Regulatory Guide 5.28: Difference between revisions

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==A. INTRODUCTION==
==A. INTRODUCTION==
Paragraph (g) of proposed § 70.58 of 10 CFR Part 70 (38FR3077) would require certain AEC licensees authorized to possess special nuclear material to establish, maintain, and follow procedures for reviewing and evaluating shipper-receiver differences. This guide identifies concepts, principles, and methods that are acceptable to the Regulatory staff for determining significant shipper-receiver difference
Paragraph (g) of proposed § 70.58 of 10 CFR Part 70 (38FR3077) would require certain AEC licensees authorized to possess special nuclear material to establish, maintain, and follow procedures for reviewing and evaluating shipper-receiver differences. This guide identifies concepts, principles, and methods that are acceptable to the Regulatory staff for determining significant shipper-receiver differences.


==B. DISCUSSION==
==B. DISCUSSION==
Statistical controls are required as an integral part of special nuclear materials control and accounting systems to assure that licensees of fuel processing and fuel fabrication facilities effectively account for the special nuclear material they possess and identify losses when they occur. An important statistical indicator of control is an observed shipper-receiver difference, which results from comparing two independent determinations of transferred material. A shipper-receiver difference is the difference between the amount stated by the shipper as having been shipped and the amount stated by the receiver as having been receive Essential to a comprehensive evaluation of the significance of this indicator are statistical techniques using associated limits of error for testing whether detected differences may be attributable to measurement erro The power or discernibility of such significance tests depends on the quality and amount of data evaluate The shipper and receiver of transferred material should make independent measurements to determine the amount of SNM in a shipment. A non-zero shipper-receiver difference generally occurs because of errors introduced by sampling bulk materials and measuring weights or volumes and SNM concentrations. Additio.ally, a shipper-receiver difference could be the result of a diversion, theft, unmeasured loss of SNM, or recording mistak The identification and evaluation of shipper-receiver differences is one of the means of detecting diversio theft, loss, or misstatements of the amount of SNM transferred. Additionally, such evaluation and subsequent resolution will tend to limit the amount of material unaccounted for (MUF) transferred from one facility of anothe Subcommittee N15-3 of the American National Standards Institute (ANSI) Standards Committee NI Methods of Nuclear Materials Control, has developed a standard that provides concepts and principles for the statistical evaluation of shipper-receiver differences in the transfer of special nuclear materials. This standar to be designated ANSI NI 5.17, "Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials," has been reviewed by Subcommittee NI 5- This standard references the standard ANSI NI 5.1 "Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control," which defines limit of error as twice the standard deviation of the estimate This is not always consistent with 10 CFR Part 70 and Regulatory Guide 5.3, "Statistical Terminology and Notation for Nuclear Materials which define limit of error as the uncertainty component used in constructing a 95% confidence interval.USAEC REGULATORY GUIDES Copies of published guides may be obtained by request indocatng thr dvs~ons desired to the U.S. Atomic Energy Commission. Washington. D.C. 2054 Regulatory Guidee Ms issued to describe end make available to the public Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regultory staff of implementing specific parts of improvemants in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delinteete techniques .-ed by the staff in of the Commission. U.S. Atomic Energy Commission. Washington. D.C. 2054 evltueting apecific problems or postulated accidents, or to provide guidance to Attention: Chief. Public Proceedings Staf appliceints. Regulatory Guides are not subetitutes for regulations and compliance with themr is not required. Melhods end solutions different from those set out in The guides are issued in the following ten broad division the guides will be acceptable if they provide a basis for the findings requisite to the isuance or continuaers of a permit or license by the Commlssion. 2. Research and Test Reactors 7. Transportation 3. Fuels and Materials Facilities 8. Occupational Heekh Published guides will be revised periodically, as appropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new informaltion or experience. S. Materials end Plant P-otec'ion 10 General  
Statistical controls are required as an integral part of special nuclear materials control and accounting systems to assure that licensees of fuel processing and fuel fabrication facilities effectively account for the special nuclear material they possess and identify losses when they occur. An important statistical indicator of control is an observed shipper-receiver difference, which results from comparing two independent determinations of transferred material. A shipper-receiver difference is the difference between the amount stated by the shipper as having been shipped and the amount stated by the receiver as having been received.  Essential to a comprehensive evaluation of the significance of this indicator are statistical techniques using associated limits of error for testing whether detected differences may be attributable to measurement error.  The power or discernibility of such significance tests depends on the quality and amount of data evaluated.  The shipper and receiver of transferred material should make independent measurements to determine the amount of SNM in a shipment. A non-zero shipper-receiver difference generally occurs because of errors introduced by sampling bulk materials and measuring weights or volumes and SNM concentrations. Additio.ally, a shipper-receiver difference could be the result of a diversion, theft, unmeasured loss of SNM, or recording mistake.  The identification and evaluation of shipper-receiver differences is one of the means of detecting diversion.  theft, loss, or misstatements of the amount of SNM transferred. Additionally, such evaluation and subsequent resolution will tend to limit the amount of material unaccounted for (MUF) transferred from one facility of another.  Subcommittee N15-3 of the American National Standards Institute (ANSI) Standards Committee NI 5.  Methods of Nuclear Materials Control, has developed a standard that provides concepts and principles for the statistical evaluation of shipper-receiver differences in the transfer of special nuclear materials. This standard.  to be designated ANSI NI 5.17, "Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials," has been reviewed by Subcommittee NI 5-3.  This standard references the standard ANSI NI 5.16.  "Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control," which defines limit of error as twice the standard deviation of the estimates.  This is not always consistent with 10 CFR Part 70 and Regulatory Guide 5.3, "Statistical Terminology and Notation for Nuclear Materials which define limit of error as the uncertainty component used in constructing a 95% confidence interval.USAEC REGULATORY GUIDES Copies of published guides may be obtained by request indocatng thr dvs~ons desired to the U.S. Atomic Energy Commission. Washington. D.C. 20545.  Regulatory Guidee Ms issued to describe end make available to the public Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regultory staff of implementing specific parts of improvemants in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delinteete techniques .-ed by the staff in of the Commission. U.S. Atomic Energy Commission. Washington. D.C. 20545.  evltueting apecific problems or postulated accidents, or to provide guidance to Attention: Chief. Public Proceedings Staff.  appliceints. Regulatory Guides are not subetitutes for regulations and compliance with themr is not required. Melhods end solutions different from those set out in The guides are issued in the following ten broad divisions.  the guides will be acceptable if they provide a basis for the findings requisite to the isuance or continuaers of a permit or license by the Commlssion. 2. Research and Test Reactors 7. Transportation 3. Fuels and Materials Facilities 8. Occupational Heekh Published guides will be revised periodically, as appropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new informaltion or experience. S. Materials end Plant P-otec'ion 10 General  


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
The recommendations contained in the proposed ANSI Standard N15.17, "Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials," Draft 5, dated April 10, 1974,1 are generally acceptable to the Regulatory staff for use in nuclear material control and accounting procedures, except that in section 4.6 of the standard the variances used in the evaluation of shipper-receiver differences should be considered as defined in Regulatory Guide 5.18, "Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control," which provides two clarifications with regard to ANSI Standard N15.16-1974 having the same titl In addition, the following should be done: 1. Shipper-receiver differences should be reviewed and evaluated on an individual container, material batch, and shipment basis and on a transfer series of like-type material. Appropriate investigative and corrective action should be taken to reconcile shipper-receiver differences that are statistically significant at the 95% confidence leve . A statistically significant shipper-receiver difference warrants investigation to decide whether corrective action, e.g., reconciliation, is necessary or, more important, whether diversion or theft has occurred. The following measurement information should be available in order to perform an adequate investigation: a. Number of measurements of weight for each lot and containe b. Random and systematic errors for weighings and basis for the error estimate 'Copies may be obtained from the Institute of Nuclear Materials Management, 505 King Avenue, Columbus, Ohio 43201, Attn: Mr. H. L. Toy.d. Sampling scheme used and replicate sampling information, e. Replicate analysis waa f. Number of samples and elemental analyses going into each average value reported, g. Sampling errors and basis for the error estimates, h. Random and systematic errors for the elemental analyses and basis for the error estimates, i. Sampling scheme for isotopic analyses, j. Number of isotopic analyses per lot, and k. Random and systematic errors of the isotopic analyses and basis for the error estimate . In regard to principle 4.3 of the standard, the receiver's measurements, including sampling, should be made independent of the shipper' . In regard to principles 4.2 and 4.4 of the standard, the procedure for evaluating shipper and receiver data should provide the capability to localize any detected diversion to specific transfer material batches and either to a specific container or a specific group of container . Paragraphs 1.1 and 1.2 of the standard purposely limit the scope of the standard. The detection of missing material and, in turn, the uncovering of diversion or theft should be timely. Receipts should be piececounted and item-identified for comparison with the shipment bill of lading as soon as possible, but in no case later than 24 hours after receipt. Also within 24 hours, the integrity of tamper-safing devices should be verified, and receipts should be measured by weighing and, to the extent practical, by nondestructive analysis (NDA) for comparison with shipper's values. More accurate and precise measurements for completing AEC Form 741 and for further data evaluation should be made as soon as practicable.5.28-2c. Replicate weighing data,}}
The recommendations contained in the proposed ANSI Standard N15.17, "Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials," Draft 5, dated April 10, 1974,1 are generally acceptable to the Regulatory staff for use in nuclear material control and accounting procedures, except that in section 4.6 of the standard the variances used in the evaluation of shipper-receiver differences should be considered as defined in Regulatory Guide 5.18, "Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control," which provides two clarifications with regard to ANSI Standard N15.16-1974 having the same title.  In addition, the following should be done: 1. Shipper-receiver differences should be reviewed and evaluated on an individual container, material batch, and shipment basis and on a transfer series of like-type material. Appropriate investigative and corrective action should be taken to reconcile shipper-receiver differences that are statistically significant at the 95% confidence level.  2. A statistically significant shipper-receiver difference warrants investigation to decide whether corrective action, e.g., reconciliation, is necessary or, more important, whether diversion or theft has occurred. The following measurement information should be available in order to perform an adequate investigation: a. Number of measurements of weight for each lot and container.  b. Random and systematic errors for weighings and basis for the error estimates.  'Copies may be obtained from the Institute of Nuclear Materials Management, 505 King Avenue, Columbus, Ohio 43201, Attn: Mr. H. L. Toy.d. Sampling scheme used and replicate sampling information, e. Replicate analysis waaa.  f. Number of samples and elemental analyses going into each average value reported, g. Sampling errors and basis for the error estimates, h. Random and systematic errors for the elemental analyses and basis for the error estimates, i. Sampling scheme for isotopic analyses, j. Number of isotopic analyses per lot, and k. Random and systematic errors of the isotopic analyses and basis for the error estimates.  3. In regard to principle 4.3 of the standard, the receiver's measurements, including sampling, should be made independent of the shipper's.  4. In regard to principles 4.2 and 4.4 of the standard, the procedure for evaluating shipper and receiver data should provide the capability to localize any detected diversion to specific transfer material batches and either to a specific container or a specific group of containers.  5. Paragraphs 1.1 and 1.2 of the standard purposely limit the scope of the standard. The detection of missing material and, in turn, the uncovering of diversion or theft should be timely. Receipts should be piececounted and item-identified for comparison with the shipment bill of lading as soon as possible, but in no case later than 24 hours after receipt. Also within 24 hours, the integrity of tamper-safing devices should be verified, and receipts should be measured by weighing and, to the extent practical, by nondestructive analysis (NDA) for comparison with shipper's values. More accurate and precise measurements for completing AEC Form 741 and for further data evaluation should be made as soon as practicable.5.28-2c. Replicate weighing data,  
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Revision as of 19:44, 6 April 2018

Evaluation of Shipper-Receiver Differences in Transfer of Special Nuclear Materials
ML003740063
Person / Time
Issue date: 06/30/1974
From:
Office of Nuclear Regulatory Research
To:
References
RG-5.28
Download: ML003740063 (2)


June 1974 U.S. ATOMIC ENERGY COMMISSION REGULATORY GUIDE DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 5.28 EVALUATION OF SHIPPER-RECEIVER DIFFERENCES IN THE TRANSFER OF SPECIAL NUCLEAR MATERIALS

A. INTRODUCTION

Paragraph (g) of proposed § 70.58 of 10 CFR Part 70 (38FR3077) would require certain AEC licensees authorized to possess special nuclear material to establish, maintain, and follow procedures for reviewing and evaluating shipper-receiver differences. This guide identifies concepts, principles, and methods that are acceptable to the Regulatory staff for determining significant shipper-receiver differences.

B. DISCUSSION

Statistical controls are required as an integral part of special nuclear materials control and accounting systems to assure that licensees of fuel processing and fuel fabrication facilities effectively account for the special nuclear material they possess and identify losses when they occur. An important statistical indicator of control is an observed shipper-receiver difference, which results from comparing two independent determinations of transferred material. A shipper-receiver difference is the difference between the amount stated by the shipper as having been shipped and the amount stated by the receiver as having been received. Essential to a comprehensive evaluation of the significance of this indicator are statistical techniques using associated limits of error for testing whether detected differences may be attributable to measurement error. The power or discernibility of such significance tests depends on the quality and amount of data evaluated. The shipper and receiver of transferred material should make independent measurements to determine the amount of SNM in a shipment. A non-zero shipper-receiver difference generally occurs because of errors introduced by sampling bulk materials and measuring weights or volumes and SNM concentrations. Additio.ally, a shipper-receiver difference could be the result of a diversion, theft, unmeasured loss of SNM, or recording mistake. The identification and evaluation of shipper-receiver differences is one of the means of detecting diversion. theft, loss, or misstatements of the amount of SNM transferred. Additionally, such evaluation and subsequent resolution will tend to limit the amount of material unaccounted for (MUF) transferred from one facility of another. Subcommittee N15-3 of the American National Standards Institute (ANSI) Standards Committee NI 5. Methods of Nuclear Materials Control, has developed a standard that provides concepts and principles for the statistical evaluation of shipper-receiver differences in the transfer of special nuclear materials. This standard. to be designated ANSI NI 5.17, "Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials," has been reviewed by Subcommittee NI 5-3. This standard references the standard ANSI NI 5.16. "Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control," which defines limit of error as twice the standard deviation of the estimates. This is not always consistent with 10 CFR Part 70 and Regulatory Guide 5.3, "Statistical Terminology and Notation for Nuclear Materials which define limit of error as the uncertainty component used in constructing a 95% confidence interval.USAEC REGULATORY GUIDES Copies of published guides may be obtained by request indocatng thr dvs~ons desired to the U.S. Atomic Energy Commission. Washington. D.C. 20545. Regulatory Guidee Ms issued to describe end make available to the public Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regultory staff of implementing specific parts of improvemants in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delinteete techniques .-ed by the staff in of the Commission. U.S. Atomic Energy Commission. Washington. D.C. 20545. evltueting apecific problems or postulated accidents, or to provide guidance to Attention: Chief. Public Proceedings Staff. appliceints. Regulatory Guides are not subetitutes for regulations and compliance with themr is not required. Melhods end solutions different from those set out in The guides are issued in the following ten broad divisions. the guides will be acceptable if they provide a basis for the findings requisite to the isuance or continuaers of a permit or license by the Commlssion. 2. Research and Test Reactors 7. Transportation 3. Fuels and Materials Facilities 8. Occupational Heekh Published guides will be revised periodically, as appropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new informaltion or experience. S. Materials end Plant P-otec'ion 10 General

C. REGULATORY POSITION

The recommendations contained in the proposed ANSI Standard N15.17, "Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials," Draft 5, dated April 10, 1974,1 are generally acceptable to the Regulatory staff for use in nuclear material control and accounting procedures, except that in section 4.6 of the standard the variances used in the evaluation of shipper-receiver differences should be considered as defined in Regulatory Guide 5.18, "Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control," which provides two clarifications with regard to ANSI Standard N15.16-1974 having the same title. In addition, the following should be done: 1. Shipper-receiver differences should be reviewed and evaluated on an individual container, material batch, and shipment basis and on a transfer series of like-type material. Appropriate investigative and corrective action should be taken to reconcile shipper-receiver differences that are statistically significant at the 95% confidence level. 2. A statistically significant shipper-receiver difference warrants investigation to decide whether corrective action, e.g., reconciliation, is necessary or, more important, whether diversion or theft has occurred. The following measurement information should be available in order to perform an adequate investigation: a. Number of measurements of weight for each lot and container. b. Random and systematic errors for weighings and basis for the error estimates. 'Copies may be obtained from the Institute of Nuclear Materials Management, 505 King Avenue, Columbus, Ohio 43201, Attn: Mr. H. L. Toy.d. Sampling scheme used and replicate sampling information, e. Replicate analysis waaa. f. Number of samples and elemental analyses going into each average value reported, g. Sampling errors and basis for the error estimates, h. Random and systematic errors for the elemental analyses and basis for the error estimates, i. Sampling scheme for isotopic analyses, j. Number of isotopic analyses per lot, and k. Random and systematic errors of the isotopic analyses and basis for the error estimates. 3. In regard to principle 4.3 of the standard, the receiver's measurements, including sampling, should be made independent of the shipper's. 4. In regard to principles 4.2 and 4.4 of the standard, the procedure for evaluating shipper and receiver data should provide the capability to localize any detected diversion to specific transfer material batches and either to a specific container or a specific group of containers. 5. Paragraphs 1.1 and 1.2 of the standard purposely limit the scope of the standard. The detection of missing material and, in turn, the uncovering of diversion or theft should be timely. Receipts should be piececounted and item-identified for comparison with the shipment bill of lading as soon as possible, but in no case later than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after receipt. Also within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the integrity of tamper-safing devices should be verified, and receipts should be measured by weighing and, to the extent practical, by nondestructive analysis (NDA) for comparison with shipper's values. More accurate and precise measurements for completing AEC Form 741 and for further data evaluation should be made as soon as practicable.5.28-2c. Replicate weighing data,