Regulatory Guide 3.19

Reporting of Operating Information for Fuel Reprocessing Plants

ML003740314
Person / Time
Issue date:	02/28/1974
From:	Office of Nuclear Regulatory Research
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RG-3.19
Download: ML003740314 (8)

FEBRUARY 1974 U.S. ATOMIC ENERGY COMMISSION

REGULATORY GUIDE

DIRECTORATE -OF REGULATORY STANDARDS

REGULATORY GUIDE 3.19 REPORTING OF OPERATING INFORMATION

FOR FUEL REPROCESSING PLANTS

A. INTRODUCTION

Fuel reprocessing plants may be constructed in steps to provide a buildup of services timed to meet Industry Section 50.36, '"Technical Specifications," of needs, regulatory requirements, and economic

s. These

10CFR Part S0, "Licensing of Production and steps, for example, could include separate construction Utilization Facilities," requires that each applicant for a and startup of facilities for (1) irradiated fuel receipt and license authorizing operation of a production or storage, (2) uranium and plutonium purification and utilization facility include in his application proposed recovery, (3) neptunium recovery, (4) high-level, liquid technical specifications. These technical specifications as waste storage, and (5) high-level liquid waste approved by the AEC are incorporated into the facility solidification. Reporting is required regarding startup license and are conditions of the license. The technical and operation of each service to assure assessment of its specifications for fuel reprocessing plants include a effect on the safety of the entire facility.

section on reporting requirement;. In addition to the reporting requirements necessary for compliance with Some plant operations are maintained continuously the technical specifications of the license, there are from the time of their Initial operation through their specific reporting requirements included in Part S0 as final decommissioning. These facilities require continued well as in Parts 20, 40, 70, 71, and 73 of Title 10. For surveillance and are subject to these reporting the convenience of licensees, these specific reporting requirements regardless of the operational status of requirements are included in the reporting program other plant facilities. For example, coding and storage described in this guide. Each report discussed in this of high-evel liquid waste must be continued whether or guide is either required by ABC regulations or is not the primary solvent exctraction operation for normally specified in licensees' technical specifications. uranium recovery is in operation.

In some cases this program may need to be This guide presents an acceptable reporting program supplemented or modified because of unique plant for fuel reprocessing plant licensees. Tables I and 11 of design features or other factors. The need. for a this guide are compilations of time limits or frequency supplemental or modified program will be determined intervals for submitting routine and nonroutine reports.

on an individual-case basis. An acceptable interim reporting program for radioactive effluents and environmental monitoring is presented in a

B. DISCUSSION

separate guide.,

The information provided in the reports discussed

C. REGULATORY POSITION

herein should be sufficient to permit an assessment by the Commission of all safety-related activities during and The following reporting program should be used to following startup of the facility. implement the reporting requirements of 10 CFR Parts

20, 40, 50, 70, 71, and 73 and reporting requirement In addition to those reports that relate to the safety imposed by the AEC as license conditions including of operation of the plant, the information on nuclear those reports usually required by the technical materials safeguards and on -packages used for specifications.

transportation of radioactive materials that must be SRegulatory Guide 1.21 (Safety Guide 21). "Measuring and Reporting of Effluents from Nuclear Power Plants." Although reported. pursuant to the Commission's regulations is this guide was prepared for use by reactor licensees, it may be also included. used for interim guidance by reprocessing plant licensees.

USAEC REGULATORY GUIDES CoPi. o*

Ode p5ahad y btaied by rQu bm st Ow eiisbi diashd t e US. Atomic Erewy Corssion. Waeninton. DC. 20M4.

Rquoutorv G.ds am beuse toso1, t nd m4nks MeIlal., to the "Ithile Attention: okiector of ROegulatoy Sanderds. Comwments ad ms.mstosn for Prtthode ecmltable to the AEC Reguhatory stf of lknplementqht cff parts of wic lemsot in threud gme eI1 sarf s, and Iould b a-nt to ltIts S*ecretary s

00 CoOMITsiO.?S segultlorss. to delinearte leadwniques kised Isy te staff int of the Commissiuon. US. Atomic Ensemsy C*mss WaNsltron, 0A. 20M5, ovduatieq qseciflc "Irofm Or isstulbtad occidents. or to roide guidance to Atntetion: Chief. Plic P AnPt*f.

amplicent. Rulatory Guldn amenotmsutlttha fr regulatiom end Vomplieni twith them nWtrequitrL Methods end solutiom different fom thousat out in TM pildes amlIsuled in the follawing te Iroad d6idons:

OweMildnewill be ectapbla If thy prowideabmls 1w at~ indpnsequisiteto VW lsustan or ontinuanin of a permit or loom Irbyv te Comrslon. 1. Power Reactor,

6. Products

2. Researchand Toet Rwactor, 7. Trnm'ortatioa

3. Fuels red Matefi, bl Facllties 8. Occupetioml Stath Publishd paid. will be revlied ieriodically. a appropriate, to ecommodete 4. Enironnental end Sitino 9. Antitnrst RAvew owmnuam endto reflect new Inforrntion or expartf. L MUaterIalsed Punl Promction 1

0. GOMMs

I. Routine Reports (d) a progress and status report on any

2 items identified as requiring additional Information a. Operations Reports during the operating license review or during the preoperational testing or startup of the facility, K

(1) Preoperational Reports including items discussed in the AEC's Safety Evaluation Report and Supplements, items on which additional A summary report of preoperational information was required as conditions of the license.

testing, including that performed with unirradiated and items identified in the licensee's preoperational or uranium, should be submitted. The report should startup reports; and include results and conclusions of equipment proof tests, (e) a report of measured in-plant radiation shutdown procedure tests, and emergency procedure levels which' are greater than those estimated in the final tests. Recommendations for any corrective acilons or safety analysis report by a factor of two or more.

equipment modifications indicated by these tests should be included. Other testing may be requested by the (4) Semiannual Operations Reports 4 Commission on a case.by-case basis to match the peculiarities of specific facilities. Schedules for Routine operating reports covering the submitting this Information are proposed by the operation of the previous 6 months should be submitted applicant for approval by the Commission. The reports within 60 days after January 1 and July I of each year.

should be submitted in writing to the Deputy Director The initial report should be submitted within 60 days For Fuels and Materials, Licensing, U.S. Atomic Energy after the end of the first six-month period during which Commission, Washington, D.C. 20545. initial receipt of irradiated fuel took place. Each report should include the following:

(2) Startup Reports (a) Fuel Receiving and Storage A summary report of plant startup testing Amounts, properties, and description should be submitted following receipt of an operating of irradiated fuel received, stored, or shipped.

license, following an amendment to the license involving a planned increase in plant throughput, or following (b) Operations Summary modifications or additions that may have significantly altered the performance of the plant. The report should A summary of operating experience include a description of the measured values of the occurring during the reporting period that relates to the operating conditions or characteristics obtained during safe operation of the facility including a summary of:

the test program and a comparison of these values with (I) processing operations performed design predictions and specifications. Any corrective and their duration;

actions that were required to obtain satisfactory (ii) amounts of radioactive material operation should also be described. Startup reports received, transferred, or stored as high-level liquid or should be submitted within 90 days following solid waste or disposed of as solid waste. Curie content completion of the startup test program. or content of significant isotopes should be stated:

(iii) performance characteristics of

(3) First Processing Year Operation Report safety-related plant structures, systems. and components;

This report should be submitted within 60 (iv) changes in facility design;

days after completion of the first year of processing (v) changes in operating procedures operation. This year begins on the date of initial which were necessitated by (iii) and (iv) above or which processing of irradiated fuel. This report may be otherwise were required to improve the safety of incorporated into the semiannual operating report and operations:

should gover the following: (vi) results of any tests and (a) an evaluation of plant performance to inspections required by the licensee's technicai date in comparison with design predictions and specifications;

specifications; (vii) a brief summary of those changes, (b) a reassessment of the safety analysis tests, and experiments requiring authorization from the submitted with the license application if measured Commission pursuant to 10 CFR 50.59(a); and operating characteristics indicated .that there may be 4 Reports in this category should be submitted in writing to substantial variance from prior analyses; 3 the Director of the appropriate AEC Regulatory Operations Regional Office, except for the reports in Item 1.a(l) and (2).

' Previously submitted safety analysis reports may be incorporated by reference.

(c) an assessment of the performace of I A single submittal may be made for a multiple-activity structures, systems, and components important to facility. The submittal should combine those sections that are safety; common to all activities at the facility.

3.19-2

(viii) any changes in the plant following the year in which initial receipt of irradiated operating staff for those positions designated as key fuel took place. This report may be combined with supervisory personnel positions in the technical semiannual operations reports. Each report should specifications. include the following:

(c) Shutdown (a) Occupational Personnel Radiation Exposure Descriptive material covering all shutdowns occurring during the reporting period. For (i) A tabulation of the number of each shutdown, information should be provided on: occupational personnel exposures for plant operations (i) the part or parts of the plant shut personnel (permanent and temporary) in the following down and the part or parts remaining in operation, e.g., exposure increments (in rem) for the reporting period:

fuel receiving, waste storage, product recovery; no measurable exposure, measurable but less than 0.1, (II) the cause of the shutdown; 0.1-0.25, 0.2S-0.5, 0.5-0.75, 0.75.1, 1.2, 2-3, 3-4, 4-5, (iii) the method of shutdown, e.g., 5.6, 6-7, 7-8, 8.9, 9-10, 10-11, 11-12, and over 12. A

routine or emergency; tabulation of the number of personnel receiving more (iv) duration of the shutdown (in days than 3 rem annually and the major cause(s).

or hours); (9i) A tabulation of the number of (v) status of each part of plant during personnel receiving more than 1000 mrem exposure in the shutdown, eg., operational, hot standby, or the reporting period according to duty function [e.g.,

cdeanout; routine plant operation, surveillance and inspection (vi) consequences of shutdown, e.g., (regular duty), routine plant maintenance, special plant abnormal radiation levels or releases of radioactive maintenance (describe maintenance), routine fuel material to the environs; and handling, and other job-related exposures.]

(vii) corrective action taken to prevent (iii) A report of either (1) the total repetition, if appropriate. number of individuals for whom personnel monitoring is required under 10 CFR § 20.202(a) during the calendar year or (2) the total number of individuals for whom personnel monitoring was provided during the calendar (d) Maintenance year.

A discussion of corrective maintenance (b) FSAR Changes (excluding preventive maintenance) performed during the reporting period on safety-related systems and Submission of revised FSAR pages on components and on systems and components that a replacement page basis appropriately prepared for control, the telesse of radioaetive materials to. the direct Insertion into the applicable FSAR section and environs. For any malfunction for which corrective describing all safety-related changes in facility design, maintenance was required, information should be method of operation, revised safety or transient analysis, provided on: or facility equipment additions. Also a listing of (i) the system or component effective pages by date of revision or revision number involved; should be submitted.

(ii) the cause of the malfunction;

(iii) the results and effect on safe b. Additional Routine Reporting Requirements operation; and (iv) corrective action taken to prevent Table I lists routine reports required by 10 CFR

repetition. Parts 20, 40, 50, 70, and 73, including those listed in Regulatory Position C.I .a.

(e) Changes, Tests, and Experiments

2. Nonroutine Reports A brief description and a summary of the safety evaluation of those changes, tests, and a. Reporting of Abnormal Events experiments carried out without prior Commission approval, pursuant to the requirements of 1OCFR. (I) Abnormal Occurrence Reports

50.59(b).

A notification must be made within 24 (S) Annual Operations Reports hours by telephone and telegraph to the Director of the appropriate AEC Regulatory Operations Regional Reports covering the -operation of the Office, (cc to the Director of Licensing) followed by a previous 12 months should be submitted within the first written report within 10 days to the Director of the quarter of each calendar year. The initial report should appropriate AEC Regulatory Operations Regional Office

"be submitted within the first quarter of the year in the event of an abnormal occurrence.

3.19-3

Appendix A of this guide, "Standard (h) Conditions arising from natural or Format for Reporting Abnormal Occurrences," should man-made events that affect or threaten to affect the be used as guidance when submitting abnormal safe operation of the plant.

occurrence reports.

(2) Reporting of Unusual Events Abnormal occyrrences are dermed in the licensee's technical specifications and usually include, as A written report dsould be forwarded a minimum, items (a) through (h) of this paragraph. within 30 days to the Director of the appropriate AEC

(a) A safety system setting less Regulatory Operations Regional Office in the event of:

conservative than the limiting setting $established in the (a) Discovery of any substantial errors in technical specifications. accident analyses, or In the methods used for such (b) Conditions which result in a limiting analyses, as described in the Safety Analysis Report or in condition for operations not being met. the bases for the technical specifications;

(c) Abnormal degradation of one of the (b) Discovery of any substantial variance several barriers designed to confine radioactive materials. from performance specifications contained in the (d) Leakage of product or radioactive technical specifications or in the Safety Analysis Report;

waste material from storage tanks Into leak monitoring or sumps. (c) Discovery of any condition involving a (e) An unplanned or uncontrolled release possible single failure which, for a system intended to be of radioactive material from the site boundary. designed against assumed single failures, could result in a (f) Incidents or conditions which loss of the capability of the system to perform its safety prevented or could have prevented the performance of function.

the intended safety function of an engineered safety feature system or protection system.

(g) Inadequacies in the Implementation of administrative or procedural controls such that the b. Additional Nonroutine Reporting inadequacy causes or threatens to cause the existence or Requirements development of an unsafe condition in connection with the operation of the plant. Table II lists nonroutine reports required by As defined in Regulatory Guide 3.6. "Guide to Content of 10 CFR Parts 20, 40, 50, 70, and 73, including those Technical Specifications for Fuel Reprocesinl Plants. listed in Regulatory Position C.2.a.

"N

3.19-4

TABLE I

REPORTING SUMMARY-ROUTINE REPORTS

Asquirement Report Timing of Submitulu TS Preoperational As scheduled between licensee and AEC.

TS Startup Within 90 days following completion of the startup test program.

TS First Processing Year Operation Within 60. days aftei completion of the first year of operation. Year begins on the date of processing Irradiated fuel.

TS Annual Within first quarter of each calendar year.

Semiannual Within 60 days after January I and July I of each year.

§20.407 Personnel Expos ure and Monitoring Within first quarter of each calendar year.

§20.408 Personnel Expo sure on Termination of Within 30 days after the exposure of the individual has Employment or Work been determined or 90 days after date of termination of employment or work assignment, whichever is earlier.

§4o.64(a) Transfer of Sour ce Material Promptly upon transfer.

§40.64(a) Receipt of Sourc:e Material Within 10 days after material is received.

§40.64(b) Source Material IInventory Within 30 days after June 30 of each year.

§50.59(b) Changes, Tests, nd ,sxperunents Annually or at shorter intervals as may be specified in the license.

§ 70.53 Special Nuclear daterial Status Within 30 days after June 30 and December 31 of each year..

§70.54 Transfer of Sped al Nuclear Material Promptly upon transfer.

§70.54 Receipt of Speci diNuclear Material Within 10 days after material is received.

§71.61 Loss of Effective ness of packaging Within 30 days after noting loss of effectiveness.

' Technical specifications

.3.19-5

TABLE 11 REPORTING SUMMARY-NONROUTINE REPORTS

Rapoil Notification Requirement Initln Wrt tWn RePort qq qi LJ .. days

""SI Abnormal Occurrence wuMn Z

awtu a

)days TS Unusual Events WiIln 3(

§20.405 Overexposures and Excessive Levels of Radfatiqn and Concentration of Radioactive Material Within 0days

)days Theft or Loss of Material Immediately WIthin 3N

§20.402 Severe Accident Involving Licensed Material Immediately None reqpired

§20.403(a)

Accident Involving Licensed Material W'ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> None req

§20.403(b)

S days Promptly Within I

§40.64(c) Theft or Unlawful Diversion of Source Material

§V0.59(d) Authorization of Changes, Tests, and Experiments Luired

§70.52 Accidental Criticality or Loss of Special Nuclear Promptly None req Material I days

§73.71 Unaccounted for Shipments, Suspected Theft, or Immediately Within 1I

Unlawful Diversion of Special Nuclear Material Special Within 3 months TS

K

'Technical specifications.

'AEC authorization may be required p*ixo to perfmbinkl the chazne, test, or expakaent l1:this category.

'Special reports coveln8 inspections, tests. And maintenance that lur apprOpriAte to Aun= ufe eion or to.

reports are detenlned on an ibdjlud-tu.cuobam deulpte in the facility. The ftequepcy And content of these peclal Technical Specifications.

I

3.19-6

APPENDIX A

STANDARD FORMAT FOR REPORTING ABNORMAL OCCURRENCES

The standard format for submission of abnormal information included, the format for AOR's presented In occurrence reports (AOR) identifies the principal this Appendix should be used, and the information Information that should be contained In a completed requested should be submitted when applicable. If AOR and gives a format for presenting it. In the course investigation is not complete by the time the initial of reviewing past AOR's, the AEC Regulatory staff has report Is submitted, the licensee should so indicate and found a wide variance in the type and detail of information reported. To assure that AOR's submitted give estimated time when a supplemental report will be are consistent both in format and In the principal submitted.

STANDARD FORMAT FOR ABNORMAL OCCURRENCE REPORTS

I. Report Number: 6. Description of Occurrence:

2a. Report Date:

7. Designation of Apparent Cause of Occurrence:

2b. Occurrence Date: - Design

- Installation/Construction

3. Facility: - Procedure

- Unusual Service Condition Including Environmental

4. Identification of Occurrence: - Manufacture

- Operator

- Component Failure

5. Conditions Prior to Occurrence: - Other (specify)

- Routine

- Routine Startup Operation 8. Analysis of Occurrence:

- Routine Shutdown Operation

- Hot Standby 9. Corrective Action:

- Cold Shutdown

- Other (specify) 10. Failure Data:

NOTES TO AOR STANDARD FORMAT

1. Report Number: Abnormal occurrence reports which identifies the type of abnormal occurrence should be numbered sequentially on a calendar-year and the system, component, or event involved.

basis for each facility (or each unit of a multi-unit (Regulatory Position C.2.a.1 should be used es a site) using the facility (unit) docket number as the guide for listing the type of abnormal occurre-ice.)

principal identifier (e.g. Docket Number/Year-Sequential number in calendar year).

Supplementary reports should be numbered using S. Conditions Prior to Occurrence: The applicable alphabetical identifying letters following the caption should be used followed by a description of principal report number (e.g. Docket plant status prior to the abnormal occurrence. Major Number/Year-Sequential number in calendar plant parameters should be included.

year-alphabetical letter identifying supplementary report.) 6. Description of Occurrence: A chronological sequence of events should be described in an

2. Date: Date of (a) report submitted and (b) objective manner. The following should be included:

occurrence.

a. Method of detection and time of detection.

3. Facility: Name and location of facility. b. Step-by-step sequence of events identifying all protection system actions and operator actions

4. Identification of Occurrence: The abnormal to bring the situation under control.

occurrence should be identified by a short title

7. Designation of Apparent Cause of Occurrence: The

3.19-7

single apparent cause should be identified and a. Corrective action taken (or to be taken) to narrated. When other causes contributed to the correct the abnormal occurrence.

abnormal occurrence, the narrative of the apparent. b. Corrective action taken (or to be taken) to K

cause should discuss fully the single cause assigned prevent repetition of the occurrence and of and the contributing causes assigned. similar occurrences.

8. Analysis of Occurrence. The abnormal occurrence 10. Failure DNta Where equipment failure is cause of should be analyzed for safety implications. The the occurrence or equipment failed a a result of the analysis of effects and the attendant consequences occurrence the following information should be should be supported by sufficient information, as provided:

applicable: a. Record of previous failures and malfunctions of a. Maximum and minimum conditions during "the affected systems and components or of transients. similar equipment.

b. Equipment malfunction. b. Equipment identification-(e.g. component.

c. Operator error.

manufacturer, name plate data).

d. Damage to systems and components.

'The cause of the occurrence is desfibed in Item 7.

"Designation of Apparent Cause of Occurrence" and the action taken to bring the situation under control is discussed in Item 6,

9. Corrective Action:' The following information "Description of Occurrences." These items should not be should be provided: repeated in this discussion.

3.1948