Inspection program, evaluating

Food and Drug Administration, Office of Planning and Evaluation. OPE Study 49 Results of the Toxicology Laboratory Inspection Program (Jan.-March 1979). July 1979. 

Principle. The purpose of self-inspection is to evaluate the manufacturer s compliance with GMP in all aspects of production and quality control. The self-inspection program should be designed to detect any shortcomings in the implementation of GMP and to recommend the necessary corrective actions. Self-inspections should be performed routinely, and may be, in addition, performed on special occasions, e.g., in the case of product recalls or repeated rejections, or when an inspection by the heath authorities is announced. The team responsible for seif-inspection should consist of personnel who can evaluate the implementation of GMP objectively all recommendations for corrective action should be implemented. The procedure for self-inspection should be documented, and there should be an effective follow-up programme. 

May BOEMRE direct me to conduct ac BSEE Requirement a. If BOEMRE identifies safety or noncompliance concerns based on the results of our inspections and evaluations, or as a result of an event, BOEMRE may direct you to have an independent third-party audit of your SEMS program, in addition to the regular audit required by 250.1920, or BOEMRE may conduct an audit. Iditional audits Discussion This paragraph contains one of the many BOEMRE references to independent third-party audits. ... 

The items to evaluate to determine the adequacy of the controls designed to prevent unwanted energy flows and exposures to hazardous environments include the technical information system, maintenance and inspection programs, direct supervision and services provided by higher levels of supervision, and the functional operability of facilities (Fig. 18-11). 

The inspection topics are concerned with the existence of an adequate inspection program. Factors to be evaluated include... 

Virtually all definitive test work is done in a pilot plant or plant. The final test is performance of actual operating equipment. A systematic, quantitative inspection program is the final measure of success of a corrosion control program. All other methods are evaluated in terms of how closely they approximate this method. Other methods used are listed and described briefly below. 

Safety officials must ensure that their organization s respiratory protection program complies with the elements covered in the sample program presented above, and they must also ensure that respirator program evaluations are also accomplished. Why Because 29 CFR 1910.134 requires regular inspection and evaluation of the respirator program to determine its continued effectiveness in protecting employees. Remember that periodic... 

Conduct regular inspections and evaluations to determine the continued effectiveness of the program. 

Program Evaluation. An annual evaluation should be conducted to determine whether respirators are being correctly used, maintained, and stored. This evaluation should include physically inspecting a representative sample of the respirators used on the site. The representative sample should include at least 10% of the respirators used on site. 

Risk analysis refers to techniques for identifying, characterizing, and evaluating hazards. The identification of risk, defined in Eq. (12.1), and risk analysis found their way into many applications where they can add value in prioritization and management processes. The application of general risk analysis principles to help prioritize and manage the inspection program for plant equipment, now commonly referred to as risk-based inspection (RBI), is one of the newest applications of risk principles [3]. Some examples of risk criteria and associated units are shown in Table 12.1. 

After appropriate annealing, each LEC and VGF crystal is subjected to an intensive seed- and tail-end wafer inspection program that includes structural control, measurement of electrical parameters and other physical and chemical properties relevant for device manufacturing. Spot checks of wafers between seed and tail are carried out additionally. All data are stored in a data base for continuous and detailed evaluation in relation to technological synthesis, crystal growth and watering parameters. 

Since that time, organizations such as the National Board of Boiler and Pressure Vessel Inspectors and the Technical Association of the Pulp and Paper Industry have issued warnings to plant operators, and these have resulted in the formation of inspection programs for evaluating the integrity of deaerator tanks. As a result, many operators have discovered serious cracking problems. The following example illustrates the problem. 

Additional SRSPO inspection procedures/guidelines will be developed, as needed, to complement the SRSPO inspection programs discussed above. Upon completion,these procedures/guidelines will be evaluated and reported in a supplement to the SER.. Those reviewed to date, including OG-450 and OG-451, were found to be consistent with the restart criteria. Based on the above, the inspections and audits criterion is acceptably satisfied. 

WSRC evaluated the station material condition policies and procedures against the criteria of INPO 85-038. The results of the evaluation are included in the Reactor Maintenance Self-Assessment Report. MIP Sections III and XII includes a plan and schedule to implement a maintenance inspection program and a conduct of maintenance program prior to restart. These two programs address 14 of the 15 self-assessment corrective actions that are related to station material condition. The one remaining corrective action is addressed by MIP Section XIV, "Maintenance Interface and Support Activities." This MIP item addresses the need to monitor, control, and document plant modifications and system changes and is scheduled for implementation in 1991. 

Also, the procedure requires a written report to be submitted for each inspection and a copy to be filed in the Area History File. A copy is also to be sent to the Reactor Technology Department. However, this procedure did not state who is responsible for evaluation, acceptance, or origination of a nonconformance report. WSRC has implemented departmental procedures to resolve these deficiencies by including inspection acceptance criteria in the work packages. The staff determined that DPSOL 105-1851B, as supplemented by other inspection programs discussed below, forms an acceptable basis for restart. 

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