ML19221B112
| ML19221B112 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-12.5, NUREG-75-87, NUREG-75-87 12.5, SRP-12.05, SRP-SRP-12.05, NUDOCS 7907120442 | |
| Download: ML19221B112 (8) | |
Text
NU REG-75/087 pR REGg 9
s s
o N;.w,MY ]STANDARD REVIEW PLAN 3\\
U.S. NUCLEAR REGULATORY COMMISSION n
\\'V /
OFFICE OF NUCLEAR REACTOR REGULATION e nn SECTICN 12.5 HEALTH PHYSICS PROGRAM REVIEW PESPOMIBIL TIES Primary - Radiological Assesssent Branch (RAB)
Secondary - Quality Assmince Branch (CAC)
I.
ARE AS OF REVIEW The following areas of the applicant's safety analysis report (SAR) related to the health physics program are reviewed as part of the radiation protecticn prograr 1.
CRGANIZATION a.
tre administrative organization of the health physics program, including the authority and responsibilitj of each position identified (prelininary safety analysis report, FSAR ard gdate in the final safety analysis report, FSAR).
b.
The esperience and qualifications of the personnel responsible for the healtn phys.cs pronrar and for handling and ronitorirg radioactive material. Reference ray be rade to SM Chapter 13 as am rcpriate (final safety analy:is report, FS"R).
c.
Inforration describing the irplementation of Regulatcry Guides 8.8, 8.10, S.2 and 1.8.
Internation describing alternatives, if such are proposed (FSAR and update in FSAR).
d.
Review of qualifications, e g erience, and organization will be cocrdinated witn CA3.
2 ECUlfvENT, INSTPUMDTATION, M D FACILITIES a.
The criteria for sele' ting pcrtable and laboratory technical equipment and instrumentation for perforring radiation and contamination surveys, for in-plant airborne radioactivity monitoring and sarpling, for area radiation ronitorinj, and for perscnnel r:onitoring for corral operaticn, anticipatei operational occurrences and accident ccr ditions (PSAR and updcte in FSM).
b.
The descripticn of instrument storage, calibration, and raintenance facilities (PSAR and update in FSAR).
c.
The description and location of the health physics facilities (including locker and shower rooms, respiratory protective eqJiDrent, and other contaminatico Con-trol equiprient ard areas, and infomation describing hcw such f acilities and services will allow male and female workers to receive the necessary protection against radioactive contamination (PSAR and update in FSAR).
790H 20PD-USNRC STANDARD REVIEW PLAN Stenderd rev,ew p4ene oro propered for the guidance of the Ofhce of Nucieer heector Reg #enon staff resconenble f,* ene review of oppucetions to construct end operste nuclear power poente Theet documeets are made avestab6e to the pubhc es part of the Commission a policy to enf orm the pucieer eridustry and the generet pube6c of reguietory procedures and potecsee Stenderd rev.e p6 ens are not substnutos for reguietow guideo or the Commiseson o regutetsono end ces,hpbonce wfth then,le not roov ted The standard rewtow pien sectione one keyed to Rev eien 2 of the $tendard Formet and Content of Sef ety Analyses Reporte a
foe Nuclear Power Ptente NM eli sectione of the Standard Formet beve e correspond ng review plan Pubbshed stenderd review plane wdl be revised periodicotty. es appropnote. to occommodete commente end to rettact new inf ormation end emperience Commente end eusgesticas for improv* ment won be cons.dered end ohnuid be sent to the U 5 Nuc6eer Reguletory Commies.on Othee of Nudeer iteactor Regulation. Weehengton D C 2%h6 Rev. 1 149 190
d.
The location of items in 2a, b, and c and the description of types of detectors and ronitors, sensitivity, range, and frequency and methods of calibration (FSAR).
e.
Information describing the implementation of Regulatory Guides 8.4, 8.8 and 8.9.
Information describing alternatives, if such are proposed.
3.
FROCEDURES a.
The description of physical and administrative measures for controlling access and stay time in radiation areas (FSAR).
b.
The description of procedures and methods of operation for assuring that occupa-tional radiation exposure (ORE) will be as low as is reasonably achievable ( ALARA)
(FSAR).
c.
The description of methods, frequencies, and procedures for conducting radiatinn surveys (FSAP).
d.
The description of the bases and methods for monitoring and control of personnel and equipment and of surface contamination including reporting practices (FSAR).
e.
The description of methods and procedures for evaluating and contrclling potential airborne radioactivity concentrations, for special air sampling and the issue and use of resoiratory equipment, and for handling and storage of sealed and unsealed byproduct, sovice and special nuclear materials (FSAR).
f.
The description of radiation protection training programs (FSAR).
g.
Information describing the implementation of Regulatory Guides 8.8, 8.10, 8.2, 8.7, 8.9, 1.16, 1.39, and 1.8.
Information describing alternatives, if such are proposed (PSAR and update in FSAR).
II.
ACCEPTACE CRITERI A The descriptive information in the 5AR is considered to be sufficient if it riets the minimun information needs set forth in Section 12.5 of the " Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants," Revision 2.
Specific acceptance criteria for the areas of review given above are as follows:
1.
ORGANIZATION Acceptance will be based on a determination that the organization described, along with the duties, qualifications. and training of the individuals responsible for assuring that ORE will be ALARA are in accordance with Regulatory Guides 8.8, 8.10, 8.2, and 1.8.
Alternatives will be evaluated nr. the basis of a comparison with the referenced Regulatory Guides.
2.
ECUIFMENT, INSTRUMENTATION, AND FACILITIES The following shall be included in order that these iters are acceptable:
a.
The radiochenistry laboratory is equipped to perforn routine analyses required for personnel protection, surveys, and related health physics functions.
b.
The counting room (low background) is equipped and has the rv nary instrumenta-tion to perform routine counting on all plant radioactivity les (water, air, swipe survey, etc. ) in conformance with 10 CFR Part 20.
Couvi g roon equipment n
to normally include the following:
Rev. I 12.5-2
(1) Multi-channel ganma pulse height analyzer.
(2) Low background alpha-teta proportional counter and gama ray and alpha-beta scintillation counters Regulatory Guide 5.9 provides specifications for Ge(Li) spectroscopy systems that ray be useful for application to the ganma ray system.
(3) End window G-M type counter.
c.
Por ta t'l a instruments for measurina radiation or radioactivity to include:
(1) Low and high range ion charber rate neter type instruments.
(2) Portable G-M detectors.
(3) Alpha scintillation or proportional counter rate meters.
(4) Neutron dose rate detector.
(5) Air sanplers for use with particulate filters and iocine collecticn devices (such as charcoal cartridges) and airborne radioactivity monitors.
d.
Persoanel monit3 ring instruments to include:
(1) Friskers for dete; ting radioactive contamination.
(2) Self-reading low and intermediate pocket dosimeters (for early evaluation of individual doses). Perfornance and other requirements shall conform to Regulatory Guides S.4 and 8.14, or to appropriate proposed alternatives.
l (3) Film badges and/or thermoluminescent dosimeters (TLD).
(4) Provisions for bioassay and whole body counting to neet the requirements of 10 CFR Part 20 and Regulatory Guide 8.9, or tc appropriate proposed alternatives.
e.
Utility-issued personnel protection equipnent to included:
(1) Anti-contamination clothing.
(2) Plastic suits for liquid contanination control.
(3) Head covers, shre covers, gloves, and safety related items.
(4) Pressure /Denand full-face-piece air line respirators.
(5) Continuous air flow two-piece plastic suits for covering whole body.
(6) Pressure demand full-face-piece self-contained breathing apparatus.
(7) Full-face mechanical filter respirators.
f.
Personnel protective clothing and equipment th c meet the requirements of the American Standards Institute ANSI Z88.2 andtheU.S.SureauofMinesapprovedl schedules for use in atmospheres containing radioactive materials.
g.
As a minimur the following health physics support facilities or areas be provided.
(1) Portable instrument calibration and storage area. The latter should be easily accessible.
(2) Personnel decontamination area with necessary monitoring equipment. This facility should be located and designed to expedite rapid cleanup of per-sonnel and should not be used as multiple purpose area.
(3) Facility and equipment to clean, sanitize, repair, and decontaminate per-sonnel protective equipment, monitoring instruraants, respirators, etc.
(4) A change room.
(5) Control points for entrance or exit into controlled access areas of the plant.
12.5-3 Rev. 1 149 192
(6) One or more health physics stations, which may be used as the lacation for portable radiation survey equipment, respiratory protective (quipment, per-sonnel nonitoring equipnent, and con amination control supplies. These stations and the equipc'ent should be readily accessible and equipped to facilitate conrunication throughout the plaat.
Acceptance will also be basec' on implementation of the guidance of Regulatt y Guide 8.8 er the provision of acceptable alternativrs.
3.
PROCEDURES Plans and procedures will be acceptable if they meet the criteria provided in Regulatory Guides 8.8, 8.10,1.33, and 3.2 or proposed apprcpriate alternatives. Thereshouldbel provisions for a special control procedure for any zcne 4 or higher area that includes a special survey of the area before entry and the developrent of a radiation work permit program. The work pernit progra, should include the follcwing: 4 ta on radia-tion levels in the area befcre entry and the development of a radiaticn work permit program. The work pemit program should include the following: data on radiation levels in the area, allowab'e wtrking time, protective clothing and respiratory pro-tective equipment, special sools, portable shieloing, and health physics and special personnel r.onitoring device; Maintenance, repair, surveillance, and refueling procedures and methods used by the applicant shculd be reviewed to assure that occupational rac1ation exposures will be ALARA and in accordance with Regulatory Guide 8.8.
For major dose accumulating functions, a post-operation review should be conductcd to evaluate the effectiveness of tne work permit program in assuring that occupadonal radiation expc sures (ORE) will be as low as is reasonably achievable (ALARA). There should be provisions for supervision end control of the handling or r:ovement of mater al within and from radiation or controlled access areas. Acceptance criteria for contamination control limits are being developed. There shall also be provisions for personnel anitoring procedures, bioassay, keeping records of personnel doses, and the reporting of personnel doses. 10 CFR 520.102,.201, 401, and.407 provide the criteria for radiation surveys, personnel nonitoring, bioassay, record keeping, and reporting. Cuidance regarding these areas is provided by Regulatory Guide 8.2 (surveys and personnel monitoring), 8.3 (personnel nonitoring equipment),
8,9 (bioassay), and 1.16,8.2,8.7(recordkeepingandreporting),8.8(decontamination.l inspection, radiation protection progran, and operations), 3.13 (training on radio-active risks to fetuses), and 8.14 (neutron personnel nonitoring).
The acceptability of the health physics program will also be based on provisions for the ind;ctrination and personnel training and retraining prograns Pegulatory Guides 8.P, 8.10, and 1.8 provide inforration rega-ding these areas. Section 19.12 of 10 CFR Part 19 requires i..struction of perscnnel nn radiation protection. There should be a regular review of the radiation protection pregram, which should include updating procedures, equipment, and f acilities where improvements are possible. The program should inciude r egular audits to determine where occupational radiation expnsures are occurrinn and to review possible methods for reducing these exposures.
Rev. 1 12.5-4 iU) l93
With regard to plant cleanliness, which is critical where radioactive material is concerned, Regulatory Guide 1.39 discussea housekeeping requirements that are applicable to operation as well as construction. Finally 10 CFR Part 70 provides the guidance on special nuclear, source, and byprodcct m terials.
III. REVIEW FROCEDURES The infornation furnishtd in the SAR is reviewej for comrleteness in accoraance with the
" Standard Format and Cont >nts of Safety Analysis Reports for Nuclear Power Plants,"
Revision 2.
RAB reviews all the areas discussed in I.,
evaluating acceptability by making the referenced corparisons with regulations, regulatory guides, and industry standards. These can be sumarized as follows 1.
The organizational position, functional respor,sibilities, experience, and qualifications of persons responsible for the health physics program. The plant organizatioa, the functional responsibilities, and the qualifications of personnel are the primary responsibility of the Quality Assurance Branch, and are reviewed as part of Chapter 13.
RAB reviews the heal th pnysics/radiatian protection function and per-sonnel qualifications, in accordance with Regulatory Guide 1.8.
2.
The equipnent necessary to measure rao:nactivity and radiation fields and exposures, including the nunber, type, range, sensitivity, Calibration method aro frequency, availability, and planned used of portable, fixed, laboratory, and personnel monitoring instrumenta tion.
3.
Yhe health physics facilities and associated protective equipment for controlling ORE and contamination.
4.
The training and indoctrination program and health physics instruction manuals, as well as the respiratory protective equipnent 'itting program. Plant procedures are the primary responsibility of the Operator Licensing Branch which reviews in Cnapter 13 (Section 13.5), such formal procedures as the plant radiation p' otection procedures. RAB reviewers of health physics / radiation protection procedura comitments should corriunicate any problems to the OLB.
5.
The procedures to control storage and novement of radioactive material, to control exposures, and to control contamination. Where these procedures are part of the formal plant operating procedures. the review will include informing the OLB of any problems as in 4 above.
Based on the review, RAB may requec' additional information or request the applicant to modify his submission in order to reet the acceptance criteria described in Subsection II.
12.5-5 Rev. 1
)h
IV.
EVALUAT!0N FINDING 5 The staf f's review should verify that adequate and sufficient information is contained in the SAR and amendments to arrive at conclusions of the following type, which are to be included in the staff's Safety Evaluation report. The report will include a sumary of the applicant's coverage, the staff's basis for review and acceptance criteria, and the findings of the review. The following is a brief representation of the evaluation findings: I The health physics program objectives are to provide reasonable csurance that the limits of 10 CFR Part 20 are not exceeded, to further reduca unavoidable exposures, and to ensure that individual ano total man-rem occupational radiation exposures are maintained as low as is reasonably achievable.
The duties of the plant (Health Physicist) include (list duties). The health physics organizations, the qualifications of the health physics personnel, the objectives of the health Physics progran, and the ways in which it will be implemented are in accordance with t k guidelines of Regulatory Guides 8.8, 8.2, 8.10, and 1.8 and are acceptable.
The radiation protection features at (plant name) include a (health physics laboratory radiochemistry lab, personnel decontamination and emergency treatment areas, an access control point, counting room, cali'
+ ion room, respirator testing facility, health physics office, laundry,etc.). These facilities are sufficient to naintain occupational radiation exposures as low as is reasonably achievable and are consistent with the provisions of Regulatory Guide 8.8.
Equipment to be used for radiation protection purposes includes (portable radiation survey instruments, personnel monitoring equipment, fixed and portable area and airborne radio-activity ronitors, laboratory equipment, air sa plers, respiratory protective equipment, protective clothing, etc.).
The number and tges of eruipment to be used is adequate and 4
provides reasonable asst.rance that the applicant will be able to maintain occupational exposures as low as is reasonably achievable.
All pernanent and tenporary plant personnel will be assigned (beta-ganna themolumineaent dosineter badges or film badges) to be worn at all times. These badges will be processed (r onthly), or more frequently if significant exposures are suspected. All personnel assigned (TLD or film badges) are also required to wear (direct or indirect) reading dosineters when entering the controlled area. The readings fron these dosimeters will be used to keep a running total of an individual's dose prior to TLD or film badge processing.
Plant visitors wear self-reading dosinetcrs or are escorted by an individuai wearing such personnel dosimetry devices. Neutron film badges, neutron dosimeters, and alarming dosineters will also be provided for personnel when necessary. Whole t>ody counts of all plant personnel will be con hcted on a scheduled basis and other bioassays will be provided when deened necessary by the (Health Physicist or Radiochemical Engineer). All radiation exposure information will be processed and recorded in accordance with 10 CFR Part 20.
Maintenance, repair, surveillance and refueling procedures and methods used by tnc applicant are reviewed to assure that all plant radiation protection procedures, practices, and l
(} }
Rev. 1
- 12. 5-f;
(
criteria have been considered, to assure that occupational radiation exposures will be ALARA and in accordance with Regulatory Guide 8.8.
Procedures are also developed to I
assure that exposure limits are not exceeded by plant or visitor persnnnel onsite, to administer and contial conditions of radiation work permits; to rost radiation areas; tn establish radiation access control zones; to control all radioactive material entering or leaving the plant site; and to train plant and visitor personnel in radiation protection i
policies and procedures and meet the requirements of Regulatory Guide 1.33.
i l
Based on the information presented in the (PSAR, FSAR) and the applicant's responses to f
our questions, wp conclude that the a;plicant intends to implement a radiation protection program that will mcintain in plant rauiation exposures within the applicable limits of 10 CFR Part 20 and 50 and will maintain exposures as low as is reasonably achievable.
V.
REFERENCES 1.
10 CF R Part 20, " Standards f or Protection Against Radiation. "
2.
10 CFR Part 19, "ht i ces, Instructions and Reports tc Workers; Inspections."
3.
Regulatory Guide 1.8, " Personnel Selection and Training."
4.
" Administrative Controls f or Nuclear Power Plants," American N)tional StanJards Institute S.
Regulatory Guide 8.8, "Information Relevant to Ensuring That Occupati( 11 Radiation Exposures at Nuclear Power Stations Will Be A; Low As Is Reasonably Achievable."
6.
Regulatory Guide 8.6, " Standard Test Procedures for G-M Counters."
7.
ANSI Draft NS47, " Control of Radioactive Surface Contamination on Material, Equipment and facilities to be Released for Uncontrolled Use."
(in preparation) 8.
Regulatory Guide 1.39, "Hausekeeping Requirements for Water Conled Nuc? ear Power Plants."
9.
USBM-23, " Respiratory Protective Services for Use in Atmospheres Containing Radioactive Materials," U.S. Bureau of Mines (1973).
10.
Regulatory Guide 8.7, " Occupational Radiation Exposure Records System."
11.
Regulatory juide 8.4, " Direct Reading and Indirect Reading Pocket Dosimeters."
12.
' Film Badge Perfarmance Criteria."
13.
Regulatory Guide 6.?, " Guide f or Administrative Practices in Radiation Mo.a toring."
12.5-7 Rev. 1 149 196
14.
E'4S I 238. 2,
"Fracecurr-s f> - Rospira tcry Protection,' Anerican '.ational Star.dards institute.
15.
10 CFP Part 20. %;'endix B, Tat;1e 1. " Concentrations in Air and Water Above atural 33ckground.
16.
Pegulatory Guide 1.16 "Fr oorting of Operatirm I n f orma t i c r,.
'7 Regulatory Gaido 1. 70, ' Standard Fcrrat and Contents of Safety A'aly;is Peports for
',.c l e a r r)ne r Plants '
18.
Repiatory Guido S 9 Acce; table Conce; t
" m is, rauatic.;, and Assus.ptions for a Lioassay frograr 19.
10 CFR Part 70, "S;ecial Nuclear Material.
20.
Re :alatory Guide 5.9, ' Specifications of Ge(1.i) 5;.
tr,,ct.cy Syst ms for N itural Protectior "easurements - Part !
C.tta Acquisition."
21.
h olatory Guide 1.33, 'Puality Assurance Progra" & quirements (Operation ).
22.
P"quiatory G;ide 8.14. " Personnel Neutrcn Dosimeters.
23.
Requlatory Guide 8.15, " Acceptable Proqra~s for Respira tc c, Prc tectic-c4 Pegulatery Guido 8.13, " Instruction Concerning enatal Radiation Exposure.
O m't/
ml l' Rev, 1 12.5-8 I
g