ML19308C286

Submits Rept on Nuclear Reactor Insp.Problems Identified in Rept Amenable to Solution.Resolution of Items Should Produce Substantive Improvements in Insp Process

ML19308C286
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Site:	Crane
Issue date:	05/19/1976
From:	Moeller D Advisory Committee on Reactor Safeguards
To:	Rowden M NRC COMMISSION (OCM)
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ML19308C281	List: ML19308C280 ML19308C286
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~~ bq ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR REGULATORY COMMISSION

,a WASHINGTON, D. C. 20555 May 19, 1976 4

Honorable Marcus A. Rowden Chairman U. S. Nuclear Regulatory Comission Washington, DC 20555

SUBJECT:

REPORP ON NUCLEAR REACIOR INSPECTION

Dear Mr. Rowden:

In response to a reguest_ from the Comission in early 1975, the Advisory Comittee on Reactor Safeguards established an Inspection and Enforce-ment Subcomittee to review and coment on the adequacy, scope, and possible redirection of the Nuclear Regulatory Comission's Office of Inspection and Enforcement (NRC-IE). W is action was also in response to recognition of a need for greater attention to these matters as a result of the boiling water reactor (BUR) pipe cracking problem. %e scope of the Subcomittee's evaluation program was directed primarily to those matters pertaining to portions of commercial nuclear power plants covered by the American Society cf Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Sections III and XI. While an attempt was made to develop some information pertaining to fire inspection practice, the depth of the review was somewhat limited.

he Comittee'also had limited opportunity to review inspection and enforce-ment aspects of instrumentation and controls, concrete containments, rotating machinery, heat transfer equipment, and preoperational testing.

A review of these matters was completed by the Comittee during its 193rd meeting, May 6-8, 1976. W e subject was also a matter of discussion with the NRC Staff during the 191st meeting of the Comittee, March 4-6, 1976, and at meetings of the Inspection and Enforcement Subcommittee held in ll Washington, D. C., on August 13, October 1, and Ndvember 21, 1975. Members of the Subcommittee and invited experts visited the pressure vessel facilities 1

of Combustion Engineering, Inc., in Chattanooga, Tennessee, on January 23, s

l 1976, and a Subcomittee meeting was held that same day. A Subcomittee meeting was also held on February 20, 1976, in Chicago, Illinois, to discuss inspection procedures with personnel from Commonwealth Edison Company and Region III NRC-IE. During this review, the Subcomittee had the benefit of discussions with representatives from code groups, insurance companies, electric utilities, nondestructive testing' organizations, the National

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Board of Boiler and Pressure Vessel Inspectors, and of the documents listed.

% e problem of terminology in the inspection and examination of nuclear conponents is recognized as relatively complex. %erefore, the Comit-tee is attaching a glossary of terms used, or directly interacting with s

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Honorable Marcus A. Rowden May 19, 1976 terms cited,'in this report to minimize confusion concerning the meaning

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' intended for specific terms. Most definitions were derived from the ASME

' Boiler and Pressure Vessel Code, but are considered applicable to other areas of concern in electrical conponents, instrumentation, structures, l-and fire prevention. Were should be a clear differentiation between exam-ination and inspection. We Comittee,will use the terminology indicated in the attached glossary, where the_" examiner" conducts the nondestructive or destructive tests whereas the " inspector" is responsible for such items as the validation.of test methods and calibration procedures, qualifica-

' tion of examiners,l monitoring'and/or auditing the tests, and reviewing the: records. While terminology such as testing, checking, etc. is used

.in lieu of examination by.other groups, "exdmination" will be used herein regardless of the conponents considered.

he Comittee recognizes that the National Aeronautics and Space Adminis-

. tration '(NASA) and Federal Aviation Administration (FAA), and various other federal agencies use combined examiner-inspector approaches. However, t

• his type of arrangement is ineffective unless the inspection agency can p.) vide its own examination facilities at the point of inspection.

In tla: case of the nuclear industry, this is impractical because of the need e

to utilize the owner's operating personnel and equipment for the examination program. It is possible for the inspection agency to perform some-types of examination, but these should be primarily confirmatory actions to establish that the examination procedures are appropriate to the need.

In evaluating the requirements for inspection and examination of nuclear facilities, the Comittee considered the' relevance of the practices of NASA,=FAA, and other organizations who have rigorous requirements for environmental testing of components, including extensive life testing under environmental conditions, as a part of their inspection require-

.ments. For short-lived space vehicles and high speed aircraft, where there is no latitude to determine performance adequacy prior to use under i-extreme conditions, stringent gerformance verification is necessary.before 4

operational-use.

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of nuclear power reactors, performance veri-fication is achieved partly by environmental tests, partly.by a series of plant preoperational tests, and partly by clo,sely controlled. tests during low power operation and the period of gradual increase of power t

to the operating level.. B is procedure allows anple opportunity to expose most inadequacies of design or construction.

l An examination of various foreign codes refevant to the. inspection of g

pressure boundary components did not reveal substantive differences ~or potential improvements that could be incorporated into appropriate' i,

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' United States' codes or standards. W e fundamental differences between codes are too great to permit a quantification of the pluses in one code o

versus the minuses in another. Until differences in philosophy can be resolved, there appears to be only limited opportunities for corrbining the best features of'the relevant French, German (Federal Republic of Germany), Japanese, United Kingdom, and United States codes.

An increased effort between the NRC and appropriate code or standards l

groups to develop better criteria and codes or standards comparable to the ASME Nuclear Codes for fire prevention, for electrical systems, and for other safety-related components, is desirable. Current requirements 1I often are ill-defined and amorphous so the '8 inspector" lacks adequate criteria to determine acceptability. U& il these criteria are better defined, there will continue to be conft.lon concerning acceptable limits as evaluated by the NRC-IE organization.

j A well-defined Cuality Assurance (@) Program developed by all responsible parties for design, constr.uction, and operation is essential if there is J

to be a coordinated cnd teaningful inspection program by the hird Party (authorized inspector) and the Fourth Party (NRC-IE). Such a program pro-vides criteria for the evaluation of the relevant components or systems.

An inevitable result of a good m program is the identification of some inadequate quality or erroneous work by an effective inspection and enforcement activity since lack-of-perfection is implicitly indicated by the need for inspection. h e adequacy of workmanship should be evaluated on the basis of frequency of occurrence of unacceptable results and repe-tition of substandard results rather than on the basis of isolated incidents.

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% e principle of in-depth safety protection is predicated on the assumption that even though one or more lines of safety defense may break down, simul-taneous failure of all lines of defense has a sufficiently low probability of occurrence to make its consequences an acceptable safety risk. Coopera-tive efforts leading to an improvement in m such as the activities of the i

S Coordinating Agency for Supplier Evaluation. (CASE) should be encouraged.

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%e Committee recognizes the need to validate @ programs through review f

c of. appropriate documentation. However, inspections should represent a balance between direct inspection of equipment and facilities and review of documents since the best way to assess an organization's attitude is through direct observation during construction or operation of a facility.

With regard to the problem of detection of stress corrosion in piping that initiated this report, its ultimate solution will depend to a major degree on better nondestructive examination techniques and on more clearly l

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Honorable Marcus A. Rowden May 19, 1976

. defined standards for such examinations. The Comittee is aware of the joint ' efforts by industry, the Electric Power Research Institute, the

. Nuclear Regulatory Comission, and the Energy Wsearch and Development Administration to inprove nondestructive examinat.?'n procedures on aus-

.tenitic stainless steel and hopes such efforts will lead to appropriate improvements. With regard to examination procedures, such as those pre-

sented in the American Society for Nondestructive Testing document, SNP-

'IC-1A, modifications are desirable but may need to await the results of experimental programs.

The Comittee believes that the NRC Office of Inspection and Enforce-ment can be more objective if its personnel, while being responsible for inspection, are not responsible for the performance of the examination

. and testing activities. _ It is not necescary to perform the work in order to establish that examination practices are appropriate. The Comittee e

believes that if the NRC-IE organization has a suitable staff of experts in inspection and examination practices and monitors the use of these prac-tices at important installations,.it will provide the most effective inspec-tion program.

Further, conflicts between the NRC Staff and other government-authorized inspectors required by mandatory codes followed in the United States will be avoided. For example, the cases of intergranular stress corrosion cracking (IGSCC) in BWR piping were identified by operating per-i sonnel retained by the licensee and used during routine plant operation.

s It would be totally impractical to obtain comparable timely response under such conditions if the NRC Staff had to perform these examinations and inspections before the safety implications could be evaluated.

It is necessary to recognize that the qualifications of both " inspectors" and " inspection specialists", whether employees of an " authorized inspection agency" or NRC-IE, will vary with the type of inspection.

For example, j

th ! qualifications of an " authorized inspector" on a construction project, i

where ASME,Section III, is applied, will differ markedly from the qualifi-cations of an " inspector" on an pperating nuclear power plant who is required to audit and evaluate by ASME,Section XI. Because this difference is not

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generally recognized, some " inspectors" may lack necessary qualifications.

Intheinspectionofthepressureboundary,wherhASME,SectionsIIIand XI are comprehensive codes with well-defined responsibilities for exami-nation and inspection, it should be possible~to enhance NRC-IE activities by giving ASME more authority'while holding them accountable. A specific s

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suggestion would be to modify Article NA-4000 of ASMS,Section III, to conform more closely to 10 CFR 50, Appendix B, and by requiring an upgrading of the qualifications of.the " authorized inspector" through rigorous appli-a M

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Honorable Marcus A. Ibwden May 19, 1976

'Qaclity Assurance. To a degree, the preceding has been accomplis'hed, but further improvements may be possible and should be explored.

A fertile area for. improving the reliability and scope of inspections is through improved interactions between Wird Party (authorized inspector) and Fourth Party (NRC-IE) Jinspectors and acceptance by Fourth Party of W ird Party inspections,' subject to audit. Each of the levels of inspection and each of the inspection parties would have its capabilities strengthened and its diities better delineated. W e NRC-IE Staff could concentrate its efforts _on making certain that this istthe case so that it can use the results of these inspections as a basis for, safety evaluation.

" Authorized inspectors" employed by inspection agencies, inspectors enployed by the owner-or his agent, and NRC-IE personnel have different levels of capabilities and responsibilities.

'Ib some degree the respon-sibilities overlap and this situation has some advantages as well as disadvantages as applied to the ASME codes. % e situation is less clear with respect to operational inspection, fire prevention, and instrumentation and controls. % e level of expertise available to the several inspection sources is re. fully defined and may be inadequate. % e responsibilities i~

and capabi10.ies of the various inspection organizations need further review and evaluation.

W e enforcement policy of the NRC-IE should be such as to encourage responsible reporting of unsatisfactory conditions of significance to public health and safety. Penalty systems should be directed toward those having responsibility for organizing and implementing inspection and examination functions (e.g., owner-management, architect-engineer (A-E) management when designated under owner-A-E contract, insurance agencies when designated by owner-contract, constructors and suppliers when designated by recognized codes, standards, and regulations or by owner-contract).

r A potential limitation pertinent to both hird Party (authorized inspectors) i and to Fourth Party (NRC-IE) inspection personnel is the inability of a single person to cope with the tremendous detaiI in a code such as ASME,Section III, where familiarity with design, construction, materials, and examination is required. A viable solution is a strong cadre of " inspection specialists"-in both the " authorized inspection agency" and the NRC-IE organization. Such specialists are essential where problems arise that exceed the capabilities of online " inspectors". Competencies among

" authorized inspection agencies" vary with'some being stronger than s

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- others. %e Comittee believes that the NRC-IE organization needs to increase its Staff in this area through direct hires or through increased use of consultants, s

I n e existing level of staffing and capabilities in the NRC-IE organiza-

. tion probably needs to be expanded. %e capabilities of NRC-IE could be used more effectively if some of the duties now performed by its personnel were performed by " inspection agencies" not in the enployment of the NRC. However, regardless of this, there appears to be a definite need for more expertise in the NRC-IE organization to serve as a cadre of supporting personnel when important safety matters arise requiring resolution. Further, the inspection capabilities need to include fire protection, instrumentation and controls, rotating machinery, and various operational test activities as well as matters covered by the ASME Boiler and Pressure Vessel Code.

% e Committee believes that the problems identified above are amenable to solution, and positive programs leading to resolution of these items should produce substantive improvements in the inspection process.

Sincerely yours, M

Dade W. Moeller Chairman.

Attachment:

Glossary of Terms

References:

1.

Ietter, dated February 17, 1976, E. L. Kemmler, % e Hartford Steam Boiler Inspection and Insurance Company, to the Honorable Abraham Ribicoff, s

concerning the inspection of nuclear plaats by insurance conpanies 2.

"NELPIA and MAERP Inspection Guide for Boiler and Machinery Inspection Property Insurance Association," Burt C. Proom, Jtily 1975,. Nuclear Energy Liability Property Insurance Associa' ion and Mutual Atomic Energy t

Reinsurance Pool 3.

American National Standards Institute (ANSI), " Qualifications and Duties for Authorized Nuclear Inspection," ANSI N626.0, 1974 4.

" Qualifications and Duties for Authorized Nuclear Inservice Inspection,"

~ ANSI N626.1, Jtly 2, 1975 5.

" Qualifications and Duties for Authorized Nuclear Inspection (Concrete),"

ANSI N626.2, July 1975 I

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~ Honorable Marcus A. Ibwden May 19, 1976 References 03ntinue _d:

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6.. ~ Technischer Ueberwachungs-Verein Rheinland (TUV), " Requirements for the Design and Execution of a Quality Assurance Program for Nuclear Installations," Report No. 932/7411, July 17, 1975 7.

Intter, dated October 17, 1975, G. E. Weldon to R. Minogue, concerning a national nuclear fire code 8.

" International Guidelines for the Fire Protection of Nuclear Power Plaats," National Nuclear Risks Insurance Pools and Association, 1974 Editions 9.. Joint Hearing

'1he Joint Committee on Atomic Energy of the United States and the Committee on Government'0perations of the U. S. Senate,

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Ninety-fourth Congress, Nuclear Regulatory Commission Action Requiring

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Safety Inspection Nhich Resulted in Shutdown of Certain Nuclear Power Plants, February 1975 j

10. ASME Boiler and Pressure Vessel Code,.Section III - Nuclear Power Plant Components, 1974 Edition

11. ASME Boiler and Pressure Vessel Code,Section XI - Rules for Inservice Inspection of Nuclear Power Plant Components, 1974 Edition

12. Ietter, dated October 27,1 75, Institut Fur Reaktorsicherheit Der Technischen Ueberwachungs - Vereine (IRS-TUV) to Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, Washington (Battelle, Northwest), concerning inspection and enforcement information from Sweden

13. Letter, dated July 11, 1975, IRS-TUV to Battelle, Northwest, concerning inspection and enforcement information from Sweden, ("Wes und Geschichte der 'Ibchnischen Ueberwachungs - Vereine", G. Wiesenack 1971) 14.

Topical Report on Coordinating Agency for Supplier Evaluation, January, 1976 sP q

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- ATTACIMTE 1

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. %e following definihoas.are. those used in AS!E,Section III and ASfE,Section XI; however, @ay are considered to be generally applicable to all

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classes of components, examinations, and inspections.

(Note: "NA-refers - to. AStE,. SectioniIII, "INA -

" refers to ASfE, Section~XI, aEd

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"*" refers to usage by the ' ACRS Inspecti~on and Enforcement Subcomittee) 7 AUDITS - NA-4900 A comprehensive system of planned ~and periodic audits shall be carried out T

by the Certificate of Authorization holder's organization to assure compliance with all-aspects of the Quality _ Assurance Program and to determine the effec-s tiveness of the Program.

AITIUORIZED INSPECTION AGENCY - NA-5111 An Authorized Inspection Agency is one designated as such by the appropriate legal authority of a' State or Municipality of the United States or a Province

'of Canada. _ %e agency employs the Authorized Inspectors who perform inspec-tions required by this Section. We agency may be a State of the United States or a Province of Canada or an insurance company authorized to write

-boiler and pressure vessel insurance.

CERTIFICATE OF AUIHORIZATION - NA-8112

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An _ Owner, hgineering Organization, Manufacturer, or Installer may apply to the American Society of Mechanical mgineers, upon forms issued by the Soci -

ety, for a Certificate of Authorization for the scope of work which he intends to perform.

CIASSES - CODE *

. Construction rules are specified for items which are designated Code Classes 1, 2, 3, CS and MC. %ese code classes recognize the different levels of importance associated with the function of each item as related to the safe x

i operation of.the nuclear power plant. Ebr exampl6, Class 1 includes, but 3

~is not limited to, components making up the primary coolant boundary.

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= nents -(e.g.,~ pressure vessels) contained in the laws of States, Municipal-

~ities, Federal Governmeat, etc. %e' AStE Boiler 'and Pressure Vessel Codes arela_ specific example. Wey are mandato,ry..

v CODE - ASME III - NA-ll10 he. rules'of this section constitute requirements for the constrmtion of

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' nuclear power plant items-such as. vessels, storage tanks, piping, p eps,

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valves, and core. support structures, and component supports, for use in 1

or containment of, portions of the nuclear ~ power system of any power plant.

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CODE - ASME XI - INTRODUCTION / FOREWORD Section XI,- Rules for Inservice Inspection of Nuclear Power Plant Compo-nents of the ASE Boiler and Pressure Vessel Code is addressed to provide rules for the examination, testing, and inspection of Class 1, 2, and 3 components and systems in a nuclear power plant. Application of this Sec-

. tion of the Code begins when the requirements of Section III, Rules for Construction of Nuclear P>wer Plant Components, have been satisfied.

CONsTxu(TION - NA-ll10 FOOItDfE Construction is an all-inclusive term comprising materials, design, fabri-

. cation, examination, testing, inspection, and certification required in the manufacture and installation of items.

= ENFORCEENT AUTHORITY - IWA-2110(e)

Denotes s regional or local governing body such as a State or Municipality of the United States or Canadian Province empowered to enact and enforce boiler code legislation.

EXAMINATION - IWA-2110(a)

Denotes the performance of all visual observation and nondestructive testing such as radiography, ultrasonic, liquid penetrant, and magnetic particle methods.

EXAMINATION TECHNIQUES - IWA-2200 Methods, techniques, and procedures for the inservice inspections are titled visual, surface, and volumetric. Each term describes a general method permitting a selection of different techniques or procedures restricted to that method to accommodate varying pegrees of accessibility and radiation levels,.and the automation of equipment to perform the 4

s examinations.

EXAMINER - IWA-2110(a)

'Ihe individual (s) performing all visual observation and nondestructive testing such as radiography, ultrasonic, liquid penetrant, and magnetic particle methods.

EXAMINER - QUALIFICATIONS - IMA-2300 a)

Personnel performing nondestructive examination operations shall c

be qualified with a procedure prepared in accordance with

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SNIMC-1A for the applicable examination technique and methods.

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For nondestructive examination methods not covered by SNT 'IC-1A docu-ments, persdnnel shall be qualified by the Owner or his agent to compar-able levels of competency by subjection to comparable examinations on the particular methods involved; for example, leak testing., % e practical portion of SNP-TC-1A shall be performed using the Owner's procedure (s) on part(s) representative of the Owner's plant.

FUW INDICATION -IWA-2110(c)

Denotes the evidence or signal obtained by application of a nondestructive exanination that may reveal the presence of a flaw. Flaw indications include cracks, slag inclusions or segregates, aligned or clustered poros-ity,' lack of weld penetration, lack of weld fusion, and laminations or combinations thereof.

INSPECTION - IWA-2110(b) 1 Denotes verifying the performance of examinations by an Inspector ~ represent-ing a State, or Municipality of the United States, Canadian Province, Author-ized Inspection Agency, or other enforcement authorities having jurisdiction over the nuclear power components at the plant site.

INSPECTION AGP1CIES - NA-3520 Organizations to ' 3 agreements with Owners, Digineering Organizations, Manu-facturers or Installers to provide inspection of nuclear power plant items or their installation.

OFFICE OF INSPECTION AND ENFORCEMENI*

We office under the Nuclear llegulatory Commission responsible for inspection of nuclear facilities (see Begulatory authority).,

x' INSPECTION - FIRST PARTY (09NERS)*

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Denotes verifying the performance of examinations by an inspecto'r who represents, and is employed by, the owner of the facility.

INSPECTIdN - SECOND PARTY (MANUFAC'IURERS)*

Denotes verifying the per,formance of examinations by an inspector who represents, t

.and is employed by, the manufacturer.

INSPECTION - THIRD PAITY*

..s Denotes verifying the performance of examinations by an inspector as defined in IWA-2130.

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. INSPECTION - FOURTH PARTY (NRC-IP)*

Denotes verifying the performance of examinations by an employee of the Nuclear Regulatory Commission's Office of Inspection and Enforcement as distinguished from an Authorized Inspector.

INSPECTION SPECIALISTS - NA-5113 Any Inspection Agency which has contracted to perform inspections required by this Section shall, in addition to Inspectors, maintain a staff of Inspection Specialists, each of whom has demonstrated his qualification by passing an examination acceptable to the Society in one or more methods of nondestructive examination and, in addition, the tests for Inspection Specialists given by the National Board of Boiler and Pressure Vessel Inspectors for knowledge of and familiar-ity with this Section.

INSPECTOR - INA-2110(d)

Denotes an " Authorized Inspector" as defined in IWA-2130.

INSPECTOR - DUTIES (INSERVICE) - INA-2120 a)

It is the duty of the Inspector to witness or otherwise verify all the examinations and pressure tests required by this Divi-sion for Class 1, and for Class 2 components where required.

W e Inspector shall also make any additional investigations necessary to verify that all applicable requirements have been met.

. b)

It is the duty of the Inspector to assure himself that the nondestructive examination methods used follow the techniques specified in this Division. W e Inspector shall also assure himself that the examinations are performed in accordance with written qualified procedures and by pergpnnel employed 1

by the owner or his agent and qualified in accordance with SNP-IC-1A and INA-2300. The duties of the Inspector include checking with his Inspection Specialists fo the technical contentandrequirementsoftheexamination('proceduresand' the qualification procedures of nondestructive examination personnel.

c)

It is the duty of the Inspector to assure himself that the

. inservice tests required on punps and valves (INP and IWV) 7 have been coupleted ~and the results recorded.

d) -It is the duty of the Inspector to assure himself that the

. examinations and tests required for Class 3 components s

1-and systems (IWD-1000) have been conducted and the results recorded.

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e) he Inspector has the right at any time to require requalification of any procedure or operator G n the Inspector has reason to believe the-requirements are not being met.

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% e examination records shall be certified by the Inspector only after he has satisfied himself that all the requirements have been met and that the records are correct.

g) h e Inspector shall review the repair program to determine com-pliance with the requirements of this Division.

h)

It is the duty of the Inspector to assure himself that the welding procedures employed during the repair ahd the welding operators are qualified in accordance with IWA-4000 and that a 7onde-structive examination methods used comply with requic..ents in IWA-2200 and IWA-2300.

INSPECIOR - DUTIES (CONSTRUCTION) NA-5210 a)

% e Inspector who performs the detailed inspections in compliance with this section shall witness or otherwise verify all examina-tions and make all inspections required by this Section. He shall also make any other inspections and witness or verify

-(including making measurements) any other examinations and addi-tional investigations which, in his judgment, are necessary to ascertain whether the item being inspected has been constructed (NA-ll10, Ebotnote 1) in compliance with the rules of this Sec-tion. Parts and piping subassemblies shall be in accordance

.with the accepted design drawings.

b)

We duties of the Inspector shall not be interpreted by virtue of these rules to extend to any construction requirements beyond those of this Section which may be set forth in the Design Specification or on drawings. Howevet, such require-ments shall not result in construction which fails to conform with the requirements of this Section (NA-3252).

1 INSPECIOR - THIRD PAR 1Y (AUTHORIZED) - IWA-2110(d)

Denotes 'an " Authorized Inspector" as defined in IWA-2130.

INSPECIOR - QUALIFICATIONS - IWA-2130(b)

Any. Inspector who performs inspections required by this Division shall have first been qualified by written examination pursuant to the legis-lation or rules of a State of the United States, the legislation of a e

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over a nuclear power plant at the installation location and that has adopted this Division. %e Inspector shall not be an employee of the Owner or his agent.

JURISDICTIONAL AUIHORITY*

hat body in the State _ empowered by its legislature to enforce the laws of the State with respect to boilers, pressure vessels, and nuclear reactors. We title of the Chief Diforcement Officer is usually Chief Inspector.

e MANUFACTURER - NA-3310 he organization or combination of organizationc which constructs (NA-ll10) any item to meet the Design Specifications and the requirements of the Code.

OPERATION

• Denotes status of a nuclear power system during the power generation (and ascent to power) stages.

OMER - IWA-1400 EtXmCfE

. W e organization responsible for the operation, maintenance, safety, and power generation of the nuclear power system.

QUALITY ASSURANCE - NA-4121 All those planned and systematic actions necessary to provide adequate confidence that all items manufactured or installed are in accordance with the rules of this Section.

Quality Assurance includes:

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Quality Control Examination (NA-4122), which comprises the exami-

. nations of the physical characteristics of a material, components, part, or appurtenance and the acceptance standards associated with those examinations;

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'2) - Quality Oontrol Administration (NA-4123), which is the management and documentation which assures that the specified Quality Control examination is carried out.

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7-P2GUIRIORY AUniORITY - INA-2110(f)

Denotes'a Federal Government agency, such as the United States Nuclear Ibgulatory Comission, empowered to issue and enforce regulations con-

. cerning the design, construction, and operation of nuclear power plants.

STANIMRDS*

'1 hose test methods, definitions, recomended practices, classifications, specifications, and other related material representing a ccamon viewpoint to those parties concerned (producers, users, general interest groups).

Lblike codes,-standards are voluntary.

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~ PRODUCTS OF:"IE STUDY" Greher X0MA 7/19/

~IE MISSION AND STRATEGIES

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NRC Manual. Chapter-0127, "Orgartization and Functions, 0ffice of-

' Inspection -and Enforcement" IE study group 2/23/78 (a study product)

.2.

"The NRC Program of Inspection-and Enforcement" Nuclear Safety vol 19-6 Nov-Dec 1978,'IE study group (a study byproduct) 3.

" Discussion paper on IE~ construction program role for achieving "public hialth and safety" IE study group 1977 (s study product)

-w VENDOR INSPECTION

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SECY-77-64, " Licensee Contractor and Vendor Inspection Progrs="

RCI Div 2/2/77 (not a study product, more like a study precursor)

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NUPI6/CR-0217. Report ' of a' Study of the Licensee' Contractor and Vendor Inspection Program (LCVIP)" TRW.Inc. 5/78

_ (a study. product)

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.SECY-78-495

" Letter to OMB concerning the NRC's Licensee Cont.ractor-and vendor Inspection Qfgram" RCI Division.

9/S/78 (A study Product)

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- RESIDENT INSPECTION 7.

SECY-77-133 " Resident Inspectica Trial Program" ROI Div. 1/2S/77 (not. a study product, more like a study precursor)

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NUPIG-0425 "NRC Inspection Alternatives, a Study Report" IE study group 4/77 (a study product) 9.

hTREG-0397 " Revised Inspection Program for Nuclear Power Plants" IE

' study group 1/78 (a study product) 10.- " Observations in regard to the NRC Resident Inspection Progra "

J. W.. Flora, consultant 9/19/77 (an independent look at a study module' product) 11.

" Program Plan, Resident _ Inspection Program" IE study group 6/77 ( a

~ study' product) i DI:ICTJINSPECTION:

' Independent NRC Measurements and Analysis" ROI Div. 1/6/7S (a-study 10.

. p'roduct) 13.

" Independent Nondestructive Exanination' Study" RCI Div 7/1/78 (a ctudy; product)'

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. i INCENTIVE SYSTEM 14

" Analysis and application of Incentive Systems for the U.S. Nuclear Regulatory Commission" Presearch, Inc. 12/6/78 (A study product) 15.

"NRC Enforcement Initiatives" IE Study Group 11/30/77 (a study product) 16.

" Phase'I report, Utility of Incentive Systems for Licensees" TEW Inc.

10/77 (a study product) 17.

NUREG/CR-0387 "A Study of Incentive Systems for Nuclear Licensees" TRW Inc. 8/78 (a study product)

OTHER AGENCY PROGRAMS-18.

NUREG/CR-0200 " Study of Nuclear Regulatory Commission Inspection Enforcement Regional Offices Interaction with Other Agencies" General Research Corp.

11/11/77 (a study product) 19.

NUREG/CR-0051 (Volumes 1 & 2 ) " Evaluation of Inspection and Enforcement Programs of other Regulatory, Safety, and Professional Organizations -

Phase I" Teknekron, Inc. 9/77 (a study product) 20.

NUREG/CR-0052 " Evaluation of Inspection and Enforcement Programs of Other Regulatory, Safety, and Professional Organizations - Phase II" Teknekron, Inc. 2/78 (a study product)

LICENSEE PERFORMANCE EVALUATION 21.

" Draft Report - Licensee Inspection and Enforcement Indicators" and " Update" M. Howard 9/26 and 10/26/77 respectively (a study product) 22.

" Safeguard Performance Evaluation Final Repcrt - Security at Power Reactors" Reg. III Safeguards BR 2/22/77 (not a study product, more like a study precursor) 23.

" Individual Site Ratings from the IE Employee Survey on Evaluation of Licensees" IE Study Group and Hay Associates 4/78 (a study product) 24.

" Licensee Performance Evaluation Phase I Report" Teknekron, Inc. 5/78 (a study product) 25.

SECY-7E-554 " Licensee Regulatory Performance Evaluation" F ' Div.

10/25/78 (a study product)

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APPLICATION OF WASH-1400 26.

NUPIG/CR-0153 " Insights into Improving the Efficacy of Nuclear Power Plant Inspection Procedures Based Upon Risk Analysis" Battelle Labs 5/78 (a RES -funded report) 27.

Work Statement of Contract with Sandia for applying WASH-1400 to IE Inspection Modules. Sandia Corp.

APPLY STATISTICAL SAMPLING 28.

" Benefit, Cost Analysis of the Trial Program Involving Statistical Sampling Inspection Techniques" ROI Div. 1/14/77 (a study product)

MEASUPIS OF IE EFFECTIVENESS No Products Produced e