Regulatory Guide 8.19: Difference between revisions

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{{Adams
{{Adams
| number = ML003739550
| number = ML18165A214
| issue date = 06/30/1979
| issue date = 06/14/2018
| title = Rev 1 Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants Design Stage Man-Rem Estimates
| title = Periodic Review
| author name =  
| author name = Stutzcage E
| author affiliation = NRC/RES
| author affiliation = NRC/NRO/DSEA
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person =  
| contact person = Karagiannis H
| document report number = RG-8.19 Rev 1
| case reference number = RG-8.019, Rev 1
| document type = Regulatory Guide
| package number = ML18165A204
| page count = 12
| document type = Regulatory Guidance
| page count = 2
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY
{{#Wiki_filter:}}
COMMISSION
Revision 1 June 1979 REGULATORY
GUIDE OFFICE OF STANDARDS
DEVELOPMENT
REGULATORY
GUIDE 8.19 OCCUPATIONAL
RADIATION
DOSE ASSESSMENT
IN LIGHT-WATER
REACTOR POWER PLANTS DESIGN STAGE MAN-REM ESTIMATES
 
==A. INTRODUCTION==
Section 50.34, "Contents of Applications;
Technical Information," of 10 CFR Part 50, "Licensing of Production and Utilization Facil ities," requires that each applicant for a permit to construct a nuclear power reactor provide a preliminary safety analysis report (PSAR) and that each applicant for a license to operate such a facility provide a final safety analysis report (FSAR). Section 50.34 specifies in general terms the information to be supplied in these reports.
 
A more detailed description of the information needed by the NRC staff in its evaluation of applications is given in Regulatory Guide 1.70, Revision 3, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." Section 12.4, "Dose Assessment," of Regulatory Guide 1.70, Revision 3, states that the safety analysis report should provide the estimated annual radiation exposure to person* nel at the proposed plant during normal opera tions. The man-rem estimate requirement is an important part of the overall, ongoing radiation protection design review. The purpose of this requirement is to provide that adequate detailed attention is given during the prelimi nary design stage (as described in the PSAR), as well as during construction after completion of design (as described in the FSAR), to dose causing activities to ensure that personnel exposures will be as low as reasonably achiev able (ALARA). The safety analysis report pro vides an opportunity for the applicant to demonstrate the adequacy of that attention and to describe whatever design' and procedural chahges have resulted from the dose assess ment process.
 
The objective of this guide is to describe a method acceptable to the NRC staff for per Lines indicate substantive changes from previous issue.forming an assessment of collective occupational radiation dose as part of the ongoing design review process involved in designing a light water-cooled power reactor (LWR) so that occupational radiation exposures will be ALARA.
 
==B. DISCUSSION==
The dose assessment process requires a good working knowledge of (1) the principal factors contributing to occupational radiation expo sures that occur at a nuclear reactor power plant and (2) methods and techniques for ensuring that the occupational radiation expo sure will be ALARA.  In assessing the collective occupational dose at a plant, the applicant evaluates each poten tially significant dose-causing activity at that plant (i.e., activities that result in greater than one man-rem per year). The applicant specifically examines such things as design, shielding, plant layout, traffic patterns, expected maintenance," and radioactivity sources. This evaluation process is aimed at the consideration of eliminating unnecessary exposures, minimizing foreseen required doses (individual and collective), and examining the cost-effectiveness of each dose-reducing meth od and technique.
 
This evaluation process and the dose reductions that may be expected to result are the principal objectives of the dose assessment.
 
The dose assessments prepared in accordance with this guide are intended for use as an aid in what should be a continuing search for dose-reducing techniques and not for NRC regulatory enforcement purposes.
 
The principal benefits arising from this eva luation process occur during the period of pre liminary design since many of the ALARA prac tices are part of the design process. On the USNRC REGULATORY
GUIDES Commento ahud be aunt to di Secrawy of Oe Coma.nion, U.S. Nucer Regubtory Cn-ntmmio.n, Waihington, D.C. 2 , Attention:
Dockeft0 ars Regbtor, Guideq am issued ID decrb rok-, rmilebe to fte pubk Service Branch.  maldiod captsibleo ftO NRC Wl of , -pn, wt of thne Cormn iaona to d" %leeclmiqu umd by fe stiff in eawu- The guides are Wled In fte flowng ton broad dhtalon: L F A", pro ns or POstulAtd cdn. or to provide guidanco to Gukdn we ro subetkutes for regubmora, ad eorn-
 
===1. POVW Reaictors ===
6. Products P1Kmce wflh dn is not requed. Methode and aolutlons iffaMrnt from tioee 2. Reewch and Teat Rmctor 7. Treplortation ea out I dn quldee wl be acceptable ff they provide a beal for fte idge 3. Fu and MeRaNW ins Fact & Occupationel Inhld raque to dihenue m or condinumce of a peri or kern by dte 4. EnroM nenw and Sttig 9. Antitrust and Financial Review Conunlelon
5. MPa lIs and Plant Protectioi
10. General R qued a for age of inued gude (which nay be rprodu or for Convrdtnw and sn gest.or, forl- ipr ntes , in dine , guides are enouragd at pcmnt WChnintont D.C. tat r c of future guides sl times and guidee will be rewbee, n approprite to accomodat Iomet inapcfic I =iln a=uW be aein wrtn oteU.S. Nuclear Regulatory and to ~refetnw ioonormato or emperlec.Tegie rvade ei Comnimaon, Waatibigton, D.C. 2050, Attenrtion:
Dkactor, Division of of VAubeiv covnueta reoivdfo i ui ndaiinlae eiw Tedwilal infrm~rration and Document Control.
 
other hand, additional benefits can also accrue during advanced design stages and even dur ing early construction stages, as better evalu ation of dose-causing operations are available and further design refinements can be identi fied. In addition, operations that will need special planning and careful dose control can be identified at the preoperational stage when the applicant can take advantage of all design options for reducing the occupational dose.  C. REGULATORY
POSITION This guide describes the format and content for assessments of the total annual occupational (man-rein)
dose at an LWR--principally during the design stage. The dose assessment at this stage should include estimated annual personnel exposures during normal operation and during anticipated operational occur rences. It should include estimates of the fre quency of occurrence, ,the existing or resulting radiation levels, the manpower requirements, and the duration of such activities.
 
These esti mates can be based on operating experience at similar plants. However, to the extent possible, estimates should include consideration of the design of the proposed plant, including radiation field intensities calculated on the basis of the plant-specific shielding design, taking into account the effect of any dose reducing design changes.
 
The dose assessment process and the con comitant dose reduction analysis should involve individuals trained in plant system design, shield design, plant operation, and health physics. Knowledge from all these disciplines should be applied to the dose assessment and to the entire radiation protection design review in determining cost-effective dose reductions.
 
Plant experience provides useful information on the numbers of people needed for jobs, the duration of different jobs, and the frequency of the jobs as well as on actual occupational radiation exposure experience.
 
The applicant should use personnel exposure data for specific kinds of work and job functions available from similar operating LWRs.* Useful reports on these data have been published by the Atomic Industrial Forum, Inc. and the Electric Power Research Institute, and a summary report on occupational radiation exposures at nuclear power plants is distributed annually by the Nuclear Regulatory Commission.
 
The occupational dose assessment should include projected doses during normal opera tions, anticipated operational occurrences, and shutdowns and should be based on anticipated radiation conditions after at least 5 years of plant operation.
 
Some of the exposure-causing activities that should be considered in this *See Regulatory Guide 1.16, "Reporting of Operating Infor mation--Appendix A Technical Specifications," for exapleo Of work and job functin.dose assessment include steam generator tube plugging and maintenance, repairs, inservice inspection, and replacement of pumps, valves, and gaskets. Doses from nonroutine activities that are anticipated operational occurrences should be included in the applicant's ALARA dose analysis.
 
Radiation sources and personnel activities that contribute significantly to occu pational radiation exposures should be clearly identified and analyzed with respect to similar exposures that have occurred under similar conditions at other operating facilities.
 
In this manner, corrective measures can be incorpora ted in the design at an early stage.  Tables 1 through 8 are examples of work sheets for tabulation of data in the dose assessment process to indicate the factors con sidered. The actual numbers used in the tabu lations will depend on plant-specific information developed in the course of the dose assessment review.  An objective of the dose assessment process should be to develop 1. A completed summary table of occupa tional radiation exposure estimates (such as Table 1), 2. Sufficient illustrative detail (such as that shown in Tables 2 through 8) to explain how the radiation exposure assessment process was performed, 3. A systematic process for considering and evaluating possible dose-reducing design changes and associated operating proce dure changes as part of the comprehen sive ongoing design review, and 4. A record of the rievidw procedures, documentation requirements, and identi fication of principal ALARA-related changes resulting from the dose assess ment. This record should be included in the assessment as a demonstration of the steps taken to ensure exposures will be ALARA.  During the final design stage, dose assess ment should be updated to take into account any major design changes. In particular, com pleted shielding design and layout of equipment should permit better estimates of radiation field intensities in locations where work will be per formed.  Analysis of the elements of the man-rem esti mate (e.g., radiation levels, task duration, and frequency), treated qualitatively, can be of significant value in making engineering judgments regarding design changes for ALARA purposes.
 
As a result of the dose assessment process described herein, it is to be expected that various dose-reducing design changes and innovations will be incorporated into the design.8.19-2 The precision of the man-rem estimate is of secondary importance.
 
That estimate's relation ship to actual man-rem doses received during subsequent plant operation will depend pri marily on operating experience and maintenance and repair problems encountered rather than on design projections, however precise.
 
Entries in the tables should be identified and their basis explained in the text of the report, e.g., available data from similar plants, expected (reduced)
values due to design, and engineering improvements.
 
Such information will readily identify those areas in which ALARA efforts are to be made or have been made. Additionally, it would be of value to indicate whether the reduced values in appli cable cases were derived on the basis of physical (or other) models. This would alert individuals concerned with the analysis of the occupational radiation dose assessment report in determining whether the well-intended im provements are productive or counterproduc tive.
 
==D. IMPLEMENTATION==
The purpose of this section is to provide in formation to applicants regarding the NRC staff's plans for using this regulatory guide.  This guide reflects current NRC staff prac tice. Therefore, except in those cases in which the applicant proposes an acceptable alterna tive method for complying with specified por tions of the Commission's regulations, the method described herein is being and will con tinue to be used in the evaluation of submittals in connection with applications for construction permits or operating licenses until this guide is revised as a result of suggestions from the public or additional staff review. For construc tion permits, the review will focus principally on design considerations;
for operating licenses, the review will focus principally on administrative and procedural considerations.
 
8.19-3 TABLE 1 TOTAL OCCUPATIONAL
RADIATION
EXPOSURE ESTIMATES
Dose Activity (man-reins/year)
Reactor operations and surveillance (see Tables 2 & 3) Routine maintenance (see Table 4) Waste processing (see Table 5) Refueling (see Table 6) Inservice inspection (see Table 7) Special maintenance (see Table 8) Total man-reins/year Occupational exposures from Tables 2 through 8 are entered in Table 1 and added to obtain the facility's estimated total yearly occupational dose.8.19-4 TABLE 2 OCCUPATIONAL
DOSE ESTIMATES
DURING ROUTINE OPERATIONS
AND SURVEILLANCE
Activity Walking in radiation zones Checking systems and equipment:
Containment cooling system Boron acid (BA) makeup system Fuel pool system Control rod drive (CRD) system Other systems (specify):
! 1 Pumps: CRD Residual heat removal Accumulators Pressurizer valves Other equipment (specify):
.Total Average dose rate (mrem/hr)Exposure Number of time per workers event (hr) Utility Contractor Number of events per year Dose (man-rems/year)
Utility Contractor
-+ -*The list of activities is for illustrative purposes only, is not all inclusive, and would be expected to vary from plant to plant.
 
TABLE 3 OCCUPATIONAL
DOSE ESTIMATES
DURING NONROUTINE
OPERATION
AND SURVEILLANCE
Activity Operation of systems equipment:
Safety injection system Feedwater pumps & turbine Instrument calibration Other (specify):
Collection of radioactive samples: Liquid Gas Solid Radiochemistry Radwaste operation Health physics Other (specify):
Total Average dose rate (mrem/hr)Exposure Number of Number of time per workers events event (hr) Utility Contractor per year Dose (man-rems/year)
Utility Contractor
-+ =The list of activities is for illustrative purposes only, is not all inclusive, and would be expected to vary from plant to plant.00 cO !
TABLE 4 OCCUPATIONAL
DOSE ESTIMATES
DURING ROUTINE MAINTENANCE
Average dose rate (mrem/hr)Activity Changing filters: Waste filter Laundry filter Boron acid filter Pressure valves BA makeup pump o* BA holding pump Instrumentation and controls:
Transmitter inside containment Transmitter outside containment Radwaste processing system Other (specify):
Total*The list of activities is for illustrative Exposure time per event (hr)Number of workers Utility Contractor Number of events per year Dose (man-reins/year)
Utility Contractor
-+ -purposes only, is not all inclusive, and would be expected to vary from plant to plant.
 
TABLE 5 OCCUPATIONAL
DOSE ESTIMATES
DURING WASTE PROCESSING
Activity Control room Sampling and filter changing Panel operation, inspection and testing Operation of waste processing and packaging equipment Other (Specify):
Average dose rate (mrem/hr)Exposure time per event (hr)Number of workers Utility Contractor Number of events per year Dose (man-rems/year)
Utility Contractor
-+ -Total not all inclusive, and would be expected to vary from plant to plant.*The list of activities is for illustrative purposes only, is I OO
TABLE 6 OCCUPATIONAL
DOSE ESTIMATES
DURING REFUELING
Average Exposure Number of Number of Dose , dose rate time per workers events (man-reins/year)
Activity (mrem/hr)
event (hr) Utility Contractor per yearl Utility Contractor Reactor pressure vessel head and internals- removal and installation
---Fuel preparation
-----Fuel handling -----Fuel shipping -----Other (specify):
----?D Total ---+ = CD I The list of activities is for illustrative purposes only, is not all inclusive, and would be expected to vary from plant to plant.  Most work functions performed during refueling, and the associated occupational dose received, will vary depending on facility design (BWR or PWR), reactor pressure vessel size, and number of fuel assemblies in the reactor core. For a detailed description of pre-planned activities, time, and manpower schedule, refer to the "critical path for refueling tasks," which should be available from the Nuclear Steam Supply System (NSSS) supplier.I
TABLE 7 OCCUPATIONAL
DOSE ESTIMATES
DURING INSERVICE
INSPECTION
Average Exposure Number of Number of Dose dose rate time per workers events (man-reins/year)
Activity (mrem/hr)
event (hr) Utility Contractor per year Utility Contractor Providing access: installation of platforms, ladders, etc., removal of thermal insulation Inspection of welds Follow up: installation of thermal insulation, platform removal, and cleanup Total + -= *The list of activities is for illustrative purposes only, is not all inclusive, and would be expected to vary from plant to plant.  0 Estimates should be based on average yearly values over a 10-year period. Variations are expected as a consequence of reactor size, design, number of welds to be inspected yearly, and the degree of equipment automation available for remote examination of welds.I
TABLE 8 OCCUPATIONAL
DOSE ESTIMATES
DURING SPECIAL MAINTENANCE
Activity Servicing of control rod drives Servicing of in-core detectors Replacement of control blades Dechanneling of spent and channeling of new fuel assemblies Steam generator repairs Other (specify):
I I-.Average dose rate (mrem/hr)Exposure time per event (hr)Number of workers Utility Contractor Number of events per year Dose (man-rems/year)
Utility Contractor Total-+ -=The list of activities is for illustrative purposes only, is not all inclusive, and from plant to plant.would be expected to vary significantly Most preplanned (or routine) maintenance activities during outage are described in the "critical path for refueling tasks," which should be available from the NSSS supplier, and are performed in parallel with the critical path refueling tasks to shorten reactor outage time.
 
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Revision as of 14:21, 31 July 2019

Periodic Review
ML18165A214
Person / Time
Issue date: 06/14/2018
From: Stutzcage E
NRC/NRO/DSEA
To:
Karagiannis H
Shared Package
ML18165A204 List:
References
RG-8.019, Rev 1
Download: ML18165A214 (2)
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