Regulatory Guide 1.20: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A367
| number = ML003739957
| issue date = 06/30/1975
| issue date = 05/31/1976
| title = Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing
| title = Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.020, Rev. 1
| document report number = RG-1.20, Rev 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 8
| page count = 9
}}
}}
{{#Wiki_filter:Revision 1 U.S. NUCLEAR REGULATORY COMMISSION                                                                                                                 June 1975 REGULATORY GUIDE
{{#Wiki_filter:Revision 2 U.S. NUCLEAR REGULATORY COMMISSION                                                                                                                   May 1976 REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
        OFFICE OF STANDARDS DEVELOPMENT
                                                                REGULATORY GUIDE 1.20
                                                                        REGULATORY GUIDE 1.20
                                  COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM
                                        COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM
                                                      FOR REACTOR INTERNALS DURING
                                                          FOR REACTOR INTERNALS DURING
                                    PREOPERATIONAL AND INITIAL STARTUP TESTING
                                          PREOPERATIONAL AND INITIAL STARTUP TESTING


==A. INTRODUCTION==
==A. INTRODUCTION==


==B. DISCUSSION==
==B. DISCUSSION==
Criterion 1, "Quality Standards and Records," of                                    Reactor internals important to safety are designed to Appendix A, "General Design Criteria for Nuclear'Power                            accommodate steady-state and transient vibratory loads Plants," to 10 CFR Part 50, "Licensing of Production                               for the service life of the reactor. This guide presents a and Utilization Facilities," requires that structures,                            comprehensive vibration assessment program for use in systems, and components important to safety be                                    verifying the structural integrity of the reactor internals designed, fabricated, erected, and tested to quality                              for flow-induced vibrations prior to commercial opera- standards commensurate with the importance of the                                  tion. The overall program includes individual analytical, safety functions to be performed. Section 50.34, "Con-                            measurement, and inspection programs. The term "com- tents of Applications; Technical Information," of 10                              prehensive" appears in the title of the overall program to CFR Part 50 requires the applicant to determine and to                             emphasize that the individual programs should be used specify the margin of safety associated with normal                               cooperatively to verify structural integrity and to estab- operation and anticipated operating transients.                                   lish the margin of safety. For example, the analytical program not only should be used to provide theoretical This guide presents a method acceptable to the NRC                            verification of structural integrity but also should be the staff for implementing the above requirements with                                 basis for the choice of components and areas to be respect to the internals of light-water-cooled reactors'                           monitored in the measurement and inspection programs;
Criterion 1, "Quality Standards and Records," of                                    Reactor internals important to safety are designed to Appendix A, "General Design Criteria for Nuclear Power                            accommodate steady-state and transient vibratory loads Plants," to 10 CFR Part 50, "Licensing of Production                               for the service life of the reactor. This guide presents a and Utilization Facilities," requires that structures,                            comprehensive vibration assessment program for use in systems, and components important to safety be                                    verifying the structural integrity of the reactor internals designed, fabricated, erected, and tested to quality                              for flow-induced vibrations prior to commercial opera standards commensurate with the importance of the                                  tion. The overall program includes individual analytical, safety functions to be performed. Section 50.34, "Con                             measurement, and inspection programs. The term "com tents of Applications; Technical Information," of 10                              prehensive" appears in the title of the overall program to CFR Part 50 requires the applicant to determine and to                             emphasize that the individual programs should be used specify the margin of safety associated with normal                                 cooperatively to verify structural integrity and to estab operation and anticipated operating transients.                                     lish the margin of safety. For example, the analytical program not only should be used to provide theoretical This guide presents a method acceptable to the NRC                            verification of structural integrity but also should be the
during preoperational and initial startup testing. 2 Inser-                        the measurement program should be used to confirm the vice inspections and inservice monitoring programs to                              analysis, but the program (i.e., data acquisition, reduc- verify that the reactor internal components have not                               tion, interpretation processes) should be sufficiently been subjected to structural degradation as a result of                           flexible to permit definition of any significant vibratory vibration during normal reactor operation are not                                 modes that are present but were not included in the covered by this guide.                                                            analysis; the inspection program should be considered and used as a powerful tool for quantitative (e.g., as an indicator of maximum total relative motion) as well as qualitative (e.g., establishment of boundary conditions by inspection evidence at component interfaces) verifica-
*-'  staff for implementing the above requirements with                                 basis for the choice of components and areas to be respect to the internals of light-water-cooled reactors'                           monitored in the measurement and inspection programs;
'Reactor internals, as used in this regulatory guide, comprise                     tion of both the analytical and measurement program core support structures and adjoining internal structures. Core                   results.
      during preoperational and initial startup testing. 2 Inser                         the measurement program should be used to confirm the vice inspections and inservice monitoring programs to                              analysis, but the program (i.e., data acquisition, reduc verify that the reactor internal components have not                               tion, interpretation processes) should be sufficiently been subjected to structural degradation as a result of                             flexible to permit definition of any significant'vibratory I vibration during normal reactor operation are not covered by this guide. The Advisory Committee on Reactor Safeguards has been consulted concerning this modes that are present but were not included in the analysis; the inspection program should be considered and used as a powerful tool for quantitative (e.g., as an guide and has concurred in the Regulatory Position.                                indicator of maximum total relative motion) as well as qualitative (e.g., establishment of boundary conditions lReactor internals, as used in this regulatory guide, comprise                     by inspection evidence at component interfaces) verifica core support structures and adjoining internal structures. Core                  tion of both the analytical and measurement program support and internal structures are defined in Article NG-1120                   results.


support and internal structures are defined in Article NG-I 120
of Section III (Nuclear Power Plant Components) of the ASME
  of Section 111 (Nuclear Power Plant Components) of the ASME
        Boiler and Pressure Vessel Code.
  Boiler and Pressure Vessel Code.


The original guidelines of Regulatory Guide 1.20 have kConsistent with Regulatory Guide 1.68, "Preoperational and                        been refined in this revision to incorporate items that Initial Startup Test Programs for Water-Cooled Power                             will expedite review of the applicant's vibration assess- Reactors," preoperational testing as used in this guide consists of those tests conducted prior to fuel loading, and intial startup               ment program by the NRC staff. Generally, this has been testing refers to those tests performed after fuel loading.                       accomplished by increased specificity in the guidelines USNRC REGULATORY GUIDES                                        Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regulatory Guide% ate issud to describe and matte available to the publc            Regulatory Commission. Washington, D.C. 20566. Attention Dockelting and methods acceptable tO the NRC staff of implementing specific pans of the            Service Section.
The original guidelines of Regulatory Guide 1.20
      konsistent with Regulatory Guide 1.68, "Preoperational and                        were refined in Revision 1 to incorporate items that Initial Startup Test Programs for Water-Cooled Power                             would expedite review of the applicant's vibration Reactors," preoperational testing as used in this guide consists of those tests conducted prior to fuel loading, and intial startup               assessment program by the NRC staff. Generally, this testing refers to those tests performed after fuel loading.                     was accomplished by increased specificity in the guide lines for the vibration analysis, measurement, and
    *Lines indicate substantive changes from previous issue.


Commisson's regulations. In delineate techniques used by the staff in vavlu         The guides are Issued in the following ten broad divisions sling specsifc problems or postulated accidents, or to provide guidance to oppli cants Regulatory Guides are not substitutes lor regulations. and compliance          I. Power Reactors                        6, Products w"th therr is no. required. Methods and solutions dilterent from those set out in    2 Research and Test Reactors            7. Transportation the gurdes will be acceptable if they provide a basis tor the findings requisita to  3. Fuels and Materials Facilities        S. Occupational Health the tsluence or continuance of a permit or license by the Commission                4. Environmental and Siting              9. Antltrust Review Comments and suggestions for improvements in these guide% are encourageo            S  Materials and Plant Protection      10. Genteal at all times. and guides wilt be tewised. as eppropriate, to accommodate corn ments and to reflect new informatton or eaperience However, comments on              Copies of published guides may be obtained by written request indicating the thins gurde. If recersed within about two months ailts ats issuance. will be par      divisions desired to the U.S. Nuclear RegulatotV Commission. Washinglon. 0 C.
inspection programs and by inclusion of guidelines for USNRC REGULATORY GUIDES                                          Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regulatory Guides are issued to describe and make available to the public            Regulatory Commissiooi.    Washington. D.C    20566. Attention Docketing and methods acceptable to the NRC staff of implementing specific parts of the            Service Section Commission's regulations, to delineate techniques used by the staff in evalu         The guides are issued in the following ten broad divisions:
    sting specific problems or postulated accidents, or to provide guidance to appli.


Kcuterly useful in evaluating the need for an early tevismon                        2066M. AttentloA. Direitor. Of tice of Standards Development
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 and 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. Occupa,.onal Health the issuance or continuance of a permit or license by the Commission.                4. Environmental and Siting            8. Antitrust Review Comments and suggestions for improvements in these guides are encouraged              5. 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 experience. This guide was revised as a      Copies of published guides may be obtained by written request 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.


for the vibration analysis, measurement, and inspection            sequently modified in design (e.g., as in item 1.3 below)
review.                                                                               20566. Attention: Director. Office of Standards Development.
  programs and by inclusion of guidelines for scheduling            remains a Valid Prototype relative to its original design.


significant phases of the comprehensive vibration assess- ment program.                                                              1.3 Conditional Prototype. A Valid Prototype that later experiences adverse inservice vibration The original guidelines served as the basis for testing        phenomena and subsequently has been modified in many prototype and similar-to-prototype (referred to in            arrangement, design, size, or operating conditions is this guide as non-prototype) reactor internals. Operating          designated a Conditional Prototype. Upon satisfying experience and the tendency for the design of sub-                  conditions described elsewhere in this guide, the Condi- sequent reactor internals to differ somewhat from that              tional Prototype serves as the reference design for of the initially designated prototypes have, in some                Non-Prototype, Category Ill and IV, reactor internals instances, made the basic prototype and non-prototype              configurations.
scheduling significant phases of the comprehensive vibra          sequently modified in design (e.g., as in item 1.3 below)
tion assessment program.                                         remains a Valid Prototype relative to its original design.


classifications difficult to apply, resulting in the need for
The original guidelines served as the basis for testing              .1.3 Conditional Prototype. A Valid Prototype many prototype and similar-to-prototype (referred to in          that later experiences adverse inservice vibration this guide as non-prototype) reactor internals. Operating        phenomena and subsequently has been modified in experience and the tendency for the design of sub                arrangement, design, size, or operating conditions is sequent reactor internals to differ somewhat from that            designated a Conditional Prototype. Upon satisfying of the initially designated prototypes, in some instances,       conditions described elsewhere in this guide, the Condi made the basic prototype and non-prototype classifica            tional Prototype serves as the reference design for tions difficult to apply, resulting in the need for               Non-Prototype, Category III and IV, reactor internals time-consuming case-by-case resolution of reactor inter          configurations.
*time-consuming case-by-case resolution of reactor                          1.4 Non-Prototype, Category 1. A reactor inter- internal classifications and corresponding vibration               nals configuration with substantially the same arrange- assessment programs.                                               ment, design., size, and operating conditions as a specified Valid Prototype and for which nominal differ- This revision expands on the previous classifications          ences in arrangement, design, size, and operating condi- and outlines an appropriate comprehensive vibration                tions have been shown by test or analysis to have no assessment program for each class. The new classifica-             significant effect on the vibratory response and tions are defined in regulatory position C.A below. In              excitation of those reactor internals important to safety.


general, the expanded classifications and corresponding programs allow for the use, under certain conditions, of                  1.5 Non-Prototype, Category II. A reactor prototype reactor internals that have experienced some              internals configuration with substantially the same size adverse inservice vibration phenomena as limited proto-            and operating conditions as a specified Valid Prototype, types and for the use, under certain conditions, of                but with some component arrangement or design differ- reactor internals that are in some respects structurally            ences that are shown by t.-st or analysis to have no dissimilar from the designated prototype as limited                  significant effect on the vibratory response and excita- non-prototypes. The expanded classifications will make              tion of those unmodified reactor internals important to the use of this guide compatible with design and                    safety.
nal classifications and corresponding vibration assess ment programs.                                                            1.4 Non-Prototype, Category I. A reactor inter nals configuration with substantially the same arrange Revision 1 expanded on the previous classifications          ment, design, size, and operating conditions as a and outlined an appropriate comprehensive vibration              specified Valid Prototype and for which nominal differ assessment program for each class. The classifications are        ences in arrangement, design, size, and operating condi defined in regulatory position C.I below. In general, the        tions have been shown by test or analysis to have no expanded classifications and corresponding programs              significant effect on the vibriatory response and allow for the use, under certain conditions, of prototype        excitation of those reactor internals important to safety.


operating experience.
reactor internals that have experienced some adverse inservice vibration phenomena as limited prototypes and                  1.5 Non-Prototype, Category II. A reactor for the use, under certain conditions, of reactor internals      internals configuration with substantially the same size that are in some respects structurally dissimilar from the        and operating conditions as a specified Valid Prototype, designated prototype as limited non-prototypes. The              but with some component arrangement or design differ expanded classifications make the use of this guide              ences that are shown by test or analysis to have no compatible with design and operating experience. Revi            significant effect on the vibratory response and excita sion 2 retains the expanded classifications of Revision 1.        tion of those unmodified reactor internals important to Some changes in the corresponding vibration assessment            safety.


1.6 Limited Valid Prototype. A Non-Prototype, Category 11 or Ill, reactor internals configuration that  
programs and in the reporting of results were made as a result of substantive public comments and additional                    1.6 Limited Valid Prototype. A Non-Prototype, staff review.                                                    Category II or III, reactor internals configuration that has successfully conrpleted the appropriate comprehen C


==C. REGULATORY POSITION==
==Q. REGULATORY POSITION==
has successfully completed the appropriate comprehen- sive vibration assessment program and has itself experi- The classifications provided in regulatory position C.1        enced no adverse inservice vibration phenomena. An should be used by the applicant to first categorize the             operating Valid Prototype that has demonstrated reactor internals according to design, operating param-            extended satisfactory inservice operation subsequent to a eters, and the operating experience of potential proto-              design modification may be considered a Limited Valid typed. The appropriate comprehensive vibration                      Prototype relative to the modified reactor internals assessment program should then be established from the              configuration. A Conditional Prototype that has demon- guidelines specified for that classification in the succeed-         strated extended satisfactory inservice operation may be ing sections of this guide. The comprehensive vibration            considered a Limited Valid Prototype.
sive vibration assessment program and has itself experi enced no adverse inservice vibration phenomena. An The classifications provided in regulatory position C. I      operating Valid Prototype that has demonstrated should be used by the applicant to categorize the reactor       extended satisfactory inservice operation subsequent to a internals according to design, operating parameters, and         design modification may be considered a Limited Valid the operating experience of potential prototypes. The           Prototype relative to the modified reactor internals appropriate comprehensive vibration assessment program           configuration. A Conditional Prototype that has demon should then be established from the guidelines specified        strated extended satisfactory inservice operation may be for that classification in the succeeding selections of this     considered a Limited Valid Prototype.


assessment programs outlined in this guide are sum- marized in Figure 1.                                                       1.7 Non-Prototype, Category 111. A reactor inter- nals configuration with substantially the same arrange-
guide. The comprehensive vibration assessment programs outlined in this guide are summarized in Figure 1.                       1.7 Non-Prototype, Category III. A reactor inter nals configuration with substantially the same arrange
    1. Classification of Reactor Internals Relative to the         ment, design, size, and operating conditions as a Comprehensive Vibration Assessment Program                         specified Conditional Prototype with insufficient operating history to justify it as a Limited Valid
    1. Classification of Reactor Internals Relative to the       ment, design, size, and operating conditions as a Comprehensive Vibration Assessment Program                       specified Conditional Prototype with insufficient
        1.1 Prototype. A reactor internals configuration,          Prototype. Differences in arrangement, design, size, and that, because of its arrangement, design, size, or operat-          operating conditions should be shown by test or analysis ing conditions, represents a first-of-a-kind or unique             to have no significant effect on the vibratory response design for which no Valid Prototype exists.                        and excitation of those reactor internals important to safety.
      1.1 Prototype. A reactor internals configuration,          operating history to justify it as a Limited Valid that, because of its arrangement, design, size, or operat         Prototype. Differences in arralpgement, design, size, and ing conditions, represents a first-of-a-kind or unique           operating conditions should be shown by test or analysis design for which no Valid Prototype exists.                      to have no significant effect on the vibratory response and excitation of those reactor internals important to
        1.2 Valid Prototype. A reactor internals config          safety.


1.2 Valid Prototype. A reactor internals config- uration that has successfully completed a comprehensive                   1.8 Non-Prototype, Category IV. A ieactor inter- vibration assessment program for Prototype reactor                nals configuration with substantially the same arrange- internals and has experienced no adverse inservice                ment, design, size, and operating conditions as a vibration phenomena. A Valid Prototype that is sub-                specified Limited Valid Prototype, where nominal differ-
uration that has successfully completed a comprehensive vibration assessment program for Prototype reactor                      1.8 Non-Prototype, Category IV. A reactor inter internals and has experienced no adverse inservice                nals configuration with substantially the game arrange vibration phenomena. A Valid Prototype that is sub-               ment, design, size, and operating conditions as a
                                                              1.20-2
                                                            1.20-2


Reactor internals configuration for which comprehensive vibration assessment program is defined.
Inservice problems resulting in component or operational modifications Valid Prototype modified
                                                            \ Extended satisfactory /
                                                              \ rnservice operation /
                                                          -~\~\            \      ,/
  NON-PROTOTYPE                                                                        NON-PROTOTYPE
      CATEGORY I                                                                          CATEGORY I II
  Substantially Similar                                                                Substantially Similar to to Valid Prototype                                                                  Conditional Prototype Analysis and Either                                                                  Analysis, Limited Extensive Measurements                                                                Measurements, and
    :or P-ull Inspection Full Inspection NON-PROTOTYPE
                                                                  CATEGORY IV
                                                            Substantially Similar to Limited Valid Prototvoe IZZJ              Reactor internals configuration for which comprehensive vibration assessment program is defined.


01I        Summary of comprehensive vibration assessment programs.
L I              Summary of comprehensive vibration assessment programs.


QD        Reactor internals reference design which, together with its test and operating experience, provides the basis for a specific comprehensive vibration assessment program.
cm                Reactor internals reference design which, together with its test and operating experience, provides the basis for a specific comprehensive vibration assessment program.


Indicates alternative paths FIGURE I - SUMMARY OF COMPREHENSIVE VIBRATION ASSESSMENT PROGRAMS
Indicates alternative paths FIGURE 1 - SUMMARY OF COMPREHENSIVE VIBRATION ASSESSMENT PROGRAMS
                                            1.20-3
                                                    1.20-3


ences in arrangement, design, size, and operating condi.         ciently simulated by the test conditions should be tions have been shown by test or analysis to have no             identified.)
specified Limited Valid Prototype, where nominal differ      ciently simulated by the test conditions should be ences in arrangement, design, size, and operating condi     identified.)
  significant effect on the vibratory response and excita- tion of those reactor internals important to safety.                       6. The anticipated structural or hydraulic vibratory response (defined in terms of frequency, Associated with the Prototype and the Category 1,11,        amplitude, and modal contributions) that is appropriate III, and IV Non-Prototype classifications are the               to each of the sensor locations for steady-state and comprehensive vibration assessment programs delineated          anticipated transient preoperational and startup test in regulatory positions C.2 and C.3 and summarized in            conditions.
tions have been shown by test or analysis to have no significant effect on the vibratory response and excita                 6. The anticipated structural or hydraulic tion of those reactor internals important to safety.         vibratory response (defined in terms of frequency, amplitude, and modal contributions) that is appropriate Associated with the Prototype and the Category I, II,    to each of the sensor locations for steady-state and III, and IV Non-Prototype classifications are the            anticipated transient preoperational and startup test comprehensive vibration assessment programs delineated      conditions.


Figure 1. The foregoing classifications are defined relative to the three prototype reference design classifi-                  7. The test acceptance criteria with permissible cations (i.e., Valid Prototype, Conditional Prototype,           deviations and the basis for the criteria. (The criteria Limited Valid Prototype) upon whose design, test, and           should be established in terms of maximum allowable operating experience the individual comprehensive                response levels in the structure and presented in terms of vibration assessment programs are based.                        maximum allowable response levels at sensor locations.)
in regulatory positions C.2 and C.3 and summarized in Figure 1. The foregoing classifications are defined                     7. The test acceptance criteria with permissible relative to the three prototype reference design classifi   deviations and the basis for the criteria. (The criteria cations (i.e., Valid Prototype, Conditional Prototype,       should be established in terms of maximum allowable Limited Valid Prototype) upon whose design, test, and       response levels in the structure and presented in terms of operating experience the individual comprehensive            maximum allowable response levels at sensor locations.)
    .2. Comprehensive Vibration Assessment Program for                    2.2 Vibration Measurement Program Prototype Reactor Internals A vibration measurement program should be The comprehensive vibration assessment program          developed and implemented to verify the structural should be implemented in conjunction with preopera-              integrity of the reactor internals, to determine the tional and initial startup testing. It should consist of a      margin of safety associated with steady-state and antici- vibration analysis, a vibration measurement program, an          pated transient conditions for normal operation and to inspection program, and a correlation of their results.          confirm the results of the vibration analysis. The vibration measurement program should include a
vibration assessment programs are based.
        2.1 Vibration Analysis Program                          description of:
            The vibration analysis should be performed for those steady-state and anticipated transient conditions                      1. The data acquisition and reduction system, that correspond to preoperadional and initial startup test      including:
and normal operating conditions. The vibration analysis submittal should include a summary of:                                          a. Transducer types and their specifications, including useful frequency and amplitude ranges.


1. The theoretical structural and hydraulic models and analytical formulations or scaling laws and                          b. Transducer positions, which should be scale models used in the analysis.                              sufficient to monitor significant lateral, vertical, and torsional structural motions of major reactor internal
2. Comprehensive Vibration Assessment Program for                2.2 Vibration Measurement Program Prototype Reactor Internals A vibration measurement program should be The comprehensive vibration assessment program        developed and implemented to verify the structural should be implemented in conjunction with preopera            integrity of the reactor internals, to determine the tional and initial startup testing. It should consist of a    margin of safety associated with steady-state and antici vibration analysis, a vibration measurement program, an      pated transient conditions for normal operation, and to inspection program, and a correlation of their results.      confirm the results of the vibration analysis. The vibration measurement program should include a
            2. The structural and hydraulic system natural        components in shell, beam, and rigid body modes of frequencies and associated mode shapes which may be             vibration, as well as significant hydraulic responses and excited during steady-state and anticipated transient             those parameters that define the input forcing operation.                                                         function.
      2.1 Vibration Analysis Program                        description of:
          The vibration analysis should be performed for those steady-state and anticipated transient conditions                  1. The data acquisition and reduction system, that correspond to preoperational and initial startup test    including:
and normal operating conditions. The vibration analysis submittal should include a summary of:                                      a. Transducer types and their specifications, including useful frequency and amplitude ranges.


3. The estimated random and deterministic                            c. Precautions being taken to ensure acquisi- forcing functions, including any very-low-frequency                tion of quality data (e.g., optimization of signal-to-noise components, for steady-state and anticipated transient            ratio, relationship of recording times to data reduction operation.                                                        requirements, choice of instrumentation system).
1. The theoretical structural and hydraulic models and analytical formulations or scaling laws and                     b. Transducer positions, which should be sufficient to monitor significant lateral, vertical, and scale models used in the analysis.
            4. The calculated structural and hydraulic                           d. On-line data evaulation system to provide responses for steady-state and anticipated transient              immediate verification of general quality and level of operation. (The random, deterministic, overall integrated        data.


maximum response, any very-low-frequency components of response, and the level of cumulative fatigue damage                          e. Procedures for determining frequency, should be identified.)                                            modal content, and maximum values of response.
torsional structural motions of major reactor internal
          2. The structural and hydraulic system natural      components in shell, beam, and rigid body modes of frequencies and associated mode shapes which may be           vibration, as well as significant hydraulic responses and excited during steady-state and anticipated transient        those parameters that can be used to confirm the input forcing function.


5. A comparison of the calculated structural                     2. Test operating conditions, including:
operation.
and hydraulic responses for preoperational and initial startup testing with those for normal operation. (Normal                       a. All steady-state and transient modes of operating conditions that are not accurately or suffi-           operation.
 
3. The estimated random and deterministic                        c. Precautions being taken to ensure acquisi forcing functions, including any very-low-frequency          tion of quality data (e.g., optimization of signal-to-noise components, for steady-state and anticipated transient        ratio, relationship of recording times to data reduction requirements, choice of instrumentation system).
operation.
 
4. The calculated structural and hydraulic                        d. On-line data evaluation system to provide responses for steady-state and anticipated transient          immediate verification of general quality and level of operation. (The random, deterministic, overall integrated    data.
 
maximum response, any very-low-frequency components of response, and the level of cumulative fatigue damage                    e. Procedures for determining frequency, should be identified.)                                        modal content, and maximum values of response.
 
5. A comparison of the calculated structural                 2. Test operating conditions, including:
and hydraulic responses for preoperational and initial startup testing with those for normal operation. (Normal                   a. All steady-state and transient modes of operating conditions that are not accurately or suffi-       operation.


1.20-4
1.20-4


b. The planned duration of all testing in                       2. A tabulation of specific inspection areas that
b. The planned duration of all testing in                     2. A tabulation of specific inspection areas that normal operating modes to ensure that each critical               can be used to verify segments of the vibration analysis component will have been subjected to at least 106                and measurement program.
,normal operating modes to ensure that each critical                 can be used to verify segments of the vibration analysis component will have been subjected to at least 1O0                  and measurement program.


cycles of vibration (i.e., computed at the component's minimum significant response frequency) prior to the                          3. A description of the inspection procedure, final inspection of the reactor internals. (If it is not          including the method of examination (e.g., visual and feasible to perform an inspection following the accumu-            nondestructive surface examinations), method of docu- lation of 107 cycles, the structural integrity of the              mentation, access provisions on the reactor internals, reactor internals should be verified by measurements              and specialized equipment to be employed during the which demonstrate that no significant change in struc-            inspections to detect and quantify evidence of the tural response resulting from component damage has                effects of vibration.
cycles of vibration (i.e., computed at the lowest fre quency for which the component has a significant                           3. A description of the inspection procedure, structural response) prior to the final inspection of the       including the method of examination (e.g., visual and reactor internals. The duration of testing for non              nondestructive surface examinations), method of docu prototype reactor internals should be no less than that          mentation, access provisions on the reactor internals, for the applicable reference reactor internals (i.e., Valid,    and specialized equipment to be employed during the Conditional, or Limited Valid Prototype).                        inspections to detect and quantify evidence of the effects of vibration.


occurred between the time vibration testing was initiated and after 107 cycles were accrued.)
c. Disposition of fuel assemblies. (Testing should be performed with the reactor internals impor                   2.4 Documentation of Results tant to safety and the fuel assemblies (or dummy assemblies which provide equivalent dynamic mass and                        The results of the vibration analysis, measure flow characteristics) in position. The test may be               ment, and inspection programs should be reviewed and conducted without real or dummy fuel assemblies if it             correlated to determine the extent to which the test can be shown by analytical or experimental means that             acceptance criteria are satisfied. A summary of the such conditions will yield conservative results.)                 results should be submitted to the Commission in the form of preliminary and final reports.
              c. Disposition of fuel assemblies. (Testing                 2.4 Documentation of Results should be performed with the reactor internals impor- tant to safety and the fuel assemblies (or dummy                             The results of the vibration analysis, measure- assemblies which provide equivalent dynamic mass and                ment, and inspection programs should be reviewed and flow characteristics) in position. The test may be                 correlated to determine the extent to which the test conducted without real or dummy fuel assemblies if it               acceptance criteria are satisfied. A summary of the can be shown by analytical or experimental means that               results should be submitted to the Commission as such conditions will yield conservative results.)                   follows:
        2.3 Inspection Program                                                  1. If the results of'the comprehensive vibration assessment program are acceptable, the final report The inspection program should provide for                should include:
inspections of the reactor internals prior to and follow- ing operation at those steady-state and transient modes                          a. A description of any deviations from the consistent with the test conditions for regulatory                  specified measurement and inspection programs, position C.2.2.2. The reactor internals should be                   including instrumentation reading and inspection removed from the reactor vessel for these inspections. If          anomalies, instrumentation malfunctions, and deviations removal is not feasible, the inspections should be                  from the specified operating conditions, performed by means of examination equipment appro- priate for in situ inspection. The inspection program                            b. A comparison between the measured and should include:                                                      analytically determined modes of structural and hydraulic response (including those parameters from
            1. A tabulation of all reactor internal compo-            which the input forcing function is determined) for the nents .,..d iocal areas to be inspected, including:                  purpose of establishing the validity of the analytical technique, a. All major load-bearing elements of the reactor internals relied upon to retain the core support                        c. A determination of the margin of safety structure in position.                                              associated with normal steady-state and anticipated transient operation, b. The lateral, vertical,      and  torsional restraints provided within the vessel.                                          d. An evaluation of measurements that exceeded acceptable limits not specified as test c. Those locking and bolting components              acceptance criteria or of observations that were unantici- whose failure could adversely affect the structural                pated and the disposition of such deviations.


integrity of the reactor internals.
1. The preliminary report should summarize an
      2.3 Inspection Program evaluation of the raw and, as necessary, limited proc essed data and the results of the inspection program with The inspection program should provide for respect to the test acceptance criteria. Anomalous data inspections of the reactor internals prior to and follow that could bear on the structural integrity of the reactor ing operation at those steady-state and transient modes consistent with the test conditions for regulatory                internals should be identified, as should the method to position C.2.2.2. The reactor internals should be                be used for evaluating such data.


2. If (1) inspection of the reactor internals d. Those surfaces that are known to be or             reveals defects, evidence of unacceptable motion, may become contact surfaces during operation.                     excessive or undue wear, (2) the results from the measurement program fail to satisfy the specified test e. Those critical locations on the reactor           acceptance criteria, or (3) the results from the analysis, internal components as identified by the vibration                 measurement, and inspection programs are inconsistent, analysis.                                                          the final report should also include an evaluation and description of the modifications or actions planned in f. The interior of the reactor vessel for            order to justify the structural adequacy of the reactor evidence of loose parts or foreign material.                      internals.
removed from the reactor vessel for these inspections. If removal is not feasible, the inspections should be                          2. If the results of the comprehensive vibration performed by means of examination equipment appro                assessment program are acceptable, the final report priate for in situ inspection. The inspection program            should include:
should include:
                                                                                a. A description of any deviations from the specified measurement and inspection programs,
          1. A tabulation of all reactor internal compo          including instrumentation reading and inspection nents and local areas to be inspected, including:                anomalies, instrumentation malfunctions, and deviations from the specified operating conditions, a. All major load-bearing elements of the reactor internals relied upon to retain the core support                      b. A comparison between the measured and structure in position.                                            analytically determined modes of structural and hydraulic response (including those parameters from b. The lateral, vertical,      and    torsional      which the input forcing function is determined) for the restraints provided within the vessel.                            purpose of establishing the validity of the analytical technique, c. Those locking and bolting components whose failure could adversely affect the structural                            c. A determination of the margin of safety integrity of the reactor internals.                              associated with normal steady-state and anticipated transient operation, d. Those surfaces that are known to be or may become contact surfaces during operation.                                 d. An evaluation of measurements that exceeded acceptable limits not specified as test e. Those critical locations on the reactor         acceptance criteria or of observations that were unantici internal components as identified by the vibration               pated and the disposition of such deviations.


1.20-5
analysis.


The collection, storage, and maintenance of         effects of such operation on the structural integrity of all records relevant to the analysis, measurement, and            the non-prototype reactor internals should be based on inspection phases of the comprehensive vibration assess-          the results of a comprehensive vibration assessment ment program should be consistent with Regulatory                program developed for the specific non-prototype classi- Guide 1.88, "Collection, Storage, and Maintenance of             fication (i.e., Categcry 1, 1I, Ill, or IV). The comprehen- Nuclear Power Plant Quality Assurance Records," which            sive vibration assessmcnt programs for non-prototype describes a method acceptable to the NRC staff for                reactor internals are outlined below. These programs complying with Criterion XVII, "Quality Assurance                should be scheduled and documented in accordance with Records," of Appendix B, "Quality Assurance Criteria              the guidelines for the program delineated in regulatory for Nuclear Power Plants and Fuel Reprocessing Plants,"          positions C.2.4 and C.2.5 for Prototype reactor inter- to 10 CFR Part 50.                                                nals.
3. If (1) inspection of the reactor internals f. The interior of the reactor vessel for           reveals defects, evidence of unacceptable motion, evidence of loose parts or foreign material.                     excessive or undue wear, (2) the results from the
                                                            1.20-5


2.5 Schedule                                                      3.1 Non-Prototype, Category I
measurement program fail to satisfy the specified test           composite report should be assumed by the applicant for acceptance criteria, or (3) the results from the analysis,        scheduling purposes.)
           A schedule should be established and submitted                    3.1.1 Vibration Analysis Program to the Commission during the construction permit review. The schedule should provide that:                                      The Valid Prototype should be specified and sufficient evidence should be provided to support the
measurement, and inspection programs are inconsistent, the final report should also include an evaluation and                      5. The preliminary and final reports, which description of the modifications or actions planned in            together summarize the results of the vibration analysis, order to justify the structural adequacy of the reactor           measurement, and inspection programs, will be pre internals.                                                        sented to the Commission within 60 and 180 days, respectively, of the completion of vibration testing.
          1. The reactor internals design will be classified      classification Non-Prototype, Category 1.


in the Preliminary Safety Analysis Report (PSAR) as a prototype or a specific category of non-prototype. (If                          The vibration analysis for the Valid Proto- the internals are classified as non-prototype, the appli-         type, which includes a summary of the anticipated cant should identify the applicable prototype reactor             structural and hydraulic response and test acceptance internals in the PSAR. Experimental or analytical                  criteria, should be modified to account for the nominal justification for the non-prototype classification should         differences that may exist between the Non-Prototype, be presented during the construction permit review.)               Category I, and Valid Prototype reactor internals.
4. The collection, storage, and maintenance of all records relevant to the analysis, measurement, and                3. Comprehensive Vibration Assessment Programs inspection phases of the comprehensive vibration assess          for Non-Prototype Reactor Internals ment program should be consistent with Regulatory Guide 1.88, "Collection, Storage, and Maintenance of                        Non-prototype reactor internals important to Nuclear Power Plant Quality Assurance Records," which            safety should be subjected during the preoperational and describes a method acceptable to the NRC staff for                initial startup test program to all significant flow modes complying with Criterion XVII, "Quality Assurance                associated with normal steady-state and anticipated Records," of Appendix B, "Quality Assurance Criteria              transient operation under the same test conditions for Nuclear Power Plants and Fuel Reprocessing Plants,"          imposed on the applicable prototype. Evaluation of the to 10 CFRPart 50.                                                effects of such operation on the structural integrity of the non-prototype reactor internals should be based on
      2.5 Schedule                                              the results of a comprehensive vibration assessment program developed for the specific non-prototype classi A schedule should be established and submitted        fication (i.e., Category I, II, III, or IV). The comprehen to the Commission during the construction permit                 sive vibration assessment programs for non-prototype review. The schedule should provide that:                        reactor internals are outlined below. These programs should be scheduled and documented in accordance with
          1. The reactor internals design will be classified    the guidelines for the program delineated in regulatory in the Preliminary Safety Analysis Report (PSAR) as a            positions C.2.4 and C.2.5 for Prototype reactor inter prototype or a specific category of non-prototype. The            nals.


2. A commitment will be established during                        3.1.2 Vibration Measurement Program the construction permit review regarding the scope of the comprehensive vibration assessment program.                                 The vibration measurement program may be omitted if the inspection program is implemented.
classification may be revised in the Final Safety Analysis Report if schedule changes with respect to the previ                      3.1 Non-Prototype, Category I
ously designated reference reactor make such reclassifi cation appropriate. (If the internals are classified as                      3.1.1 Vibration Analysis Program non-prototype, the applicant should identify the appli cable prototype reactor internals in the PSAR. Experi                          The Valid Prototype should be specified and mental or analytical justification for the non-prototype          sufficient evidence should be provided to support the classification should be presented during the construc            classification Non-Prototype, Category I.


3. A description of the vibration measurement and inspection phases of the comprehensive vibration                             If a measurement program is implemented in assessment program will be submitted to the Com-                   lieu of an inspection program, sufficient and appropriate mission in sufficient time to permit utilization of                instrumentation should be incorporated to verify that Commission recommendations. (A 90-day comment and                  the vibratory response of the Non-Prototype, Category 1, review period by the staff should be assumid by the                reactor internals is consistent with the results of the applic~ant for scheduling purposes.)                                vibration analysis, test acceptance criteria, and the vibratory response observed in the Valid Prototype. The
tion permit review.)
           4. A summary of the vibration analysis pro-              vibration measurement program should include a gram will be submitted to the Commission a minimum                  description of the data acquisition and reduction of 60 days prior to submittal of the description of the             systems and test operating conditions consistent with vibration measurement and inspection programs.                      the general guidelines for the vibration measurement program delineated in regulatory position C.2.2 for
                                                                                The vibration analysis for the Valid Proto
          5. The final report, which summarizes the              Prototype reactor internals.
          2. A commitment will be established during            type, which includes a summary of the anticipated the construction permit review regarding the scope of            structural and hydraulic response and test acceptance the comprehensive vibration assessment program.                   criteria, should be modified to account for the nominal differences that may exist between the Non-Prototype,
           3. A description of the vibration measurement         Category I, and Valid Prototype reactor internals.


results of the vibration analysis, measurement, and inspection programs, will be presented to the Com-                            3.1.3 Inspection Program mission within 120 days of the completion of vibration testing,                                                                        If an inspection program is implemented in lieu of a vibration measurement program, the guidelines
and inspection phases of the comprehensive vibration assessment program will be submitted to the Com                             3.1.2 Vibration Measurement Program mission in sufficient time to permit utilization of Commission recommendations. (A 90-day comment and                              The vibration measurement program may be review period by the staff should be assumed by the               omitted if the inspection program is implemented.
    3. Comprehensive Vibration Assessment Programs                  for the inspection program delineated in regulatory for Non-Prototype Reactor Internals                                position C.2.3 for Prototype reactor internals should be followed.


Non-prototype reactor internals important to safety should be subjected during the preoperational and                         The inspection program may be omitted if initial startup test program to all significant flow modes         the vibration measurement program is implemented.
applicant for scheduling purposes.)
                                                                                If a measurement program is implemented in
          4. A summary of the vibration analysis pro              lieu of an inspection program, sufficient and appropriate gram will be submitted to the Commission a minimum                instrumentation should be incorporated to verify that of 60 days prior to submittal of the description of the          the vibratory response of the Non-Prototype, Category I,
vibration measurement and inspection programs. (As an            reactor internals is consistent with the results of the alternative, the information in this report may be               vibration analysis, test acceptance criteria, and the submitted to the Commission in conjunction with the              vibratory response observed in the Valid Prototype. The report specified in regulatory position C.2.5.3. In this         vibration measurement program should include a case, a 120-day comment and review period for the                description of the data acquisition and reduction
                                                            1.20-6


associated with normal steady-state and anticipated                However, if significant discrepancies exist between transient operation under the same test conditions                 anticipated and measured responses for specific compo- imposed on the applicable prototype. Evaluation of the             nents, those components should be removed froin the
systems and test operating conditions consistent with         reduction systems and test operating conditions con the general guidelines for the vibration measurement          sistent with the general guidelines for the vibration program delineated in regulatory position C.2.2 for            measurement program delineated in regulatory position Prototype reactor internals.                                  C.2.2 for Prototype reactor internals.
                                                              1.20-6


reactor vessel and a visual examination performed.              with the guidelines for Non-Prototype, Category 11, Components for which removal is not feasible should be         reactor internals and is consistent with the results examined in situ by means of appropriate inspection            obtained for similar components during the measure- equipment. In any case, the interior of the reactor vessel      ment program on the Valid Prototype.
3.1.3 Inspection Program                                          Sufficient and appropriate instrumentation should be used to define the vibratory response (i.e.,
              If an inspection program is implemented in      frequency, amplitude, modal content) of those reactor lieu of a vibration measurement program, the guidelines       internal components important to safety that have been for the inspection program delineated in regulatory            modified relative to the Valid Prototype for the purpose position C.2.3 for Prototype reactor internals should be       of demonstrating that the test acceptance criteria are followed.                                                     satisfied and establishing the margin of safety.


should be visually checked for loose parts and foreign material.                                                                 3.2.3 Inspection Program
The inspection program may be omitted if                      Sufficient and appropriate instrumentation the vibration measurement program is implemented.              should be used to monitor those reactor internal However, if significant discrepancies exist between            components important to safety that have not been anticipated and measured responses for specific compo        modified relative to the Valid Prototype to confirm that nents, those components should be removed from the            the vibratory response of such components complies reactor vessel and a visual examination performed.            with the guidelines for Non-Prototype, Category II,
      3.2 Non-Prototype, Category 11                                        An inspection program that follows the guidelines for the inspection program delineated in
Components for which removal is not feasible should be        reactor internals and is consistent with the results examined in situ by means of appropriate inspection            obtained for similar components during the measure equipment. In any case, the interior of the reactor vessel    ment program on the Valid Prototype.
 
should be visually checked for loose parts and foreign material.                                                               3.2.3 Inspection Program
        3.2 Non-Prototype, Category II                                      An inspection program that follows the guidelines for the inspection program delineated in
           3.2.1 Vibration Analysis Program                    regulatory position C.2.3 for Prototype reactor internals should be implemented.
           3.2.1 Vibration Analysis Program                    regulatory position C.2.3 for Prototype reactor internals should be implemented.


The Valid Prototype should be specified, and sufficient evidence should be provided to support                  3.3 Non-Prototype, Category III
and          The Valid Prototype should be specified, and sufficient evidence should be provided to support the classification Non-Prototype, Category II, which                 3.3 Non-Prototype, Category HI
the classification Non-Prototype, Category II, which requires demonstrating that the structural differences                   3.3.1 Vibration Analysis Program that exist between the Non-Prototype, Category II,
requires demonstrating that the structural differences that exist between the Non-Prototype, Category II,                       3.3.1 Vibration Analysis Program and Valid Prototype reactor internals have no significant effect on the vibratory response and excitation of those                     The Conditional Prototype should be unmodified Non-Prototype, Category II, components.             specified, and sufficient analytical or experimental evidence should be provided to support the classification The vibration analysis for the Valid Proto      Non-Prototype, Category III, as well as to demonstrate type, which includes a summary of the anticipated              the applicability of data from the vibration measurement structural and hydraulic response and test acceptance          program on the Prototype to the Conditional Prototype.
and Valid Prototype reactor internals have no significant                   The Conditional Prototype should be effect on the vibratory response and excitation of those       specified, and sufficient analytical or experimental unmodified Non-Prototype, Category Ii, components.             evidence should be provided to support the classification Non-Prototype, Category I11, as well as to demonstrate The vibration analysis for the Valid Proto-        the applicability of data from the vibration measurement type, which includes a summary of the anticipated               program on the Prototype to the Conditional Prototype.
 
criteria, should be modified to account for the structural    It should be demonstrated that:
differences that exist between the Valid Prototype and Non-Prototype, Category 1I, reactor internals.                                  1. The Conditional Prototype is sub stantially similar in arrangement, design, size, and Test acceptance criteria should specifically    operating conditions to the Non-Prototype, Category III,
be established for those Non-Prototype, Category II,          reactor internals.
 
reactor internal components with structural differences relative to the Valid Prototype.                                                2. Response modes attributable to the inservice vibration problems and ensuing component or
          3.2.2 Vibration Measurement Program                operational modifications do not significantly affect the applicability of the results of the vibration measurement A vibration measurement program should be       program on the Prototype to the Conditional Prototype, implemented on the Non-Prototype, Category II, reactor        or response modes attributable to the inservice vibration internals during preoperational and initial startup            problems and ensuing component or operational modifi testing.                                                      cations do affect the applicability of the results of the vibration measurement program on the Prototype to the The vibration measurement program should        Conditional Prototype, but the effects are limited to include a description of the data acquisition and              structural components and response modes that permit
                                                        1.20-7
 
clear separation of these effects from other results of the     regulatory position C.2.3 for Prototype reactor internals vibration measurement program.                                  should be implemented.
 
Details concerning the adverse vibration                  3.4 Non-Prototype, Category IV
experience of the Conditional Prototype should be provided, as should experimental or analytical informa                    3.4.1 Vibration Analysis Program tion which demonstrates that the vibration problems associated with the Conditional Prototype have been                            The Limited Valid Prototype should be corrected for both it and the applicable Non-Prototype,          specified, and sufficient evidence should be provided to Category III, reactor internals.                                support the classification Non-Prototype, Category IV.
 
The vibration analysis on the Prototype to the Conditional Prototype, which includes a summary of                     3.4.2 Vibration Measurement Program the anticipated structural and hydraulic response and test acceptance criteria for the measurement program on                       A vibration measurement program may be the Prototype, should be modified to account for the            omitted if the inspection program is implemented.


structural and hydraulic response and test acceptance          It should be demonstrated that:
component or operational modifications applicable to the Conditional Prototype and Non-Prototype, Category                          If a measurement program is implemented in III, reactor internals.                                          lieu of an inspection program, sufficient and appropriate instrumentation should be incorporated to verify that the vibratory response of the Non-Prototype, Category Test acceptance criteria, with permissible deviations, should be specified for reactor internal            IV, reactor internals is consistent with the results of the components important to safety. Each component                   vibration analysis, test acceptance criteria, and the should be categorized according to whether the results          vibratory response for the referenced limited Valid from the vibration measurement program on the Proto              Prototype.
criteria, should be modified to account for the structural differences that exist between the Valid Prototype and                            1. The Conditional Prototype is sub- Non-Prototype, Category !1,reactor internals.                  stantially similar in arrangement, design, size, and operating conditions to the Non-Prototype, Category Ill.


Test acceptance criteria should specifically    reactor internals.
type to the Conditional Prototype are applicable.


be established for those Non-Prototype, Category II,
The vibration measurement program should
reactor internal components with structural differences                          2. Response modes attributable to the relative to the Valid Prototype.                                inservice vibration problems and ensuing component or operational modifications do not significantly affect the
           3.3.2 Vibration Measurement Program                   be consistent with the guidelines delineated in regulatory position C.3.1.2 for the measurement program for A vibration measurement program should be           Non-Prototype, Category I, reactor internals.
           3.2.2 Vibration Measurement Program                 applicability of the results of the vibration measurement program on the Prototype to the Conditional Prototype, A vibration measurement program should be       or response modes attributable to the inservice vibration implemented on the Non-Prototype, Category II, reactor         problems and ensuing component or operational modifi- internals during preoperational and initial startup            cations do affect the applicability of the results of the testing.                                                        vibration measurement program on the Prototype to the Conditional Prototype, but the effects are limited to The vibration measurement program should          structural components and response modes that permit include a description of the data acquisition and              clear separation of these effects from other results of the reduction systems and test operating conditions con-            vibration measurement program.


sistent with the general guidelines for the vibration measurement program delineated in regulatory position                        Details concerning the adverse vibration C.2.2 for Prototype reactor internals.                          experience of the Conditional Prototype should be provided, as should experimental or analytical informa- Sufficient and appropriate instrumentation        tion which demonstrates that the vibration problems should be used to define the vibratory response (i.e.,          associated with the Conditional Prototype have been frequency, amplitude, modal content) of those reactor          corrected for both it and the applicable Non-Prototype.
implemented on the Non-Prototype, Category III,
reactor internals during preoperational and initial startup                3.4.3 Inspection Program testing.


internal components important to safety that have been          Category Ill, reactor internals.
If an inspection program is implemented in lieu of a vibration measurement program, the guidelines Sufficient and appropriate instrumentation for the    inspection program delineated in regulatory should be used to define the vibratory response of those position  C.3.1.3 for Non-Prototype, Category I, reactor reactor components important to safety which, because of structural or operational modifications relative to the        internals should be followed.


modified relative to the Valid Prototype for the purpose of demonstrating that the test acceptance criteria are                      The vibration analysis on the Prototype to satisfied and establishing the margin of safety.                the Conditional Prototype, which includes a summary ot'
original design of the Conditional Prototype, are expected to have response characteristics substantially different from those measured for that component during the vibration measurement program on the                                    
                                                                the anticipated structural and hydraulic response and Sufficient and appropriate instrumentation        test acceptance criteria for the measurement program on should be used to monitor those reactor internal                the Prototype, should be modified to account for the components important to safety that have not been              component or operational modifications applicable to moc'ified relative to the Valid Prototype to confirm that      the Conditional Prototype and Non-Prototype, Category the vibratory response of such components complies              Ill, reactor internals.


.20-7
==D. IMPLEMENTATION==
Prototype to the Conditional Prototype.


Test acceptance criteria, with permissible                    3.4.2 Vibration Measurement Program deviations, should be specified for reactor internal components important to safety. Each component                              A vibration measurement program may be should be categorized according to whether the results          omitted if the inspection program is implemented.
The purpose of this section is to provide guidance to All other components should be monitored          applicants and licensees regarding the NRC staffs plans with sufficient and appropriate instrumentation to con          for utilizing this regulatory guide.


from the vibration measurement program on tie Proto- type to the Conditional Prototype are applicable.                            If a measurement program is implemented in lieu of an inspection program, sufficient and appropriate
firm that the measured response for each component is substantially similar to that obtained during the vibra              Except in those cases in which the applicant proposes tion measurement program on the Prototype to the                 an acceptable alternative method for complying with Conditional Prototype.
          3.3.2 Vibration Measurement Program                    instrumentation should be incorporated to verify that the vibratory response of the Non-Prototype, Category A vibration measurement program should be          IV, reactor internals is consistent with the results of the implemented on the Non-Prototype, Category III,                  vibration analysis. test acceptance criteria, and the reactor internals during preoperational and initial startup      vibratory response for the referenced Limited Valid testing.                                                        Prototype.


Sufficient and appropriate instrumentation                      The vibration measurement program should should be used to define the vibratory response of those        be consistent with the guidelines delineated in regulatory reactor components important to safety which, because            position C.3.1.2 for the measurement program for of structural or operational modifications relative to the      Non-Prototype, Category 1, reactor internals.
specified portions of the Commission's regulations, the method described herein will be used in the evaluation The vibration measurement program should           of submittals for operating license or construction satisfy the general guidelines for a Prototype measure          permit applications docketed after June 22, 1976.


original design of the Conditional Prototype, are expected to have response characteristics substantially different from those measured for that component                          3.4.3 Inspection Program during the vibration measurement program on the Prototype to the Conditional Prototype.                                      If an inspection program is implemented in lieu of a vibration measurement program, the guidelines All other components should be monitored            for the inspection program delineated in regulatory with sufficient and appropriate instrumentation to con-          position C.3.1.3 for Non-Prototype, Category 1, reactor firm that the measured response for each component is            internals should be followed.
ment program as delineated in regulatory position C.2.2.


substantially similar to that obtained during the vibia- tion measurement program on the Prototype to the Conditional Prototype.
3.3.3 Inspection Program                                  If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or An inspection program that satisfies the          before June 22, 1976, the pertinent portions of the guidelines for the inspection program delineated in              application will be evaluated on the basis of this guide.


The vibration measurement program should                             
1.20-8


==D. IMPLEMENTATION==
SPROTOTYPE
satisfy the general guidelines for a Prototype measure- ment program as delineated in regulatory position C.2.2.            The purpose of this section is to provide guidance to applicants and licensees regarding the NRC staff's plans
                                  [Unique or first of a kind Analysis, Extensive Measurement, and Full Inspection I
          3.3.3 Inspection Program                              for utilizing this regulatory guide.
                                                            JInservice  problems resulting in component    or Vlid :Proto"          prtoa        oiiain              Conditional
                                                                                        //
        CATEGORY I
                                        NON-PROTOTYPE              \INON-PROTOTYPE
                                          CATEGORY II                                          CTGR
                                    Similar to ValidPrototype                                    CTG          Ill Substantially  Similar PROTOTYPEyp tNON
  ,to Valid-Prototype                              but omeompoent                /    /Substantially  Similar to differences                                      Conditional Prototype Analysis and Either                Analysis, Limited                      //Analysis,              Limited Extensive Measurements              Measurements, and                .A 1'Measurements, and or Full Inspection                Full Inspection                  M' I.                Full Inspection II
                                                                      Limited Valid Prototype NON-PROTOTYPE
                                                                    CATEGORCYIV
                                                                Similar        Substantially Similar to Limited Valdid Prototype Reatocofiuraio ineral        fr wiccoprhestn      iveySiiart Analysis and    Either Extensive Measurements or Full Inspection GIlD                  Reactor internals configuration for which comprehensive vibration assessment program is defined.


An inspection program that satisfies the Except in those cases in which the applicant proposes guidelines for the inspection program delineated in an acceptable alternative method for complying with regulatory position C.2.3 for PrototN pe reactor internals spc-:ified poitions of the Commission's regulations, the should be implemented.
EZZJ                Summary of comprehensive vibration assessment programs.


method described herein will be used in the evaluation
QID
      3.4 Non-Prototype, Category IV                            of submittals for operating license or construction permit applications docketed after August 21, 1975.
                      Reactor internals reference design which, together with its test and operating experience, provides the basis for a specific comprehensive vibration assessment program.


3.4.1 Vibration Analysis Program If an applicant wishes to use this regulatory guide in The Limited Valid Prototype should be              developing submittals for applications docketed on ur specified, and sufficient evidence should be provided to        before August 21, 1975, the pertinent portions of the support the classification Non-Prototype, Category IV.          application will be evaluated on the basis of this guide.  d
Indicates alternative paths}}
                                                            1.20-8
                                                                                                                            4}}


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Revision as of 10:26, 28 March 2020

Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing
ML003739957
Person / Time
Issue date: 05/31/1976
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.20, Rev 2
Download: ML003739957 (9)
v • d • e


Revision 2 U.S. NUCLEAR REGULATORY COMMISSION May 1976 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.20

COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM

FOR REACTOR INTERNALS DURING

PREOPERATIONAL AND INITIAL STARTUP TESTING

A. INTRODUCTION

B. DISCUSSION

Criterion 1, "Quality Standards and Records," of Reactor internals important to safety are designed to Appendix A, "General Design Criteria for Nuclear Power accommodate steady-state and transient vibratory loads Plants," to 10 CFR Part 50, "Licensing of Production for the service life of the reactor. This guide presents a and Utilization Facilities," requires that structures, comprehensive vibration assessment program for use in systems, and components important to safety be verifying the structural integrity of the reactor internals designed, fabricated, erected, and tested to quality for flow-induced vibrations prior to commercial opera standards commensurate with the importance of the tion. The overall program includes individual analytical, safety functions to be performed. Section 50.34, "Con measurement, and inspection programs. The term "com tents of Applications; Technical Information," of 10 prehensive" appears in the title of the overall program to CFR Part 50 requires the applicant to determine and to emphasize that the individual programs should be used specify the margin of safety associated with normal cooperatively to verify structural integrity and to estab operation and anticipated operating transients. lish the margin of safety. For example, the analytical program not only should be used to provide theoretical This guide presents a method acceptable to the NRC verification of structural integrity but also should be the

  • -' staff for implementing the above requirements with basis for the choice of components and areas to be respect to the internals of light-water-cooled reactors' monitored in the measurement and inspection programs;

during preoperational and initial startup testing. 2 Inser the measurement program should be used to confirm the vice inspections and inservice monitoring programs to analysis, but the program (i.e., data acquisition, reduc verify that the reactor internal components have not tion, interpretation processes) should be sufficiently been subjected to structural degradation as a result of flexible to permit definition of any significant'vibratory I vibration during normal reactor operation are not covered by this guide. The Advisory Committee on Reactor Safeguards has been consulted concerning this modes that are present but were not included in the analysis; the inspection program should be considered and used as a powerful tool for quantitative (e.g., as an guide and has concurred in the Regulatory Position. indicator of maximum total relative motion) as well as qualitative (e.g., establishment of boundary conditions lReactor internals, as used in this regulatory guide, comprise by inspection evidence at component interfaces) verifica core support structures and adjoining internal structures. Core tion of both the analytical and measurement program support and internal structures are defined in Article NG-1120 results.

of Section III (Nuclear Power Plant Components) of the ASME

Boiler and Pressure Vessel Code.

The original guidelines of Regulatory Guide 1.20

konsistent with Regulatory Guide 1.68, "Preoperational and were refined in Revision 1 to incorporate items that Initial Startup Test Programs for Water-Cooled Power would expedite review of the applicant's vibration Reactors," preoperational testing as used in this guide consists of those tests conducted prior to fuel loading, and intial startup assessment program by the NRC staff. Generally, this testing refers to those tests performed after fuel loading. was accomplished by increased specificity in the guide lines for the vibration analysis, measurement, and

  • Lines indicate substantive changes from previous issue.

inspection programs and by inclusion of guidelines for USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Commissiooi. Washington. D.C 20566. Attention Docketing and methods acceptable to the NRC staff of implementing specific parts of the Service Section Commission's regulations, to delineate techniques used by the staff in evalu The guides are issued in the following ten broad divisions:

sting 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 and 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. Occupa,.onal Health the issuance or continuance of a permit or license by the Commission. 4. Environmental and Siting 8. Antitrust Review Comments and suggestions for improvements in these guides are encouraged 5. 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 experience. This guide was revised as a Copies of published guides may be obtained by written request 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. 20566. Attention: Director. Office of Standards Development.

scheduling significant phases of the comprehensive vibra sequently modified in design (e.g., as in item 1.3 below)

tion assessment program. remains a Valid Prototype relative to its original design.

The original guidelines served as the basis for testing .1.3 Conditional Prototype. A Valid Prototype many prototype and similar-to-prototype (referred to in that later experiences adverse inservice vibration this guide as non-prototype) reactor internals. Operating phenomena and subsequently has been modified in experience and the tendency for the design of sub arrangement, design, size, or operating conditions is sequent reactor internals to differ somewhat from that designated a Conditional Prototype. Upon satisfying of the initially designated prototypes, in some instances, conditions described elsewhere in this guide, the Condi made the basic prototype and non-prototype classifica tional Prototype serves as the reference design for tions difficult to apply, resulting in the need for Non-Prototype, Category III and IV, reactor internals time-consuming case-by-case resolution of reactor inter configurations.

nal classifications and corresponding vibration assess ment programs. 1.4 Non-Prototype, Category I. A reactor inter nals configuration with substantially the same arrange Revision 1 expanded on the previous classifications ment, design, size, and operating conditions as a and outlined an appropriate comprehensive vibration specified Valid Prototype and for which nominal differ assessment program for each class. The classifications are ences in arrangement, design, size, and operating condi defined in regulatory position C.I below. In general, the tions have been shown by test or analysis to have no expanded classifications and corresponding programs significant effect on the vibriatory response and allow for the use, under certain conditions, of prototype excitation of those reactor internals important to safety.

reactor internals that have experienced some adverse inservice vibration phenomena as limited prototypes and 1.5 Non-Prototype, Category II. A reactor for the use, under certain conditions, of reactor internals internals configuration with substantially the same size that are in some respects structurally dissimilar from the and operating conditions as a specified Valid Prototype, designated prototype as limited non-prototypes. The but with some component arrangement or design differ expanded classifications make the use of this guide ences that are shown by test or analysis to have no compatible with design and operating experience. Revi significant effect on the vibratory response and excita sion 2 retains the expanded classifications of Revision 1. tion of those unmodified reactor internals important to Some changes in the corresponding vibration assessment safety.

programs and in the reporting of results were made as a result of substantive public comments and additional 1.6 Limited Valid Prototype. A Non-Prototype, staff review. Category II or III, reactor internals configuration that has successfully conrpleted the appropriate comprehen C

Q. REGULATORY POSITION

sive vibration assessment program and has itself experi enced no adverse inservice vibration phenomena. An The classifications provided in regulatory position C. I operating Valid Prototype that has demonstrated should be used by the applicant to categorize the reactor extended satisfactory inservice operation subsequent to a internals according to design, operating parameters, and design modification may be considered a Limited Valid the operating experience of potential prototypes. The Prototype relative to the modified reactor internals appropriate comprehensive vibration assessment program configuration. A Conditional Prototype that has demon should then be established from the guidelines specified strated extended satisfactory inservice operation may be for that classification in the succeeding selections of this considered a Limited Valid Prototype.

guide. The comprehensive vibration assessment programs outlined in this guide are summarized in Figure 1. 1.7 Non-Prototype, Category III. A reactor inter nals configuration with substantially the same arrange

1. Classification of Reactor Internals Relative to the ment, design, size, and operating conditions as a Comprehensive Vibration Assessment Program specified Conditional Prototype with insufficient

1.1 Prototype. A reactor internals configuration, operating history to justify it as a Limited Valid that, because of its arrangement, design, size, or operat Prototype. Differences in arralpgement, design, size, and ing conditions, represents a first-of-a-kind or unique operating conditions should be shown by test or analysis design for which no Valid Prototype exists. to have no significant effect on the vibratory response and excitation of those reactor internals important to

1.2 Valid Prototype. A reactor internals config safety.

uration that has successfully completed a comprehensive vibration assessment program for Prototype reactor 1.8 Non-Prototype, Category IV. A reactor inter internals and has experienced no adverse inservice nals configuration with substantially the game arrange vibration phenomena. A Valid Prototype that is sub- ment, design, size, and operating conditions as a

1.20-2

Inservice problems resulting in component or operational modifications Valid Prototype modified

\ Extended satisfactory /

\ rnservice operation /

-~\~\ \ ,/

NON-PROTOTYPE NON-PROTOTYPE

CATEGORY I CATEGORY I II

Substantially Similar Substantially Similar to to Valid Prototype Conditional Prototype Analysis and Either Analysis, Limited Extensive Measurements Measurements, and

or P-ull Inspection Full Inspection NON-PROTOTYPE

CATEGORY IV

Substantially Similar to Limited Valid Prototvoe IZZJ Reactor internals configuration for which comprehensive vibration assessment program is defined.

L I Summary of comprehensive vibration assessment programs.

cm Reactor internals reference design which, together with its test and operating experience, provides the basis for a specific comprehensive vibration assessment program.

Indicates alternative paths FIGURE 1 - SUMMARY OF COMPREHENSIVE VIBRATION ASSESSMENT PROGRAMS

1.20-3

specified Limited Valid Prototype, where nominal differ ciently simulated by the test conditions should be ences in arrangement, design, size, and operating condi identified.)

tions have been shown by test or analysis to have no significant effect on the vibratory response and excita 6. The anticipated structural or hydraulic tion of those reactor internals important to safety. vibratory response (defined in terms of frequency, amplitude, and modal contributions) that is appropriate Associated with the Prototype and the Category I, II, to each of the sensor locations for steady-state and III, and IV Non-Prototype classifications are the anticipated transient preoperational and startup test comprehensive vibration assessment programs delineated conditions.

in regulatory positions C.2 and C.3 and summarized in Figure 1. The foregoing classifications are defined 7. The test acceptance criteria with permissible relative to the three prototype reference design classifi deviations and the basis for the criteria. (The criteria cations (i.e., Valid Prototype, Conditional Prototype, should be established in terms of maximum allowable Limited Valid Prototype) upon whose design, test, and response levels in the structure and presented in terms of operating experience the individual comprehensive maximum allowable response levels at sensor locations.)

vibration assessment programs are based.

2. Comprehensive Vibration Assessment Program for 2.2 Vibration Measurement Program Prototype Reactor Internals A vibration measurement program should be The comprehensive vibration assessment program developed and implemented to verify the structural should be implemented in conjunction with preopera integrity of the reactor internals, to determine the tional and initial startup testing. It should consist of a margin of safety associated with steady-state and antici vibration analysis, a vibration measurement program, an pated transient conditions for normal operation, and to inspection program, and a correlation of their results. confirm the results of the vibration analysis. The vibration measurement program should include a

2.1 Vibration Analysis Program description of:

The vibration analysis should be performed for those steady-state and anticipated transient conditions 1. The data acquisition and reduction system, that correspond to preoperational and initial startup test including:

and normal operating conditions. The vibration analysis submittal should include a summary of: a. Transducer types and their specifications, including useful frequency and amplitude ranges.

1. The theoretical structural and hydraulic models and analytical formulations or scaling laws and b. Transducer positions, which should be sufficient to monitor significant lateral, vertical, and scale models used in the analysis.

torsional structural motions of major reactor internal

2. The structural and hydraulic system natural components in shell, beam, and rigid body modes of frequencies and associated mode shapes which may be vibration, as well as significant hydraulic responses and excited during steady-state and anticipated transient those parameters that can be used to confirm the input forcing function.

operation.

3. The estimated random and deterministic c. Precautions being taken to ensure acquisi forcing functions, including any very-low-frequency tion of quality data (e.g., optimization of signal-to-noise components, for steady-state and anticipated transient ratio, relationship of recording times to data reduction requirements, choice of instrumentation system).

operation.

4. The calculated structural and hydraulic d. On-line data evaluation system to provide responses for steady-state and anticipated transient immediate verification of general quality and level of operation. (The random, deterministic, overall integrated data.

maximum response, any very-low-frequency components of response, and the level of cumulative fatigue damage e. Procedures for determining frequency, should be identified.) modal content, and maximum values of response.

5. A comparison of the calculated structural 2. Test operating conditions, including:

and hydraulic responses for preoperational and initial startup testing with those for normal operation. (Normal a. All steady-state and transient modes of operating conditions that are not accurately or suffi- operation.

1.20-4

b. The planned duration of all testing in 2. A tabulation of specific inspection areas that normal operating modes to ensure that each critical can be used to verify segments of the vibration analysis component will have been subjected to at least 106 and measurement program.

cycles of vibration (i.e., computed at the lowest fre quency for which the component has a significant 3. A description of the inspection procedure, structural response) prior to the final inspection of the including the method of examination (e.g., visual and reactor internals. The duration of testing for non nondestructive surface examinations), method of docu prototype reactor internals should be no less than that mentation, access provisions on the reactor internals, for the applicable reference reactor internals (i.e., Valid, and specialized equipment to be employed during the Conditional, or Limited Valid Prototype). inspections to detect and quantify evidence of the effects of vibration.

c. Disposition of fuel assemblies. (Testing should be performed with the reactor internals impor 2.4 Documentation of Results tant to safety and the fuel assemblies (or dummy assemblies which provide equivalent dynamic mass and The results of the vibration analysis, measure flow characteristics) in position. The test may be ment, and inspection programs should be reviewed and conducted without real or dummy fuel assemblies if it correlated to determine the extent to which the test can be shown by analytical or experimental means that acceptance criteria are satisfied. A summary of the such conditions will yield conservative results.) results should be submitted to the Commission in the form of preliminary and final reports.

1. The preliminary report should summarize an

2.3 Inspection Program evaluation of the raw and, as necessary, limited proc essed data and the results of the inspection program with The inspection program should provide for respect to the test acceptance criteria. Anomalous data inspections of the reactor internals prior to and follow that could bear on the structural integrity of the reactor ing operation at those steady-state and transient modes consistent with the test conditions for regulatory internals should be identified, as should the method to position C.2.2.2. The reactor internals should be be used for evaluating such data.

removed from the reactor vessel for these inspections. If removal is not feasible, the inspections should be 2. If the results of the comprehensive vibration performed by means of examination equipment appro assessment program are acceptable, the final report priate for in situ inspection. The inspection program should include:

should include:

a. A description of any deviations from the specified measurement and inspection programs,

1. A tabulation of all reactor internal compo including instrumentation reading and inspection nents and local areas to be inspected, including: anomalies, instrumentation malfunctions, and deviations from the specified operating conditions, a. All major load-bearing elements of the reactor internals relied upon to retain the core support b. A comparison between the measured and structure in position. analytically determined modes of structural and hydraulic response (including those parameters from b. The lateral, vertical, and torsional which the input forcing function is determined) for the restraints provided within the vessel. purpose of establishing the validity of the analytical technique, c. Those locking and bolting components whose failure could adversely affect the structural c. A determination of the margin of safety integrity of the reactor internals. associated with normal steady-state and anticipated transient operation, d. Those surfaces that are known to be or may become contact surfaces during operation. d. An evaluation of measurements that exceeded acceptable limits not specified as test e. Those critical locations on the reactor acceptance criteria or of observations that were unantici internal components as identified by the vibration pated and the disposition of such deviations.

analysis.

3. If (1) inspection of the reactor internals f. The interior of the reactor vessel for reveals defects, evidence of unacceptable motion, evidence of loose parts or foreign material. excessive or undue wear, (2) the results from the

1.20-5

measurement program fail to satisfy the specified test composite report should be assumed by the applicant for acceptance criteria, or (3) the results from the analysis, scheduling purposes.)

measurement, and inspection programs are inconsistent, the final report should also include an evaluation and 5. The preliminary and final reports, which description of the modifications or actions planned in together summarize the results of the vibration analysis, order to justify the structural adequacy of the reactor measurement, and inspection programs, will be pre internals. sented to the Commission within 60 and 180 days, respectively, of the completion of vibration testing.

4. The collection, storage, and maintenance of all records relevant to the analysis, measurement, and 3. Comprehensive Vibration Assessment Programs inspection phases of the comprehensive vibration assess for Non-Prototype Reactor Internals ment program should be consistent with Regulatory Guide 1.88, "Collection, Storage, and Maintenance of Non-prototype reactor internals important to Nuclear Power Plant Quality Assurance Records," which safety should be subjected during the preoperational and describes a method acceptable to the NRC staff for initial startup test program to all significant flow modes complying with Criterion XVII, "Quality Assurance associated with normal steady-state and anticipated Records," of Appendix B, "Quality Assurance Criteria transient operation under the same test conditions for Nuclear Power Plants and Fuel Reprocessing Plants," imposed on the applicable prototype. Evaluation of the to 10 CFRPart 50. effects of such operation on the structural integrity of the non-prototype reactor internals should be based on

2.5 Schedule the results of a comprehensive vibration assessment program developed for the specific non-prototype classi A schedule should be established and submitted fication (i.e., Category I, II, III, or IV). The comprehen to the Commission during the construction permit sive vibration assessment programs for non-prototype review. The schedule should provide that: reactor internals are outlined below. These programs should be scheduled and documented in accordance with

1. The reactor internals design will be classified the guidelines for the program delineated in regulatory in the Preliminary Safety Analysis Report (PSAR) as a positions C.2.4 and C.2.5 for Prototype reactor inter prototype or a specific category of non-prototype. The nals.

classification may be revised in the Final Safety Analysis Report if schedule changes with respect to the previ 3.1 Non-Prototype, Category I

ously designated reference reactor make such reclassifi cation appropriate. (If the internals are classified as 3.1.1 Vibration Analysis Program non-prototype, the applicant should identify the appli cable prototype reactor internals in the PSAR. Experi The Valid Prototype should be specified and mental or analytical justification for the non-prototype sufficient evidence should be provided to support the classification should be presented during the construc classification Non-Prototype, Category I.

tion permit review.)

The vibration analysis for the Valid Proto

2. A commitment will be established during type, which includes a summary of the anticipated the construction permit review regarding the scope of structural and hydraulic response and test acceptance the comprehensive vibration assessment program. criteria, should be modified to account for the nominal differences that may exist between the Non-Prototype,

3. A description of the vibration measurement Category I, and Valid Prototype reactor internals.

and inspection phases of the comprehensive vibration assessment program will be submitted to the Com 3.1.2 Vibration Measurement Program mission in sufficient time to permit utilization of Commission recommendations. (A 90-day comment and The vibration measurement program may be review period by the staff should be assumed by the omitted if the inspection program is implemented.

applicant for scheduling purposes.)

If a measurement program is implemented in

4. A summary of the vibration analysis pro lieu of an inspection program, sufficient and appropriate gram will be submitted to the Commission a minimum instrumentation should be incorporated to verify that of 60 days prior to submittal of the description of the the vibratory response of the Non-Prototype, Category I,

vibration measurement and inspection programs. (As an reactor internals is consistent with the results of the alternative, the information in this report may be vibration analysis, test acceptance criteria, and the submitted to the Commission in conjunction with the vibratory response observed in the Valid Prototype. The report specified in regulatory position C.2.5.3. In this vibration measurement program should include a case, a 120-day comment and review period for the description of the data acquisition and reduction

1.20-6

systems and test operating conditions consistent with reduction systems and test operating conditions con the general guidelines for the vibration measurement sistent with the general guidelines for the vibration program delineated in regulatory position C.2.2 for measurement program delineated in regulatory position Prototype reactor internals. C.2.2 for Prototype reactor internals.

3.1.3 Inspection Program Sufficient and appropriate instrumentation should be used to define the vibratory response (i.e.,

If an inspection program is implemented in frequency, amplitude, modal content) of those reactor lieu of a vibration measurement program, the guidelines internal components important to safety that have been for the inspection program delineated in regulatory modified relative to the Valid Prototype for the purpose position C.2.3 for Prototype reactor internals should be of demonstrating that the test acceptance criteria are followed. satisfied and establishing the margin of safety.

The inspection program may be omitted if Sufficient and appropriate instrumentation the vibration measurement program is implemented. should be used to monitor those reactor internal However, if significant discrepancies exist between components important to safety that have not been anticipated and measured responses for specific compo modified relative to the Valid Prototype to confirm that nents, those components should be removed from the the vibratory response of such components complies reactor vessel and a visual examination performed. with the guidelines for Non-Prototype, Category II,

Components for which removal is not feasible should be reactor internals and is consistent with the results examined in situ by means of appropriate inspection obtained for similar components during the measure equipment. In any case, the interior of the reactor vessel ment program on the Valid Prototype.

should be visually checked for loose parts and foreign material. 3.2.3 Inspection Program

3.2 Non-Prototype, Category II An inspection program that follows the guidelines for the inspection program delineated in

3.2.1 Vibration Analysis Program regulatory position C.2.3 for Prototype reactor internals should be implemented.

and The Valid Prototype should be specified, and sufficient evidence should be provided to support the classification Non-Prototype, Category II, which 3.3 Non-Prototype, Category HI

requires demonstrating that the structural differences that exist between the Non-Prototype, Category II, 3.3.1 Vibration Analysis Program and Valid Prototype reactor internals have no significant effect on the vibratory response and excitation of those The Conditional Prototype should be unmodified Non-Prototype, Category II, components. specified, and sufficient analytical or experimental evidence should be provided to support the classification The vibration analysis for the Valid Proto Non-Prototype, Category III, as well as to demonstrate type, which includes a summary of the anticipated the applicability of data from the vibration measurement structural and hydraulic response and test acceptance program on the Prototype to the Conditional Prototype.

criteria, should be modified to account for the structural It should be demonstrated that:

differences that exist between the Valid Prototype and Non-Prototype, Category 1I, reactor internals. 1. The Conditional Prototype is sub stantially similar in arrangement, design, size, and Test acceptance criteria should specifically operating conditions to the Non-Prototype, Category III,

be established for those Non-Prototype, Category II, reactor internals.

reactor internal components with structural differences relative to the Valid Prototype. 2. Response modes attributable to the inservice vibration problems and ensuing component or

3.2.2 Vibration Measurement Program operational modifications do not significantly affect the applicability of the results of the vibration measurement A vibration measurement program should be program on the Prototype to the Conditional Prototype, implemented on the Non-Prototype, Category II, reactor or response modes attributable to the inservice vibration internals during preoperational and initial startup problems and ensuing component or operational modifi testing. cations do affect the applicability of the results of the vibration measurement program on the Prototype to the The vibration measurement program should Conditional Prototype, but the effects are limited to include a description of the data acquisition and structural components and response modes that permit

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clear separation of these effects from other results of the regulatory position C.2.3 for Prototype reactor internals vibration measurement program. should be implemented.

Details concerning the adverse vibration 3.4 Non-Prototype, Category IV

experience of the Conditional Prototype should be provided, as should experimental or analytical informa 3.4.1 Vibration Analysis Program tion which demonstrates that the vibration problems associated with the Conditional Prototype have been The Limited Valid Prototype should be corrected for both it and the applicable Non-Prototype, specified, and sufficient evidence should be provided to Category III, reactor internals. support the classification Non-Prototype, Category IV.

The vibration analysis on the Prototype to the Conditional Prototype, which includes a summary of 3.4.2 Vibration Measurement Program the anticipated structural and hydraulic response and test acceptance criteria for the measurement program on A vibration measurement program may be the Prototype, should be modified to account for the omitted if the inspection program is implemented.

component or operational modifications applicable to the Conditional Prototype and Non-Prototype, Category If a measurement program is implemented in III, reactor internals. lieu of an inspection program, sufficient and appropriate instrumentation should be incorporated to verify that the vibratory response of the Non-Prototype, Category Test acceptance criteria, with permissible deviations, should be specified for reactor internal IV, reactor internals is consistent with the results of the components important to safety. Each component vibration analysis, test acceptance criteria, and the should be categorized according to whether the results vibratory response for the referenced limited Valid from the vibration measurement program on the Proto Prototype.

type to the Conditional Prototype are applicable.

The vibration measurement program should

3.3.2 Vibration Measurement Program be consistent with the guidelines delineated in regulatory position C.3.1.2 for the measurement program for A vibration measurement program should be Non-Prototype, Category I, reactor internals.

implemented on the Non-Prototype, Category III,

reactor internals during preoperational and initial startup 3.4.3 Inspection Program testing.

If an inspection program is implemented in lieu of a vibration measurement program, the guidelines Sufficient and appropriate instrumentation for the inspection program delineated in regulatory should be used to define the vibratory response of those position C.3.1.3 for Non-Prototype, Category I, reactor reactor components important to safety which, because of structural or operational modifications relative to the internals should be followed.

original design of the Conditional Prototype, are expected to have response characteristics substantially different from those measured for that component during the vibration measurement program on the

D. IMPLEMENTATION

Prototype to the Conditional Prototype.

The purpose of this section is to provide guidance to All other components should be monitored applicants and licensees regarding the NRC staffs plans with sufficient and appropriate instrumentation to con for utilizing this regulatory guide.

firm that the measured response for each component is substantially similar to that obtained during the vibra Except in those cases in which the applicant proposes tion measurement program on the Prototype to the an acceptable alternative method for complying with Conditional Prototype.

specified portions of the Commission's regulations, the method described herein will be used in the evaluation The vibration measurement program should of submittals for operating license or construction satisfy the general guidelines for a Prototype measure permit applications docketed after June 22, 1976.

ment program as delineated in regulatory position C.2.2.

3.3.3 Inspection Program If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or An inspection program that satisfies the before June 22, 1976, the pertinent portions of the guidelines for the inspection program delineated in application will be evaluated on the basis of this guide.

1.20-8

SPROTOTYPE

[Unique or first of a kind Analysis, Extensive Measurement, and Full Inspection I

JInservice problems resulting in component or Vlid :Proto" prtoa oiiain Conditional

//

CATEGORY I

NON-PROTOTYPE \INON-PROTOTYPE

CATEGORY II CTGR

Similar to ValidPrototype CTG Ill Substantially Similar PROTOTYPEyp tNON

,to Valid-Prototype but omeompoent / /Substantially Similar to differences Conditional Prototype Analysis and Either Analysis, Limited //Analysis, Limited Extensive Measurements Measurements, and .A 1'Measurements, and or Full Inspection Full Inspection M' I. Full Inspection II

Limited Valid Prototype NON-PROTOTYPE

CATEGORCYIV

Similar Substantially Similar to Limited Valdid Prototype Reatocofiuraio ineral fr wiccoprhestn iveySiiart Analysis and Either Extensive Measurements or Full Inspection GIlD Reactor internals configuration for which comprehensive vibration assessment program is defined.

EZZJ Summary of comprehensive vibration assessment programs.

QID

Reactor internals reference design which, together with its test and operating experience, provides the basis for a specific comprehensive vibration assessment program.

Indicates alternative paths


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