ML19221B109
| ML19221B109 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-12.3, NUREG-75-87, NUREG-75-87 12.3, SRP-12.03, SRP-SRP-12.03, NUDOCS 7907120437 | |
| Download: ML19221B109 (10) | |
Text
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4 U.S. NUCLEAR REGULATORY COMMISSION ddb STANDARD REV EW PLAN
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OFFICE OF NUCLEAR REACTOR REGULATION SECTIO 1 12.3 RADi AilC't PROTECTION DESIGN FEATU?LS HVIEW RF'PO%1BILITIES Primary Radiuloqical Assesirent Branch (RAC)
'# C G h d a r',
- NOne 1.
AREAS UF REVIFW The follcwing ar ea, of the applicant's safety analysis report (SAR) relating to i tion protection desigii 'ratures are reviewed:
1.
FACILITY DES!GN FEATURE 5 In the preliminarj safety analysis report (rSAR), the description of equipr:ent and a.
facility design features used for assuring that occupational radiatico egosures (CN ) will be as low as is reasonably achievable (ALAFA).
b.
The radiation 2cne designations, including zcne boundaries for both norr31 opera-tional and refueling conditions (PSAR and update in the final safety analysis report, FSAR).
c.
'hc illustrative exrples Jf f3Cility desigq f ea ures Cf t he equip ~ent, CorpGnents,
and tysters listed in Secticns 12.1.3 nd 12.3.1 of
-5 tarJard form t and Ccntent.
(Ref. 1) including the scaled layout and arrangenent drawings of the f acility showing all source locations and the other design details requested in Section 12. 3.1 of the " Standard Forr:at.
(F5AR and update in FSAR). Shield wall thick nesses for all shieldeJ spaces should be specified on the draviings or provided in separate tables d.
The description of f acilities and equipment for handling and use of sealed and unsealed special nuclear, source, and bjproduct raterials (PSAR and update in FSAR),
e.
Information describing irplerrntation of Regulatory Guide 8.3 guidelines cn f acilit/ and equipment design and layout.
Inf orration describing alterna tives i f such are proposed (P5AR and update in F5AR).
7907120 0 2
SHIELDING a.
The shielding to be pro /ided for each of the radiation sources identified in 5A?
Chapter ll and Section 12.2, including the design criteria for penetrations and the shield aterial used (PSAR and update in F5AR). (Note item I.l.c above) b.
The description of the methoJs by which the shield p3rar eters wero deterrined, including pertinent codes, assu:"ptions, and techniques used or to be used in the calculations (PSAR and updata in FSAR).
USNRC STANDARD REVIEW PLAN Stenderd review piens are prepared for the gu+dence of the 4)f*ce of Nurtee Reac or Regu!arion ste't toepone h;e f r r the recew of opphcotione to sonevruct end operere aucteer power plante These documente ore vnade owesiebee to the pubiec se port of the Commission e pobr, to enf o<m the nudeer moetry and the geners4 public of regulatory procedu es and potsc.ee Stenderd renew piene are not subet tutes f or requietory guadas or the Commeseson e regulatione end 9
r comp 8:ence wrth them is not requered 1be etenderd review pien sectione are heyed to h vision 2 of the Star deed Formet and Content of Safety Aner ene Repe me v
49e Nucieer Power Piente hot off sorteone of the Stenderd Formee have a earvenpondmg s, new plan Pub 4<ehod sienderd rev+ew piene will be revised perioderselv es appropriate to accom iodete commente and N re 'ect new information and esper er e r
Commeate sad suggee'ione f or 6epprovemeat win be cone de ed end shoved be eent to i e U S Nucieer Regulatory Commese.on office of Nudens Reector Reguset.on Weehmgton D C 20L%b Rev. 1 1 [r /D
) 7
I 1 /
c.
The description of any special protective features that use shielding, geometric arrangement, or rreote handling to assure that ORE will be ALARA (PSAR and update in FSAR).
d.
Inform 3 tion describing implementation of Regulatory Guides 1.f,9 and 8.8 (regard-ing special protective features). Infonration describing alternatives, if such a e proposed (PSAR and update in FSAR).
3.
VENIILATION a.
The description of the personnel protection features incorporated in the ventila-tion system designs called for in Section 12.3.3 of " Standard Fonnat and Content.
b.
Illustrative example of the air cleaning system design (PSAR and update in FSAR).
Information describing any application of Regulatory Gui e 1.52 (particularly d
c.
Section C.4 & 5) and Regulatory Guide 8.8.
Infonnation describing alternatives, if such are proposed (PSAR and update in FSAR).
4.
ARIA RADIATION AND AIRBORNE RADI0 ACTIVITY MONITORING INSTRUMENTATION a.
The description of the fixed area radiation and continuous airborne radioactivity monitoring instrurentation, including in the PSAP, the criteria for placement and in the FSAR additional details as called for in Section 12.3.4, " Standard For~at and Content.
for normal operation, anticipated oper ational occurrences, and accident ccnditions b.
The criteria and method for obtaining representative in-plant airborne radioactiv-ity concentrations (PSAR and update in FSAR).
c.
Inf ormation describing the ic plen.entation of Pegulatory Guides 1.21, 8.2, 8.8, 1.97 and ANSI N13.1.
In onnation describing alternatives, if such are l
f proposed (PSAR and update in FSAR).
II.
ACCEPTANCE CRITERIA The descriptive information in the SAR is considered to be su'ficient if it reets the minimum inforration needs set forth in Section 12.3 of the " Standard Forc at and Contents of Safety Analysis Reports for Nuclear Power Plants, ' Revision 2.
Specific accept 3nce criteria for these areas of review are as follows:
1.
FACILITY DESIGN FEATURES Acceptabilty at the facility design features will be based on evidence that the applicant has applied the guidance in Regulatory Guide 8.8 or that alternatives have bern proposed. This includes evidence that major exposure accumulating functions (rain-tenance, refueling, radioactive material handling, processing, etc., in-service inspec-tion and calibratico) have been considered in plant design and that potential radia-tion exposure from these activities will be kept ALARA by radiation protection features incorporated in the design, including ease of accessibility to work and inspection and sarpling areas, the ability to reduce source intensity, design measures to reduce the production, distribution, and retention of activated corrosion products, the ability to reduce time required in radiation fields, provision for portable shielding and rerote handling tools, etc. Access control will be judged for acceptability in accordance with the requirenents of 10 CFR 520.303.
Rev. I 12.3-2 1/n
.>f I fl I/O
The areas inside the plant structures, as well as the general plant yard, must be identified by showing radiation areas with acceptable maximum design dose rates and Maximum zone dose rate should be defined for each zone, as well as anticipated zones.
e fuli o s. The arcas that occupancy and access control. Acceptance criterio are a3 have to be occupied on a predictable basis (number of people and stay or transit times) during norrnal operations and anticipated operational occurrences (including refueling; purging; f uel handling and storage; radioactive raterial handling; processing, use, storage and disposal; nonnal maintenance; routine operational surveillance; inservice inspection; and calibration) should be zoned such that this occupancy results in an annual dose to each of the involved individuals that is below the limits of 10 CFR Part 20 and is as low as is reasonably achievable, and a total man-ren dese that is as lcw as is reasonably achievable. Based on current operating experionce and on predictions rade for new plant designs, it is expected that the plant shielding can be designed, the plant can be zoned and sufficient radiation protection design features can be incorporated such that these individuals would receive a small fraction of the 10 CFR Part 20 limit. Whether ridiation protection design and zoning is acceptable will be based partly on the actual numbers for average annual radiation exposure to these individuals, determined in the dose assessrent required in Section 12.4 2
SHIELU WG The shielding design is evaluated as to the assurptions used to calculate shield thickness, the calculational method used, and the parareters chosen. Ther e are a nurber of acceptable shielding calculatinnal codes available for ase that are ef fective for determining the necessary shield thickress for ga m 3 ray sources and for ccabina-tion neutron-gama sources. Most of the codes used by shield designers have been entered into the code description file of the Padiation Shielding Information Center at Oak Ridge National Laboratory, whicn reans they have been tested and authenticated for operation but not for reliability and accuracy. RAB has three codes in-house fur use in shielding calculations These are 50C, a kerral integration shield design code; G', a general purpose g era ray scattering program, and "0R5E, a gene purpose Monte Carlo rultigroup neutron and ga"na ray transport code.
SDC can cal:.ulate gara ray shielding requirerents, handling 12 source geretries (including point, line, disk, plane, slab, and sphere) ana with cross sections and raterials corpositions for 17 materials. As many as 12 ga va ray energy groups, covering the range fron 0.1 to 10 MeV, ray be used to descritse the gama ray spectru"'
The staf f will use these codes, as necessary, tu calculate dnse rates for gisen shield designs and source strengths, as a confir"ation of the applicant's r ethod.
The applicant's shielding design is acceptable if the rethods are comparable to com-F only acceptable shielding calcul1tions and assu"ptions regarding source terns, cross section, shield and scurce geo~etries, and transport rethods are realistic. Accepta-ble shielding codes include but are not limited to falSN, DOT, MORSE, 5ALCE, OSR, OER, G, SDC and rany others. This listing does not imply that all the<e codes are equivalent, since some are ruch more sophisticated than nthers The staff believes it is advantageaus tc use a good calculational procedure, since an ef fective snield design is essential to reeting the criteria that occupatinnal radiation exposures will t.e as low a. is reasonably achiev3ble.
12.3-3 Rey, ]
Two doct ments provide additional guidance for acceptability of the shielding cesign.
One is "Peactor Shielding for Nuclear Engineers,' edited by N. M Schaeffer, published by AEC-0IS, 1973." The second is the Stone & Webster Engineering Corpo ation topical g
icpo,t RI-0 entit. led "Radialiun Shielding Deaign and Analysis Appio n 'or Lignt water Reactor Power Plants. " These docu: rents provide useful guidance regarding radiation shielding design. Some limitations are noted for RP-8, in that the labyrinth entrance ways may not provide dose rates at the outside entrance '_onsistent with area radiation zoning.
In addition, Rrgulatory Guide 1.69 provides guidance on the fabrication and installation of concret7 radiation shields for nuclear power plants. Acceptability cf the shield constru: tion will be based en an indication that the guidance of this document has been implemented in the facility construction, or that acceptable alternatives have been 7ecposed. Regulatory Guide 8.8 provides additional acceptance criteria regarding shielding and isolation in radiation protection design.
3.
VENTILATION The ventilation systen will be acceptable for radiation protection purposes if the criteria and bases for ventilation rates within the areas covered in SAR Sectien 12.2.2 will assure that air will flow from areas of low potential airborne radic activity to areas of higher airborne radioactivity and then to filters or vents, and that the concentrations of radioactive material in areas norrially occupied can be raintained in accordance with the requirements of 10 CFR Part 20.
The system shall have adequate capability to reduce concentrations of airborr,e radioactivity in areas not normally occupied where raintenance or in-service inspection has to be perfarned, to levels in
~
accord 3nCe With the requirements of 10 CFR 520.103. The system shall be de>igned so that filters containing radioactivity can be easily maintained and will n)t create an additional radiation hazard to personnel in normally occupied areas. Acc?ptability of the ventilation system, relative to radioactive gases and particulates will also bo based on evidence that the applicant has applied the guidance of Regulatory Guide 8.8 or that alternatives have been prepared.
Regulatory Guide 1.52, particularly Sections C.4 and 5, provides guidance that can be used in this review, although the guide is written with regard to mitigating accidents involving airborne radioactivity. Good practice in that regard is applicable to normal operation as well, since release of radioactivity in nornal operational occurrences is t.sually different only in quantity from some of the accident cases.
4 AREA RADIATION AND A!PB0Pf;E RADI0ACT!VITY MONITORING SYSTEMS The area radiation monitoring systems will be acceptable if they meet the ollowing r
criteria:
The detectors are located in areas which ray be normally occupied without i.
reste icted access and whict ray have a potential for radiation fields in excess of the radiation zone Jesignetion discussed in Subsection 12.3.11.1.
Rev. I 12.3-4 149 1/8
2.
The detectors provide on-scale readings of dose rates that include the design maxin:um dose rate of the radiation zone in which they are located as well as M
k the maninua dose rate for anticiDated operational occurrences.
3.
The detectors are calibrated annually or during fuel outages and after any main-tenance work is performed on the detector.
4.
Each monitor has a local audible alarm and variable alarm set points. Ponitors located in high noise areas should also have visual alarrs.
5.
There is readout and annunciation in the control roon i
b.
The airborne radioactivity nonitoring system will be acceptable if it ceets the I
following criteria:
1.
Air should be sampled at normally occupied locations where airborne racio-activity may exist, such as solid waste handling areas, spent fuel pools, reactor operating floors, and EWR turbine buildings. The monitoring system should be capable of detecting ten MPC-ho;rs of particulate and iodine radioactivity in any compartrent which has a possibility of containing airborne radioactivity and l t
which ray be occupied by personnel. Continuous reni+aring of air being exhausted; from locations within the facility during norra! operation is an acceptable rm thod. The use of nobie gas r:cnitors to inf', airborne radiciodine alarm le/els is also an acceptable nethod.
2.
Reprecentative air concentrations are neasured at the detectors, which are locatcd as close to the sampler intakes is possible.
3.
Ventilation nonitors are upstream of FEPA filters.
4 The detectors are calibrated routinely and af ter any raintonar.ce work is per-for'"ed on the detector.
Each locaiian has a local audible alarr: and variable alarm set points. Manitors located in high noise areas should also have visual alarms.
6.
There is readout an i annunciation in the ccntrol room.
c.
The in-plant accident radiation monitoring systems should grovide personnel with the capability to assess the radiation hazard in areas which may he accessed during the course of an accident. The accident Fontoring systems 'ay include the norn al area radiation onitors, airborne radioactivity ntonitors, and portable radiation i
12.3-5 Rev. 1 149 i79
measurement equipmer Portable inst uments which are to be usad in the event of an accident should be p. cEd to be readily available to personnel responding to an emergency. Energency power should be provided for installed accident monitoring systems. The accident monitoring systems shculd have usable ranges which include the maximum calculated accident levels, and they should be designed to operate properly in the environnent caused by the accidert.
Instrumentation designated to determine very ninh radiation fields in the event of an accident may be placed such that built-in or added shielding provides protection to instruments f ron radiation damage. In such cases these ins tru"'ents will need to be calibrated for the accident conditions. These calibrations however may take advantage of calculated shielding factors, usirig appropriate gaama energ, spectrum distributions.
The range of these instruments must be adequate to monitor the maximum radiation fields calculated in the event of an accident.
d.
Pegulatory Guide 1.21 " Measuring and Reporting of Effluents from Nuclear Power Plants,'
provides useful guidance that is applicable to the acceptability of airborne radio-activity monitoring in-plant.
Regulatory Guide 8.2 includes guidance on surveys to evaluate radiatica hazards. American National Standard ANSI N13.1 provides l
detailed guidance on sampling airborne radioactive materials in nuclear facilities and may be used for acceptance criteria on the actual samplins process and certain techniques involved. Regulatory Guide 8.8 provides guidance on monitoring systems.
e.
Instrumentatic o to monitor for accid:nt criticality will Le acceptable if it meets the criteria of 10 CFR Part 70.N (a)(l,', and Regulatory Guide 8.12, " Criticality Accident Alarm Systems."
III. REVIEW PROCEDURES The information on radiation protection design features furnished in the SAR, including ref erenced parts of Chapters 9 :nd 11, is reviewed fc com pleteness in accordance with the
" Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants,"
Revision 2.
The reviewar evaluates the SAR text and the scaled layout drawings of the facility, concentrating on the sources, shielding, and layouts for the auxiliary building, including the radwaste systems, decontanination facilities, office and access control areas, laundry, lockers and shower rooms, and laboratcry facilities; the fuel handling facilities, including the spent M l pool and related equipnent; and the EWR turbine building, including location of steam lines, reheaters, and moisture separators. For the PSAR this review is particularly concerned with preliminary design features which appear to be con-tradictory to assuring that ORC will be ALA'M.
In this review, radiation protection design features are evaluated using the guidelines of Regulatory Guide 8.8.
The access control plans are reviewed both to determine confomance with 10 CFR Part 20 and to determine whether they will control access properly in limited access areas and in restritted access areas (high radiation areas). Tae reviewer examines locations of critical controls, valve operating stations, punps, sample collection stations, inservice inspection locations, radiation monitors, control panels, mmjor pipes carrying radioactivity, filters for radioactive liquids ar.d gases, and unshielded low level radioactive material storage or Rev. 1 12.3-6 f
processing tanks. SAR Chapters 9 and 11 are reviewed to cover specific details of the fuel handling and storage systems, ventilation systems, and radwaste systems as they relate to radiation protection design. Chapter 9 will provide the major description of the mechanical features of ventilation systems with regard to the venting airborne radioactivity from the plant. Chapter 9 will also cover major features of the spent fuel pool design, the fuel handling ystem design and the spent fuel pool cleanup systen. Chapter 11 r,ay cover sore of the design details of gaseous, liquid and solid radwaste systens that relate to radiation protection. The reviewer evaluates all relevant aspects of the initial design plans particularly to ident-fy new arrangements, irproved designs, unusual shield thicknesses, a new or modified shielJ thickness calculational procedure, unusual assumptions in the calculation, placenent of radiation monitors, etc.
PAB evaluates the adequacy of the applicant's shielding design mn the basis of acceptable radiation shielding codes. RAB nakes a verifying check calculation with SDC, G or MORSF, whichever is specifically applicable to the situation.
For the FSAR the reviewer considers any changes in the design that night necessitate changer in operating procedures to accomr.odate a changed radiation Zone or a dif ferent location of equipnent-The reviewer determines whether the applicant has followed the guidance of the referenced re j ilatory guides and industry standards, both b/ compar ison of the a;'plicant's nothods wi th the infor~atico in the guides and by the applicant's reference to any such guides or to alternati ves that have been proposed. The reviewer evaluates whether the alternatives are equivalent to or irproverents on the rethouc cited in the referenced regulatory quides Alternatises that are neither of these are likely to ce disapproved.
Based on the review, RAB ray request additional inforration or reques t the applicant to reesaluate the radiation protection design features to reet the acceptance criteria of su b wr t i on II.
Ik U. 4. H A T I O.N. F I T. M W, The staf f's review should verify that adequate and suf ficient information is contaiu d in the SA-and r endaents to arrive at ccnclusions of the t ullow'ng type, whith are to be included in tha staff's 5atety valua.icn Report. The r eport v ill include a suntary of the r
applicant's coverage, the staf f's basis or review and acceptance criteria, and the findings of the review. The tallowing is a brief reprosentaticn of the evaluation findings I
The raJiation protection design features at (plant na~e) are intended to help raintain occupa tional radia tion exposure < as low as is reasonably achievable. Many nf these design feattres have been incorporated as i result of the applicant's radiation protection design review and from radiaticn exposure experience gained durino the operatinn of other rmlear pnwer piants (Include e<a ples of dosign features that have been incorporcted into the design to reduce the need for raintenance and other operations in radiation fields, reduce radiation sources where operations mus t be pertcrned; allow quick entry and easy actoss, provide rerote cperatien capability or reduce the time requi red for wor k in radiation fields, i
12.3-7 Pev. 1 149 181
and exariples of other features that reduce radiation exposure of personnel. ) These design features are cansistent with those contained in Regulatory Guide 8.8 and are acceptable.
Areds within the restricted area will be divided into (number of zones) radiation zones.
The dose rate criterion for each of these zones is derived from expected occupancy and access.
restriction.
These criteria are then used as the basis for the radiation shielding design.,
This allows for arrangements of radioactive equiprent that are in accordance with the requirements of 10 CFR Part 20 and the guidelines of Regulatory Guide 8.R.
During plant operation and refueling conditions, the Health Physics staf f Will evaluate area access classifications and ronitor entry into areas to update posting and entry require"ents for 10 CFR Pirt 20.203.
The radiation shielding will be designeJ to provide protection against radiation for operat-ing personnel, both inside and outside the plant, and for the general public. The following are suveral of the shielding design features incorporated into (plant nare). (List several exarmles of shielding design features used at plant.) Sone of the criteria used by (utility) in lacating penetrations in shield wai's at (plant name) are: (list several shield penetra-tion location cri teria used.) These shielding techniques are designed to maintain perscnnel rac iation exposures as low as is reasonably achievable and are acceptable.
The general shield design nethodology and source tern inventories used for (plant nare) are timilar to those described in the topical report (topical report name if applicable), which has been previously reviewed and accepted by the staff. The basic radiation transport analysis used for the applicants' shield design is based on (list appropriate shielding computer codes used). The applicant also used shielding inforration from operating nuclear plants as input data for their snield design calculations All concrete shielding in the plant will be constructed in general compliance with Pegulatory Guide 1.69.
We find 'he shielding design and rethodology presented in the (Preliminary or Final) Safety Analysis Report acceptable based on the criteria of the Standard Peview Plan.
The ventilation system at (plant nare) will be desigred to protect personnel and equiprent fron extreme therr.ai environrental conditions and ensure that plant personnel and the general public are not inadvertently exposed to airborne contaninants exceeding those given in 10 CFR Parts 20 ind 50.
The applicant intends to maintain personnel exposures as Icw as s reascnably achievable by: 1) maintaining air flow from areas of potentially low airborne :
sontamination to areas of higher potential concentrations; 2) ensuring negative or positive pressures to prevent exfiltration or infiltration of potential contaminants, respectivc D,
i and 3) locating ventilation systen intakes so that intake of potentially contaminated air from otner building exhaust points is minimized. These des gn criteria are in accordance with the guidelines of Pegulatory 3uide 1.52 and Regulatory Guide 8.8.
(List exarples of exposure reduction features in the vontilaticn system.)
i The applicant's area radiation monitoring systen is designed to: 1) conitor the radiation levels in areas where radiation levels could becore significant and where personnel may be present; 2) alarn when the radiation vels exceed preset levels to warn of excessive radia-tion levels; and 3) provide a continuous recoro of radiation levels at key locations
)hh b
Rev. 1 12.3-8
throughout the plant. In order to meet these objectives, the applicant plans to use (number) area monitors located in areas where personnel ray be present and where radiation levels could betone significant. The area radiation monitoring systen is equipped with local and remote audio and visual alarms and a facility for central recording. (List examples of other area ronitoring system features.)
The design objectives of the applicants' cirborne radioactivity monitoring system are: 1) to assist in maintaining occupational radiation exposure to airborne contaminants as low as is reasonably achievable; 2) to check on the integrity of systems containing radioactivity which are being monitored; and 3) to warn of inadvertent release of airborne redioactivity to prevent overexposure of personnel. The applicant will install airborne radioa tivity monitors in work areas where there is a potential for airborne radioactivity. These air-borne radioactivity nonitors have the capcbility to detect ten MPC-hours of particulate and iodine radioactivity in any compartment which has a possibility of containing airborne radioactivity and which nay be occupied by per:onnel. The applicant will provide portable continuous air monitors when needed to monitor air in areas not provided with fixed airborne radioactivity monitors. All airborne and area radioactivity monitors will be calibrated at ( ) month intervals (List exar les of other airborne radioactivity monitoring features.)
The objectives and location criteria of (plant name's) area and airborne radiation nenitoring systems are in conformance with 10 CFR Parts 20 and 50 and Regulatory Guides 8.2 and G.B.
The objective of the applicant's accident radiation nonitoring systen is to provide the capability to assess the radiation hazard in areas which ray be accessed during the course of an accident. The installed instruments have emergency power supplies; and the portable instruments are placed to be readily accessible to personnel responding to an emergency.
The systems are designed for use in the event of an accident in terms cf 1) usable in.,tru-ment range, add 2) the environrent the instrument can withstand.
V.
PEFERENCES 1.
Regulatory Guide 1.70, " Standard Forrat and Contents of Safety Analysis Reports for Nuclear Power Plants," Revision 2.
2.
Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at ibclear Power Stations will be as Low as is Reasonably Achievable."
3.
' Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities,"
fcerican National Standards Institute.
4 Regulatory Guide 1.69, " Concrete Radiation Shields for Nuclear Power Plants."
5.
Pegulatory Guide 8.2, " Guide for Adninistrative Practices in Radiation Monitoring."
6.
"Peactor Shielding for Nuclear Lngineers," N. M. Schaef fer, Editor; published by USAEC-0IS,1973.
f4}
j]}
12.3-9 Rev. 1
7.
Regulatory Guide 1.52, " Design, Test, and Maintenance Criteria for Engineered-Safety-Feature At:"osphere Cleanuo System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants."
8.
Regulatory Guide 1.21, "Measurina, Evaluating and ReDorting Radioactivity in Solid Wastes and Releases of Radioac'.ve Materials in Liquid and Gaseous Ef fluents from Liqht-Water-Cooled Nuclear Power Plants."
9.
10 CFR Part 20, " Standards for Protecticn Against Fadiation."
10.
Stone and Webster Tonical Report, " Radiation Shielding Design and Analysis Appro3ch for Light Water Peactor Power Plante, PP-8, 1974.
11.
Regulation Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident."
12.
c qulatory Guide 8.12. " Criticality Accident Alar a Systems."
e
- 13. ANSI N16.2, " Criticality Accident Alarm Systems."
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Rev. 1 12.3-10