ML19269F029
| ML19269F029 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1978 |
| From: | NRC/IE |
| To: | |
| References | |
| NUREG-0397, NUDOCS 7911140467 | |
| Download: ML19269F029 (28) | |
Text
NUREG-0397 REVISED INSPECTION PROGRAM FOR NUCLEAR POWER PLANTS 2200 303 p* "*%,,
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Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 99g1140 Ub7
Available from National Technical Information Service Springfield, Virginia E2161 Price: Printed Copy $4.50; Microfiche $3.00 The price of this document for requesters outside of the North American Continent can be obtained from th9 National Technical Information Service.
2200 504
NUREG-0397 REVISED INSPECTION PROGRAM FOR NUCLEAR POWER PLANTS 2200 305 Manuscript Completed: January 1978 Date Published: March 1978 Office of Inspection and Enforcement U. S. Nuclear Regulatory Comrnission Washingtco, D. C. 20555
CONTENTS I.
Introduction.
1 II.
The Basis for the NRC Reactor Inspection Program..
2 III.
The Current flRC Inspection Program......
..6 IV. The Revised Inspection Program.
9 V.
Utilization of the Inspection Force 13 VI.
Career Development and Training
.........17 VII.
Summary 24 2200 006
U. S. Nuclear Regulatory Commission Revised Inspection Program for Nuclear Power Planti I.
Introduction The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC ful-fills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection.
The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco.
Inspectors travel from the regional offices to nuclear power pinnts in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include station-ing inspectors at selected plants under construction and at all plants in operation.
In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress.
The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals.
This report vas requested in the Conference Report on the NRC I
Authorization..for Aopropriations for Fiscal Year 1978. The report provides a discussion of the baeis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized.
In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors.
I Senate Report, No.95-788.
c c
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II. The Basis for the NRC Reactor Inspection Program The primary safety consideration in the operation of any nuclear reactor is +he control and containment of radioactive material under both normal and accident conditions. Many controls are established to protect workers and the public from the effects of radiation.
The industry and the NRC both have roles in providing these controls and in ensuring that they are maintained. The NRC establishes rules, regulations and guides for the construction and operation of nuclear facilities. Organizations licensed by the NRC must abide by these regu-lations and are directly responsible for designing, constructing, testing and operating their facilities in a safe manner. The NRC, through its licensing and inspection programs, provides assurance that its licensees are fulfilling their responsibilities.
The underlying philosophy of the design of nuclear power facilities and the NRC regulation of them is the defense-in-depth concept.
Defense-in-depth provides three primary levels of protection.
First, the plant is designed to prevent accidents through intrinsic features, quality components, good construction, redundant systems and redundant controls.
Systems that control the reactor are designed to automatically re/ert to safe state during adverse conditions.
That is, they possess " fail-safe" qualities.
The second level consists of safety systems that protect plant workers and the public by preventing incidents or minimizing damage should incidents occur. The third level of safety consists of additional safety systems to accommodate severe hypothetical accidents that involve independent failure of the redundant protective systems at the same time as the failures which led to the accident.
In the safety design of nuclear plants, the objective is to achieve component design at each protection level and for each physical barrier provided to prevent the release of radioactivity. Although extensive efforts are made to obtain high quality, perfection can never by achieved because of 2200 308 the norma! deficiencies in all processes involving men and materials.
The realization that deficiencies will occur has led to the use of the defense-in-depth concept.
As an illustration:
The approacn of an accident condition is usually signaled by indicators such as unusua. temperature and pressure. Automatic and manually initiated actions are keyed to respond to such signals to avoid the accident.
Fo example, the reactor is immediately shutdown upon receiving such signals.
Multiple barriers are provided to pruent the release of large quantities of radioactivity from a reactor as a result of an accident. Signals are monitored by instruments and operators so that preventive actions can be taken upon breaching the first barrier.
Where a coolant is needed to mitigate an accident, pumps, valves and power supplies are available to provide the necessary coolant even if many components fail to function.
The NRC safety review prior to issuance of a construction permit determines that the defense-in-depth concept has been implemented in the basic design of a reactor. NRC regulation assures that the detailed design, construction and operation of the reactor meet regulatory require-ments and applicable standards and incorporate appropriate quality.
Because of defense-in-depth, nuclear reactors do not require perfect performance and perfect quality for the protection of the health and safety of the public.
2200 309 NRC requires the licensee and each of its contractors to have effective quality-assurance programs.
For a reactor, there are many different companies working on safety-related systems.
The quality-assurance (QA) organization of each company could number from a few to many QA inspectors. The licensee's QA organization must ensure, through direct observation and audits, that all contractors are meeting their obligations. The QA programs are not equally applied throughout the total plant.
Rather, the more important a system or component is to safety, the more rigorous the effort toward quality.
The NRC inspection program is aimed at determining how well this combination of QA programs, those of the licensee and contractors, is working. NRC inspections are made of the licensee and of each contractor performing safety-related work.
NRC concentrates primarily on those licensee and contractor efforts associated with systems having direct safety significance. NRC inspections include a thorough review of each QA organization, QA procedures, review of work control procedures, obser-vation of work in progress and a review of the records of work accomplished.
NRC also reviews the qualifications and training of the work force.
The structured quality-assurance approach for the inspection of nuclear power plants has been designed to provide for multiple levels of inspection and verification by NRC, the licensee and licensee contractors.
The nuclear inspection activity is pyramided, with each level of activity verified, inspected or audited by those above.
The NRC inspection effort is essentially the apex of this pyramid of inspections and audits.
It is the last in a series of inspections performed by many different groups.
The NRC examination is to detendne that the licensee and contractor QA programs are properly implemented.
It is not aimed at accepting " hardware" for the licensee.
By this technique, a relatively small verification sampling by the NRC can provide significant insights into the performance of the licensee and contractor QA programs in assuring the quality of the nuclear power plant.
2200 s10 If the licensee's quality-assurance program is not performing properly, NRC takes enforcement action to correct the situation.
In this way, attention is focused not only on correcting problems identified in the limited NRC inspection but also on correcting the licensee and/or contractor program deficiencies which allowed the problems to go unde-tected or inadequately corrected.
Therefore, with a relatively modest inspection staff, NRC is able to rely on the defense-in-depth concept coupled with broad-based inspection to provide adequate protection of the public.
In summary, NRC implements the defense-in-depth concept in recogni-tion of the unattainability of perfection.
NRC reduces the probability of error by requiring that licensees and their contractors have effective quality-assurance programs.
NRC regularly inspects these QA programs and takes appropriate enforcement action to promptly correct deficiencies.
2200.11 t i, m
III. The Current f4RC Inspection Program Inspections are performed on power reactors under construction, in test and in operation. Currently, the program is conducted from the five regional offices by two categories of flRC inspectors, generalists and specialists.
The generalists, sometimes called principal inspectors, have overall responsibility for one plant, although they also assist in inspect-ing other plants.
Generalist inspectors often oossess specific technical expertise. Special'.ats are experts in specific technical disciplines, such as health physics, physical security or heavy construction techniques, and they conduct inspections in these specialized areas in support of the more general inspections.
Inspections are part of flRC's review of applications for licenses as well as f1RC's issuance of construction permits and operating licenses.
Inspections continue throughout the operating life of a nuclear facility.
Prior to construction, the inspection program concentrates on the applicant's establishment and implementation of a quality-assurance program.
Inspections cover quality-assurance activities related to design, procurement and the plans for fabrication and construction. An acceptable inspection finding is a prerequisite for f1RC's acceptance of an application by a poten-tial licensee. Af ter an application has been accepted for review, inspections continue and acceptable inspection findings are an important part of the f4RC's decision to issue a construction permit.
During construction, a sampling of licensee activities is inspected to make sure that the requirements of the construction permit are followed and that the plant is built according to design and applicable codes and standards. Construction inspections look for qualified personnel, quality material, conformance to approved design and for a well-formulated and satisfactorily implemented quality-assurance program, since these factors are most important to the successful construction of a nuclear plant. The licensee's implementation of these elements is assessed by examination, on a spot check basis, of construction activities.
2200 312 As construction nears completion, preoperational testing to demonstrate the operational readiness of the plant and its staff begins.
Inspections during this phase determine whether the licensee has developed adequate test plans, assure that tests are consistent with NRC requirements and determine that the plant and its staff are prepered for safe operation.
Inspections during the preoperational phase inv)lve (1) reviewing overall test management procedures; (2) examining selecWd test procedures for tchnical adequacy; and (3) witnessing and reviewing selected tests to determine their outcomes and the consistency of planned and actual tests.
In addition, inspectors review the qualifications of operating personnel and assure that operating procedures and quality-assurance plans are developed and implemented.
About six months before the operating license is issued, a startup phase begins in preparation for fuel loading and power ascension.
Following the issuance of an operating license, fuel ;s loaded into the reactor and the actual startup test program begins. As in preoperational testing, NRC inspection emphasis is placed on test management procedures and results.
The licensee's management system for startup testing is examined, test procedures are analyzed, tests are witnessed and licensee evaluations of tests results are reviewed.
Inspectors also independently evaluate licensee activities.
When startup testing is completed satisfactorily, routine operations begin.
Thereafter, NRC continues its inspection program throughout the operating life of the plant to verify that the licensee's control systems assure the safe operation of the plant in compliance with NRC requirements.
Specific elements of the operating reactor inspection program are:
Review of the basic systems and procedures the licensee follows to be certain they conform with requirements are technical jy sound and are implemented properly.
Analysis of records of licensae operation and interviews e."
personnel to confirm that actions called for by the prescribed systems and procedures are routinely followed.
2200 313 Periodic verification of licensee and system performance by means of independent NRC observation, tests or measurements.
In addition to the inspection of nuclear power reactor licensees, the Dallas Regional Office also conducts a program to inspect contractors and vendors who provide services and components to the nuclear industry.
This program, the Licensee Contractor and Vendor Inspection Program (LCVIP) is directed toward assuring that services and products of licensee contractors and vendors are controlled by good quality-assurance programs.
This assurance is achieved through direct NRC field inspection and investigation of these programs and corrective action is taken when necessary.
Regular inspections of nuclear steam system suppliers, architect engineers, fuel fabricators and major manufacturers of components are con-ducted.
Firms are selected for inspection based on the significance of the product to plant safety and the manufacturer's volume of active nuclear bisi n ess.
Inspectors examine hardware, review documents and interview personnel to ensure that detailed control procedures have been prepared and are being followed. These inspections do not relieve licensees of any responsibility for accepting individual components but, as mentioned above, are intended to verify that contractors and vendors have good quality-assurance systems.
In addition to the regular or preventive inspections, investigations are conducted under the LCVIP as a result of allegations, inspection reports or licensee reports the.aC receives.
Data obtained about problems experienced in operating plants is fed back into the LCVIP to minimize repetitions and correct generic problems which may be undetected in other plants.
2200 3M
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IV. The Revised Inspection Program In June 1977, the Commission approved a revised inspection program that includes stationing NRC inspectors onsite at all nuclear power reactors in operation and at selected reactors under construction.
In addition to resident inspectors, the revised program includes:
A national performance appraisal capability that provides three elements:
(1) evaluation of the performance of NRC licensees from a national perspective; (2) an evaluation of the effectiveness of the NRC inspection program; and (3) confirmation of the objecti-vity of NRC inspectors.
A significant extension of direct verification of licensee activities by NRC inspectors that involves more direct measurement and increased observation of operations and tests in progress.
An enhanced career management program that includes 1 proved training and establishes clear career progressions.
(The career management program is discussed in Section VI.)
This revised inspection program afford; a balanced examination of licensee activities that contribute to safety, safe,;uards and environmental protection. The resident inspectors will be similar to the generalists (or principal inspectors) in the current program and they will conduct general inspections over a broad area ranging from activities of the reactor operators to the health ohysics and physical sectrity programs.
However, in-depth technical inspections will be conducted by specialists who will continue to be assigned in the regional offices.
The existing NRCuinspection program provides an adequate technical basis upon which to assure the safety of licensee operations.
- However, there are areas which can be improved.
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",, e 2200 315 Criticisms of the existing inspectior. program follow four ccnsistent themes:
(1) there are too few NRC inspections; (2) inspectors spend too little time actually at the plant; (3) even when cnsite, inspectors spend too much time reviewing paperwork as opposed to observing actual work or observing and conducting tests and measurements; and (4) there is not enough licensee performance evaluation with appropriate NRC response.
A decided move by NRC into more direct verification / measurements and refin-ing the program to provide more onsite time enhances the base for NRC technical judgments and, at the same time, effectively responds to those criticisms.
By assigning resident inspectors to reactor sites, the amount of time they spend at the,.lant will improve by a factor of about three.
This in-creased time will provide greater opportunity to observe and measure licensee activities, verify licensee compliance, and respond to significant events.
Furthermore, because each resident inspector will be assigned to only one site and will, therefore, have improved knowledge of that plant, inspectors should be able to provide better technical judgments concerning that plant and improve the efficiency of inspections. Although there is no way to either forecast or directly measure the results, increased NRC atter,;. ion should contribute to prevention of safety-related problems.
In essence, these revisions to the program will:
Increase NRC knowledge of the conditions at a licensed facility and provide a better technical base for regulatory action.
Lessen the progams reliance on the accuracy and completeness of licensee records by improving the inspector's ability to inde-pendently verify licensee performance.
Provide additional assurance that licensee management-control systems are effective and that licensee performance is acceptable.
2200 316 Of particular concern to the NRC is assuring the continued objecti-vity of inspectors. Working on a daily basis among licensee personnel could result in psychological capture and loss of objectivity. A two-year trail nrogram, in which two inspectors were stationed near several different plants, did not indicate any loss of objectivity on the part of inspectors.
Nevertheless, NRC has included a number of measures in the revised program that are directed toward minimizing loss of objectivity.
These include:
Selection of mature, experienced inspectors.
Additional technical training and reinforcement of the NRC Code of Conduct.
Frequent resident inspector contact with regicnal supervisors.
Limited tours of duty at a particular site.
Frequent visits by inspectors based in the regional offices to perform in-depth technical inspections.
Performance appraisal by still other inspectors to confirm objectivity and uniformity.
This last item is an important element of the revised inspection program.
In addition to checking the performance of resident inspectors, it will, on a national basis, appraise the safety performance of the utilities that operate nuclear power plants.
Performance appraisal,,111 involve assessment teams which make in-depth measurements of various aspects of reactor construction and operation. The teams will analyze inspection and licensee reports to identify potential weak spots and correct developing problems before they present a threat to the public. The performance appraisal teams will also independently evaluate the effectiveness of the inspection 2200 317 inspection program (including the effectiveness and objectivity of the resident inspectors).
Periodic critical reviews of selected areas of licensees activity will provide insight into the performance of the regional inspection program and the resident inspectors.
As the new program develops, the NRC will perform an increasing number of independent confirmatory tests and measurements at the licensee's site. While NRC has performed some radiological measurements since the early 1970's, an increase in other areas, such as nondestructive examination (radiography, ultrasonic testing, etc.) and instrument calibration is included in the revised program. The purpose of these measurements will be to gain greater confidence that the licensee's quality-assurance system is performing properly.
That is, the licensee will remain responsible for accomplishing tests and examinations of all elements of the nuclear plant, but NRC will increase its number of independent tests in order to be sure that the licensee is performing properly.
Moreover, there is more information to be gained about the effective-ness of management controls through observation of an operation or a test in progress than by solely examining records of operations and tests.
- Thus, resident inspectors will be particularly valuable in increasing observation of preoperational tests, power ascension tests, surveillance tests, routine maintenance and operations.
In summary, the revised reactor inspection program preserves the NRC philosophy that the licensee is primarily responsible for all safety, safeguards and environmental measures necessary to protect the public and the environment. The NRC role is to determine how well the licensee is performing and to correct nonperformance whenever found. The combination of resident, regional-specialist, performance appraisal and vendor inspectors will provide an improved base for making these determinations.
2200 318 V.
Utilitation of the Inspection Force The resident and performance f.ppraisal functions w1i! be developed and added to the existing regional and vendor inspection programs uver the next five years (Fiscal Years 1978-1982). Since the assignment cf inspactors onsite requires the greatest application of manpower, it is the coCrolling factor in achieving full implementation. Recruitment and training lead tim "e necessary to augment the inspection force since only experienced inspectors are considered qualified for both resident and performance appraisal positions.
Upon appioval of the supplemental appropriation for FY 1978, imple-mentation will t,egin promptly with the assignment of twenty onsite inspectors.
In FY 1979, forty-five inspectors will be stationed on site. Full implementa-tion, involving an insp?ctor at all operating sites and at selected construction sites wi'1 be achieved during FY 1981. More tt.an one inspector will be stationed at sites with multiple reactors in different phases of construction and opcration or at sites with more than two reactors in a single phase. As mentioned previously, NRC will maintain a balanced program of inspection that involves not only onsite inspectors but also inspectors based in the regional offices who will be, for the most part, specialists. These inspectors will continue to perform a full inspectinn program at sites without resident inspectors and will provide specialized technical support to those sites with resident inspectors.
Formalized efforts to improve evaluation of the NRC inspectico program, to analyze licensee performance from a national perspective, and to ensure inspection program uniformity and inspector objectivity will recei e con-tinuing management emphasis. These performance appraisal efforts will begin in FY 1978 and are expected to be in routine operation during FY 1980.
The implem~1tation of the revised program also requires detailed plans for: selection of sites and resident inspectors; program modifications related to the duties of resident and performance appraisal inspectors; and logistic support.
2200 319 m
tl Site Selection and Manning.
The first 20 sites to receive resident inspectors were chosen to assure:
The involvement of all five regions.
A mix of facilities to cover all reactor phases, construction, te ; ting and operations.
A mi.x of sites that reflect different inspection experience with reactor licensees.
The proper workload for each resident inspector to build an experience base as rapidly as possible.
A mix of reactor types.
Table I lists the number of resident reactor sites by phase in each of the regional offices. Table II shows the reactor sites by name in each region. NRC will assign resident inspectors to these sites during Fiscal Year 1978.
Resident inspectors were selected for these sites based on the site requirements, the experience and maturity of the inspectors and their desires. Movement to the sites will occur during the spring and summer of 1978 and must be completed by September 30, 1978.
Resident inspector duties and r esponribilities have been developed and included in the inspection program. The method of reporting the results of inspections conducted by the resident inspectors is presently being developed and tested.
No change in regional organization or enforcement procedures is seen for the early implementation of the revised program.
Reactor licensees will furnish only office space to resident inspectors.
The NRC will provide all other support. Modifications to the Code of Federal Regulations have been proposed to provide a firmer legal base for office 2200 20 space and inspector access to licersee sites. All other significant logistical questions associated w.th moving inspectors onsite have been resolved.
2200 321 TABLE 1 Rr.sident Reactor Sites (By Phase, Fiscal Year 1978)
Region Operations or Testing Phase Construction Phase Total s
Philadelphia 4
1 5
Atlanta 5
1 6
Chicago 3
1 4
Dallas 1
I 2
San Francisco 2
1 3
Total 15 5
20 TABLE II Resident Reactor Sites by Region (Fiscal Year 1978)
I II III IV V
Philadelphia Atlanta Chicago Dallas San Francisco Millstone Pt.
Browns Fcery D. C. Cook Arkansas San Onofre Salem North Anna Midland Comanche Peak Trojan Indian Point Surry Zion Diablo Canyon Peach Bottom Oconee Dresden Hope Creek Hatch Watts Bar 2200
.322
- 1 7-VI.
Career _ Development and Traini".g The assignment of inspectors to nuclear facility sites imposes a requirement for greater mobility within the inspection force. A resource management system is being developed to provide improved ways of planning, budgeting and measuring the expenditure of resources as well as measuring progress in meeting office goals.
This system and an improved manpower management system will be keyed to the NRC's Five-Year Plan.
The manpower system will provide detailed guidance for recruitment, assignment of personnel and training requirements.
As part of this system, a comprehensive career plan will provide guidance for the professional development of employees and will describe career opportunities for both horizontal and vertical career progression.
Career development and progression implies a need for i creasing the skill of personnel through on-the-job experience and formal training.
NRC has a good training program for the inspection force which is being expanded to meet the needs of the revised inspection program. Training for the revised program must provide a.1 appropriate balance between formal class-room instruction and on-the-job training for every newly hired inspector.
In addition, members of the current inspection force who will be located onsite or selected for the performance appraisal teams may need additional training for specific technical skills and a broadened awareness of the philosophy, policies and operation of the revised program.
Inspector training is accomplished by NRC instructors and contractors.
This training provides a means to assure that new employees are trained in an effective ma'nner and can, as early as possible, perform as fully qualified ss NRC inspectors. Training is also given to current employees in order to
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keep them abreast c new technological developments, new NRC and government regulations and new office requirements and policies.
Thus, training is a prime component of each professional's career development.
2200 23 The enlarged inspector training program that is being developed to accommodate the needs of the revised inspection program consists of a rigorous, carefully planned and balanced program emphasizing classroom training specifically designed to meet NRC needs.
The classroom training is supplemented by realistic training sessic s in a power reactor simulator and by programmed self-study and on-the-job training.
Table III lists the courses for inspectors.
The courses are in modular form so that inspectors can enter into the training schedule at a point that is commensurate with their previous experience and training.
In some cases, an inspector may be exempted from a specific course by taking a substantiating examination. Written examinations are given for most courses.
The formal classroom courses are interspersed with onsite and regional duty to provide a balance of theory and practice.
One of the greatest challenges in implementing the revised program is to obtain sufficient numbers of qualified resident inspectors.
Recruitment and training will play an important role.
It is estimated that at least two years will be required to train new inspectors for resident duties even though they may have prior experience in the nuclear industry.
Resident and performance appraisal inspectors for Fiscal Year 1978 and 1979 will come from the ranks of the current IE inspection force since both positions require considerable experience.
Newly recruited inspectors will replace these inspectors in the regions and will provide the necessary manpower for full implementation.
2200 a24
TABLE III Training Courses for Nuclear Power Plant Inspectors Course Title Duration Contents General Courses (For Most Reactor Ins. sectors) 1.
Nuclear Plant Fundamentals 1 week Systems Design and Function Facility Layout 2.
Inspection Techniques 1 week IE Role and Mission Personal Conduct How to Prepare for Inspections How to Deal with Fraud Handling of Identified Safety-Related tutters Evaluation of Licensee Management Effectiveness Legal Aspects of Inspection Operating Courses _ (For Operations, Preoperations and Startup Inspectors) 3.
Power Plant Systems and Procedures
- 4 weeks System Design and Function Facility Layout rsy Component Design and Function rs)
Facility Procedures c;)
Surveillance Testing c:)
Technical Specifications
(#
N Lin
TABLE III (Continued) v Course Duration Contents c
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4.
Integrated Facility Operations
- 3 weeks Introduction to Control Room Panels and Vi Instrumentation Technical Specifications Interrelationship of Plant Systems Effects of Component and Systems Failures on Plant Operations Facility Process Computer Nonnal and Abnormal Operating Conditions 5.
Control Room Operations
- 2 weeks Control Room Fanels & Instrumentation Control Room Indicators How to Identify Technical Specification i Compliance Es How to Evaluate Proper System Lineup and Operating Condition Facility Process Computer Surveillance Testing Evaluation 6.
Facility Design and Operations
- 2 or 3 weeks Primary Flow Cycle Terminology N
Systems Function h
Facility Design Construction Courses (For Construction Inspectorsl g
x 7.
Concrete Technology 2 weeks Concrete Technology for Nuclear Power N
Plants Codes, Standards, Guides and Regulations Related to Concrete
TABLE III (Continued) v; b" Course Duration Contents 8.
Walding Technology 2 weeks Metallurgy of Welding Welding Methods and Techniques Codes and Standards Related to Welding 9.
Nondestructive Examination 3 weeks Ultrasonic Testing Radiographic Testing Liquid Penetrant Testing
- Eddy Current Testing CodesandStandardsforNondestructiv Testing 10.
Electrical
- 3 weeks Cable Separation and Protection Cable Routing Procedures Seismic Considerations Construction Tests Requirements and Acceptable Practices Regarding Receipt, Inspection and Storage Terms and Definitions Industrial Codes N
I'd 11.
Ins trumen tation
- 2 weeks Seismic Considerations C2)
Construction Tests Requirements and Acceptable Practices Regarding Receipt, Inspection
(,a rs) and Storage
'sa Terms and Definitions Industrial Codes
TABLE III (Continued)
Course Duration Contents 12.
Quality Assurance 1 week 10 CFR 50 Appendix B IE Manual Chapters 2511 and 2512 Application of QA criteria to Regulatory Guides, Industrial Standards Codes, Standards, Guides and Regulations Support Inspection Courses 13.
BWR/PWR Radwaste 1 week Design of Radwaste Systems Operation of Radwaste Systems Design and Operations Problems of A,
Radwaste Systems q) 14.
Statistics for Safeguards
- 1 week Fundamentals of Statistics Application of Statistics to Nuclear Facilities 15.
Fundamentals for Safeguards Inspections
- 1 week Safeguards Mission Program Requirements and Relationships Health Physics at Nuclear Facilities Fuel Cycle Operations Fuel Cycle Safeguards rs)
Reactor Fundamentals rs)
Reactor Safeguards O
O
' r' N
TABLE III (Continued)
Course Duration Contents
[$5,6. Safeguards Inspection Program 1 week 10 CFR 50, 70, 73 Requirements
- Safeguards License Conditions Safeguards Responsibilities and Procedures Material Control Inspection Procedures Physical Security Inspection Procedures
- Courses under development.
4, f
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VII. Summary The four elements of the revised inspection program provide a balanced examination of the activities that influence licensee performance related to protecting the public and the environment.
The revised program consists of:
Resident inspectors onsite at all reactors in operation and selected reactors under construction.
Regicn-based inspectors who will supplement the inspections per-formed by the residents with highly specialized inspections in such areas as environmente ' monitoring, physici security and health physics.
Perfonnance appraisal to independently assess licensee perform-ance, the effectiveness of the NRC inspection program and to confirm the objectivity of inspectors.
Vendor and licensee contractor inspectors to assess the quality of services and products purchased by licensees.
The specific requirements of resident, specialist, performance-appraisal and vendor inspectors and of the entire program create a need for a compre-hensive approach to training, management of the inspect-force and rareer development.
The expanded training program for all types of inspectors and the enhanced career-management plan assu.e the performance of all elements of the inspection program by well-trained and experienced inspectors.
The organization, planning and various administrative provisions necessary to implement the revised inspection program are essentially completer Upon approval of the FY 1978 suppleniental badget appropriations request, the NRC will begii implementation with 20 sites in Fiscal Year 1978.
Assuming continued adequate funding, the program should be fully implemented by the end of Fiscal Year 1981.
2200 330
UNITED STATES I
l NUCLE AR REGULATORY COMMISSION w AsmNoToN, 0. c. 20s ss OFFICI AL BustNESS C D " ; ""
M PENALTY FOR PRIV ATE USE. 5300 ta 2200.331