the possible corrosion, should be established, and the inser- for the dew vice inspection program should be oriented toward tion prograr determining whether these limits are exceeded.

However, it should be noted that only gross deterioration of the 1.3 All prestressing system can be detected.

dons should Many hoop tendons are anchored on buttresses partially located inside the auxiliary building adjacent to the containment.

Since these anchors are not easily accessible, especially during operation of the facility, they present a special problem for liftoff tests. In the original layout of tendons, this problem should be specifically considered.

Any architectural treatment or environmental protection of the anchors should be removable without damage to the anchor.Defects that an inspector might uncover during visual inspection of the anchorage assembly should be sepa-rated into three groups: 1. Defects that can be found when the tendon is in its normally stressed condition;

2. Defects that can be found only after the tendon is the existing prestressing

~~tensioned to a igher value than force; and l
'..-; -.~~~~~cts that can be found only after the tendon is 1.C. REGULATORY

POSITION inservice inspection program described in is applicable to the following types of concrete containment structures:

Prestressed concrete containments having a ned roof on cylindrical walls about 150 feet , an overall height of about 200 feet, and the tendons: 2 approximately

200 in the dome ee families of tendons 60° apart or two tendons 900 apart), 200 vertical in the wall, oop tendons in the wall (herein designated and Prestressed concrete containments having a ial dome-shaped roof on cylindrical walls feet in diameter, an overall height ranging o 240 feet, and the following tendons: 70 to I U tendons' arranged in two families of°apart and 150 to 180 hoop tendons in the id dome (herein designated "hemispherical containments that differ from these two program described should serve as the basis relopment of a comparable inservice inspec-iM.containment structures with ungrouted ten-I be inspected in accordance with this guide.However, if it can be shown by the applicant that identical containment structures are located on one site, that no environmental or other differences are apparent, and that they were constructed by the same contractor in the same manner at the same time (continuous construction), every second containment structure need only be visually inspected as described in regulatory position C.3.1.4 Containments should be designed so that the prestressing anchor hardware is accessible for periodic examination.

1.5 The inservice inspection should be performed

1, 3, and 5 years after the initial containment structural integrity test and every 5 years thereafter.

2 For the purpose of this guide, a tendon is defined as a separate continuous multiwire or multistrand tensioned element anchored at both ends to an end anchorage assembly.1.35-2 Q

2. Sample Selection 2.1 Samples for the inspection at 1, 3, and 5 years should be selected as follows: 2.1.1 "Typical" containments:

2.1.1.1 Six dome tendons, two located in each 60° group (i.e., three families of tendons) and randomly distributed to provide representative sampling, or three located in each 900 group (i.e., two families of tendons).2.1.1.2 Five vertical tendons, randomly but representatively distributed.

2.1.1.3 Ten hoop tendons randomly but repre-sentatively distributed.

2.1.2 "Hemispherical dome" containments:

2.1.2.1 4% of the U tendon population with the result rounded off to the nearest integral number of tendons, but no less than four.2.1.2.2 4% of the hoop tendon population with the result rounded off to the nearest integral number of tendons, but no less than nine.2.2 If the inspections described in regulatory posi-tion C.2.1 indicate that there are no problems with prestressing tendons in containment structures, the samples for the subsequent inspections may be selected as follows: 2.2.1 "Typical" containments:

2.2.1.1 If there are three dome groups, one from each group; if there are two dome groups, one from each dome group plus one additional dome tendon selected at random: 2.2.1.2 Three vertical tendons randomly but representatively distributed.

2.2.1.3 Three hoop tendons randomly but representatively distributed.

2.2.2 "Hemispherical dome" containments:

2.2.2.1 2% of the U tendon population with the result rounded off to the nearest integral number of tendons, but no less than two.2.2.2.2 2% of ie hoop tendon population with the result rounded off to the nearest integral number of tendons, but no less than three.2.3 If some tendons are subject to greater prestress losses than others, this should be considered in the sample selection.

For each inspection, the tendons should again be selected on a random but representative basis so the sample group will change somewhat each time. However, to develop a history and for correlating the observed data, one tendon from each group may be kept unchanged after the initial selection.

3. Visual Inspection Tendon anchorage assembly hardware (such as bearing plates, stressing washers, sims, wedges, and buttonheads)

of all tendons selected as described in regulatory position C.2 should be visually examined.

For those containments for which only visual inspections need be performed, tendons selected as described in regulatory position C.2 should be visually examined to the extent practical without dismantling load-bearing components of the anchorage.

The surrounding concrete should also be checked visually for indications of abnormal material behavior.

The visual examination of the concrete should be scheduled during integrated leakage testing while the containment is at its maximum test pressure.The method used for removing grease in order to permit visual examination of the stressing washers, shims, wedges, and bearing plates should neither increase the effects of corrosion nor damage the steel (for instance, scratch it) and should be usable under oper-ating conditions.

4. Prestress Monitoring Tests Tendons selected as described in regulatory position C.2 should be subjected to liftoff or other equivalent tests to monitor loss of prestress during each inspection.

These tests should include the following:

4.1 The simultaneous measurement of elongation and jacking force with properly calibrated jacks. Allow-able elongations, jacking loads, allowable tolerances, and the effects of influences such as temperature should be established prior to the tests.4.2 The maximum test liftoff force should be greater than the maximum inservice prestressing force. The liftoff test should include an unloading cycle going down to essentially complete detensioning of the tendon to identify broken or damaged wires or strands.5. Tendon Material Tests and Inspections

5.1 Previously stressed tendon wires or strands from one tendon of each type (i.e., for "typical" contain-ments, one dome, one vertical, and one hoop tendon; for"hemispherical dome" containments, one U tendon and one hoop tendon) should be removed for testing and examination over the entire length to determine if evidence of corrosion or other deleterious effects is 1.35-3 0 I.I

present. At each successive inspection, the samples should be selected from different tendons.5.2 Tensile tests should be made on at least three samples cut from each removed wire or strand (one at each end and one at mid-length;

the samples should be the maximum.length practical for testing).

If frequent stress cycling is suspected, tests simulating this condition should be conducted.

Similarly, where the inservice inspection program indicates the possibility of a poten-tially corrosive atmosphere, accelerated corrosion tests should be made.6. Inspection of Filler Grease The method used for checking the presence of sheathing filler grease should account for (1) the minimum grease coverage needed for different parts of the anchorage system including, for example, button-heads; (2) the influence of temperature variations, especially the lowest temperature likely to occur between two successive inspections;

(3) the procedure used to uncover possible voids in grease in the trumpet;and (4) requirements imposed by grease specifications, qualification tests, and acceptability tolerances.

7. Acceptance Criteria 7.1 The prestress force measured for each tendon in the tests described in regulatory position C.4 should be within the limits predicted for the time of the test.7.2 There should be no more than one defective tendon in the total sample population.

If one sample tendon is defective, an adjacent tendon on each side of the defective tendon should also be checked. If both of these tendons are acceptable as defined in regulatory position C.7.1, the inservice inspection program should proceed considering the single deficiency as unique and acceptable.

However, if efither adjacent tendon is defec-tive or if more than one tendon out of the original sample population is defective, the occurrence should be considered as unacceptable.

UNITED STATES NUCLEAR REGULATORY

COMMISSION

WASHINGTON, D. C. 20555 OFFiCIAL BUSINESS PENALTY FOR PRIVATE USE. 300 7.3 Failure in the tensile test should not occur at a strength value less than the guaranteed ultimate strength of the tendon material.

Failure below this value in any tendon material sample should be considerea as unaccep-table.8. Reporting to the Commission If the acceptance criteria of regulatory position C.7 are not met or if abnormal material behavior is detected as described in regulatory positions C.3 and C.6, a possible abnormal degradation of the containment struc-ture (a boundary designed to contain radioactive mate-rials) is indicated.

Such an occurrence should be reported to the Commission.

The'report should include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the I inspection procedure, the tolerances on cracking, and the measures to be used when tolerances are exceeded.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide.This guide reflects current NRC practice.

Therefore, except in those cases in which the applicant proposes an acceptable alternative method for complying with speci-fied portions of the Commission's regulations, this guide will be used by the NRC staff in evaluating construction permit and operating license applications for plants whose construction permits are docketed after the date of publication of the guide.3The report to the Commission should be made in accordance with the reporting program summarized in Regulatory Guide 1.16, "Reporting of Operating Information

-Appendix A Technical Specification." POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORY

COMMISSION

S .