Regulatory Guide 1.20

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)

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

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

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.

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