ML20008D489

Intervenor Exhibit I-MAG-120,consisting of Excerpt of INPO May 1988 Guideline INPO 88-010, Guidelines for Radiological Protection at Nuclear Power Stations. Note Exempting Document from Us Copyright Act Encl

ML20008D489
Person / Time
Site:	Seabrook
Issue date:	06/15/1989
From:	INSTITUTE OF NUCLEAR POWER OPERATIONS
To:
References
OL-I-MAG-120, NUDOCS 9003050249
Download: ML20008D489 (14)

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GUIDELINES FOR RADIOLOGICAL PROTECTION AT NUCLEAR POWER STATIONS

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May 1988 INPO 88-010 i

INSTITUTE OF NUCLEAR POWER OPERATIONS Plant Area: Radiological Protection Key Words: Radiation, Contamination, Solid Radioactim Waste i~

LIMITEC DISTRIBUTION: Copyright 1988 by institute of Nuclear Power Operations. All rights reserved.

Not for said. Unauthorized reproduction is a violation of applicable law. Reproduction of not more than

,- ten copes by each recipient for its internal use ce use by its contractors in the normal course of business

' is permitted.This document should not be otherwise transferred or delivereo to any third party, and Ith Contents should not be made public, without the prior pgreement of INPO.

W- . .-

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l INPO 88 010 INTRODUCTION These guidelines describe key elements of a radio. The key to achieving excellence in radiologica! pro-logical protection program at a nuclear power station, tection is management and worker invohement. A implementation of these guidelines should result in a high lewl of performance in radiological protection radiological protection program that achieves a high cannot be achiewd solely by the actions of radiologi.

level of performance and contributes to the safe and cal protection personnel. Corporate managers and i

reliable operation and maintenance of the station. station managers need to actively promote high stan-dards of performance. Chapters I, Vlli, and IX provide gu dance on techniques for dewtoping and maintain-There are five main objecthes oia radiological pro. ng 8 an a fp rmancMn padcular, man-tection program at a nuclear power station. These ob. asement techniques such as the use of radiological gc,; ,, ,f,, g protection goals and a radiological deficiency program

• Individual external radiation exposures should be are described as a means for integrating radiological minimized and should not exceed regulatory or protection into the operation and maintenance of the utility limits (Chapter 111), station by all personnel.

• Indh idual internal radiation exposures should be minimized; significant internal radiation exposures Another essential ingredient in achieving a high should be prewnted (Chapter IV). level of performance in radiological protection is the proper training, qualification and mothation of

• Collecthe radiation exposure should be mini' workers and radiological protection technicians.

mized (Chapter V), Chapter il provides guidance in this area primarily

• The contamination of areas, equipment, and per. by referencing two existing INPO guidelines.

sonnel should be minimized (Chapter VI).

• The generation of solid radioactive waste should These guidelines have been written to assist utill-be minimized (Chapter Vil). ties in meeting the radiological protection perfor-mance objectives in IN PO's criteria documents. it is intended that these guidelines be used by operating in this context," minimize" means that actions are and near term operating stations to review existing or taken to control radiation exposures, contamination, planned programs in radiological protection. Near-and radioactive waste to levels as low as reasonably term operating plants may find these guidelines partic.

achievable. Guidance for achieving each objectie is ularly useful in ensuring that programs and procedures provided in the chapter shown abow in parentheses. under development will achieve a high level of radio-logical protection performance when operating. These Achievement of excellence in radiological protec. guidelines are also intended to be useful to corporate tion requires a level of performance that is well above managers and staff members responsible for the over.

minimum regulatory requirements. It is not sufficient SIS ht of station radiological protection programs. In to judge performance in radiological protection by a particular, these guidelines can be used to assess the lack of regulatory action. The nuclear power industry effectiveness and the adequacy of corporate polic,es i provides protection to its workers and the public be. and station actions in radiological protection. Groups

Wnd regulatory requirements as a standard practice. responsible for evaluating station performance can use Hence, standards of performance outlined in these this document as a basis for their activities, i guidelines reflect reasonably achievable objectives in the context of today's nuclear power industry. It is recognized that many acceptable methods exist to accomplish specific radiological protection objec-tlws. Howewr, stations are expected to meet the intent I

i l

q INPO 88010 t

>f' . of these guidelines. Deviation from any panicular is followed by a discussion section that concisely

guideline does not, in itself, indicate a problem. Differ- describes the actions needed to accomplish the objec.

ences between the guidelines and station practices tiw and includes a brief explanation of why these ac-should be carefully reviewed to determine if practices tions are necessary or imponant. The final section, bLU need to be changed. Additionally, in many cases, ex- guidelines, provides specific guidance for meeting the ample practices are included in the guidelines. These chapter objectiw and INPO's performance objectives Lm" ' examples are identified by "for example" or "e.g."in and criteria. Persons wishing to obtain an oierview of the text or sometimes are included in a parenthetical this document only need to read the introduction and

, phrase. The examples are provided to illustrate an discussion sections of each chapter.

f available method to meet the intent of a guideline but should not be construed as the only such method.

This document supersedes the February 1985

- . preliminary edition (INPO 85-004). Substantiw L. . Each chapter of these guidelines is organized into changes in context are indicated by wrtical side bars in three sections. The introduction briefly describes the the right hand margins. Minor wording changes and cbjective to be achiewd and describes, when needed, format changes are not indicated, the relationship of the chapter to other chapters. This e

s 0

L e

li L

INPO 88-010 -

L TABLE OF CONTENTS n

Chapter Page

. I N T R O D U CT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . I 1

1. RADIOLOGICAL PROTECTION ORGANIZATION AND ADMINISTRATION . . ..............

.A . I n t rod u ct io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

, B. Discussion................................................................ 1 l C. Guidelines............................................................... 1 l 1. Radiological Protection $tandards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 L 2. Resources..............................................................2'

3. Monitoring Radiological Protection Performance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

4. Accou nt abil ity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 II. TRAINING AND QUAllFICATION OF PERSONNEL IN RADIOLOGICAL eROTECTION . . . . . . . . 5 A . I ntrod u ct i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 B. Discussion................................................................ 5 C. Guidelines................................................................ 5 i 1. General Employee Training in Radiological Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

2. Radiological Protection Technician Training and Qualification . . . . . . . . . . . . . . . . . . . . . . . . 6

3. Records................................................................ 7 111. EXTERN AL RADI ATION EXPOSURE CONTROL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 9 1i A . I nt rod u ct i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B. Discussion................................................................ 9 C. Guidelines................................................................ 9

1. Exte rnal Dose limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

2. Administrative Dose Contro!5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10

3. Personnel Monitoring for External Radiation . . . . . , . . . . . . . . . . ......,.......,....11

4. Identification and Control of Radiation Sources . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . , . 14

5. R ec o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 IV. INTERN AL RADIATION EXPOSURE CONTROL . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . 17 i A . I n t rod u ct i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 B . Di sc u s s io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 C . G u id e l i ne s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17

1. Internal Dose Limits and Administrative Control Levels , , . . . . . . . . . . . . . . . . . . . . . . . . . , 17

. 2. Monitoring for internal Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19

3. - Identification and Control of Airborne Radioactivity . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . 20

4. R e c o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2 i

)

iii a

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! INPO 88 010 i

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V. RADI ATION EXPO 5URE REDUCTION '. . . . . . . . . . . . . . . . . . . . . . ..... ..... .......... 25 A . I nt rod u ct i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 B . D i sc u s s ion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 C . G u ide l i nes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25

1. Preliminary Planning and 5cheduling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25

2. Radiological Engineering . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26

3. Radiation Exposure Goals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27

4. Rec o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 Yl. CONTROL OF RADIOACTIVE CONTAMINATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 A . I nt rod u ct i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 B . Discussion . . . . . . . . . . . . ......................................... . ..... 29 C . G u i d e l i n es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 29

1. Radioactive Contamination limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29

2. Personnel Contamination Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30

3. Source ldentification and Contro! . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31

4. R e c o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 Yll. CONTROL OF 5OLID RADIOACTIVE WASTE . . . . . . . . . . . . . . . . . . . ......... .........37 A . I nt rod u ct i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ...... ... ........ 37 8 . Di scu s s ion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... 37 C . G u id e l i nes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37

1. Prewnting Materials From Becoming Radioactive . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37

2. Decontamination and Reuse of Tools and Equipment . . . . . . ..... ................. 38

3. So rti n g Ma t e ria l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38

4. Wlume Reduction Techniques . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38

5. Disposal of Radioactive Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............ 39

6. Reco rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 Vill. CONTROL OF WORK INVOLVING RADIOLOGICAL PROTECTION . . . . . . . . . . . . . . . . . . . . . . 41 A . I nt rodu ct i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 B . D i s cu s s i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 C . G u i d e l i n es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41

1. Supervision and Monitoring of Radiological \Wrk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41

2. Radiological Work Plans and Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42

3. Reco rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4 IX. MONITORING AND IMPROVING RADIOLOGICAL PROTECTION PERFORMANCE , . . . . . . . . 45 A . Int rod uction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................... ....... 45 8 . - Di scu s si on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 C . Guidelines . . . . . . . ' . . . . . . . . . . . . .........................................., 45

1. Radiological Protection incidents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45

2. Radiological Deficiencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 I

iv

INPO 88 Od CHAPTER VI CONTROL OF RADIOACTIVE CONTAMINATION times is uncomfortable and reduces worker productiv-A. INTRODUCTION ity. This reduces restrictions on personnel access for Radioactive contamination controls should mini.

mize the contamination of areas, equipment, and per. operation and maintenance and also reduces solid radioactive waste generation. Mair.caining loose con-sonnel. Control of radioactive surface contamination tamination levels in the RCA as low as practical mini-minimizes possible inhalation or ingestion of radioac, mizes the spread of contamination to personnel and tivity by personnel, skin dose from small particles of the potential for unidentified contaminated areas to radioactivity, and the spread to or build up of radioac. .

exist.

tivity in the environment from operation of the nuclear Instances in which personnel receiw contamina-station. The primary means of preventing the spread of tion on their skin or clothing abow limits or in which ,

contamination should be to contain contamination contamination is spread outside areas controlled foi at its source and to minimize the number of contami. contamination are inwstigated to determine the root nated areas and the amount of loose surface radioac. cause and to prevent recurrence. Records are kept to tivity contained in the contaminated areas.

show how radioactiw contamination and radioactive materials were monitored and controlled.

B. DISCUSSION

~'

Control of radioactiw contamination is accom- C. Guideh,nes j plished bythe following:

1. Radioactive Contamination Limits e establishing limits for radioactiw contamination Station policy should prohibit the release of detect-lewls and boundaries for contaminated areas able quantities of radioactive material either on or in

• identifying and minimizing sources of contamina- equipment and materials released from the station.

tion and radioactive material Detectable quantity is defined as the minimum activity detectable with a frisker (normally 100 cpm above

• planning and performing work to minimize the background) when either performing direct frisks or spread of contamination to areas and personnel in, counting smears.

cluding use of containments when practical

• monitoring personnel as soon as possible as they

a. PersonnelContamination Limits Personnel should be considered contaminated leave contaminated and radiologically controlled when the beta / gamma count rate on any portion of areas their body or personal clothing exceeds 100 cpm Limits for radioactim contamination are used to abow background as measured with a frisker or an define when materials, too?s, and equipment are to be equivalently sensitive technique, or when any alpha controlled as radioactive. A limit also applies to con- contamination is detected.

tamination on skin or clothing and defines when

b. Equ.ipment, Material, and Tool Contamination decontamination of the skin or clo:hing is performed.

Limits Contamination surve s identify sources of contami.

Material, including equipment or tools, should be nation in the plant. Postings, work permits, and radio.

labeled and controlled as radioactim when the logical protection personnel control access to and the beta / gamma count rate on the material exceeds 100 work performed in contaminated areas. The techniques cpm above background as measured with a frisker or described in Chapter V to reduce external and intemal equally sensitlw technique, or when any alpha con.

radiation exposure also can minim!ze the rpread of tamination is detected.

contamination.

Controlling contamination at its source and, there- c. BulkMaterials by, minimizing the number and extent of contaminat- Procedures, methods, and release limits for han-ed areas improves the operation of the nuclear station. dling potentially contaminated bulk materials should There is less need for protective clothing, which many be developed. Bulk materials, such as liquids or sand, 1

1

• l 29

nm .

INPO 88 010 that contain detectable lewls of contamination should larly useful when surveying for highly radioactive parti.

also be controlled as radioactiw material, cles because of the difficulty of detecting particles by hand frisking. Such whole-body contamination moni-

- d. Area Contamination kimits tors should be used at the exits from radiologically (1) Contaminated areas - controlled areas. All persons who enter contaminated Areas with loose surface contamination above areas should monitor themselas for contamination either 1000 dpm/100 cm2 betdgamma or 20 with a whole-body contamination monitor prior to dpmfl00 cm2 alpha should be posted and con- exiting from the radiologically controlled area. Sensi-i trolled as contaminated areas. tivity of these instruments should be set to detect con-tamination equalto stationlimits.

(2) Radioactiwmaterialareas Equipment, tools, materials, and trash with remov- b. FriskingTechniques i able or total contamination in excess of the limits The detector of a hand held frisker should be i of Section "b" abom should be controlled as radi- mowd at less than 2 inches per second at a distance of oacthe materials. Radioactiw materials should be one-half Inch or less from the body. The hand should stored only within contaminated areas or within be frisked before it touches the frisker. The detector radioactive materials storage areas. should be stopped for about 5 seconds at the nose and m uth to check for any indications of inhalation or in-

e. Protective Equipment klmits gestion of radioacthe material. The rest of the body Protective clothing with significant fixed contami- should be scanned paying particular attention to the nation (e.g., greater than 5000 cpm beta gamma on a feet (shoes), elbows, knees, or other areas that may frisker) should be removed from use or disposed of as . have contacted contaminated surfaces. lf an increase ,m radioactive waste. This clothing should not be used count rate is heard, the detector should be held at that i against the body as it might contribute to skin or cloth- location for about 10 seconds, and the meter display ing contamination, but it could be used as an outer should be obserwd. A whole body frisk of 2 or 3 layer of protecthe clothing while working in high con- minutes m nit rs about 10 percent of the body surface.

tamination areas requiring multiple layers of protecthe Background count rates should be below 300 cpm. lf loth '

background count rates below 300 cpm cannot be R piratory protection equipment should be reasonably achieved at the desired monitonng loca.

cleaned to less than 1000 dpm/100 cm) of loose con-tion, frisking to check for gross contamination should tamination prior to reuse. Significant fixed contamina- be performed, and a final frisk should be performed at tion (e.g., above 5000 cpm beta-gamma on a frisker) should be remowd or the equipment should be (mj're tem te location with acceptable background cleaned further before use.

c. Contaminated Areas

f. Aggregate Quantities of Non-bulk Materials Allpers nnelshouldperformawhole-bodyfriskas Individual items that haw been surveyed (frisked) s on as practical after leaving a contaminated area ex-and found to haw no detectable contemination are ceptas notedin 'd below.Thefriskshouldbeper-sometimes placed together to form an aggregate of f rmedpri rtod nninganypersonalclothesnotwn these materials (for example, a bag of trash or collec- in the contammated area. This ensures personal cloth-tions of bags of trash).The aggregate quantity should ing does not lessen the sensitivity of the frisking proc.

be surveyed to ensure the combined contamination ess by shielding beta radiation. All persons who enter

- has not caused detectable gamma radiation levels contammated areas should monitor themsehes with a when surveying with a high sensitivity instrument such whole body contammation monitor prior to exiting as a micro R meter, the RCA.

d. RadiologicallyControlled Areas

2. PersonnelContaminationMonitoring Personnel should be monitored in a whole body l a. AutomaticContaminationMonitors contamination monitor upon leaving the RCA. At l Automatic whole-body or hand and foot contami- " clean" nuclear power stations, personnel should i nation monitors are, in most applications, superior to monitor at least their hands and feet at the contami.

manual frisking. The whole-body monitors are particu-30 lm__

INPO 88-010 nated area exit and their whole body in a whole-body 3. Source Identification and Control  !

contamination monitor at the RCA esit. " Clean" nu- a. AreaContaminationControl cicar power stations are characterized using the follow-ing guidance: (1) Source minimization .

The sources of radioactive contamination should l

. The number and extent of contaminated areas is be controlled to minimize the number and extent low (e.g., less than 5000 ft 2/ unit or 10 percent of the  !

of contaminated areas. Elements of a contamina-RCA excluding containment, drywell and con-tion source control program are control of radioac.

denser bays).

tive leaks, use of good radiological work practices, e Radioactiw particles haw not been detected in the prewntion and prompt cleanup of radioactive plant although special surveys are taken routinely spills,and area decontamination.

to detect them. All station personnel should identify and report

. Loose contamination levels within all contaminat- radioactive leaks during routine surveillances and ed areas are consistently very low (e.g., less than rounds. The leaks should be identified in the sta-10,000 dpm/100 cm2). tion's work control system for repair. Priority should be given to leaks that spread significant e Leaks and spills of contaminated fluids are prompt-c ntamination. Drip pans, containment devices, ly controlled and repaired. or drain hoses to diwrt or collect leakage should

• Work practices are consistently used that mini. be used whenever maintenance cannot be per-mize the spread of contamination. formed quickly to fix the leak or if the leak is of a chronic nature.

e Contamination is spread outside of contaminated areas very rarely. Work sites should be prepared so the spread of contamination is minimized during work. Plan-

= Low numbers of personnel contaminations occur.

ning should include such actions as use of plastic e, Skin and ClothingContamination Records sheets or absorbent material, use of strippable Each personnel skin or clothing contamination coatings, containments, or bottles to collect leak-should be documented and evaluated to help improve age or drippage of radioactiw materials. Workers

the contamination control program. The person's should be trained to use contamination contain-j name and work group should be recorded, along with ment devices for routine maintenance procedures I the location and amount of skin / clothing contamina- such as vale packing replacement and replace-tion, results of decontamination, and a description of ment of radioactiw filters. These devices should

, circumstances involved in the occurrence, such as be used when significant contamination does not 1

RWP number, protectiw clothing required, and protec- already existin the work area.

j tlw clothing actually used on the job. Each report 4 Spills caused by improper maintenance, surveil.  !

should be reviewed by a radiological protection super,

'l -- lance testing, or operational evolutions should be j visor and reported to the worker's supervisor for cor-inwstigated. Appropriate correctim actions in- 1 l rective action,if appropriate. Radiological protection cluding design changes, plant modifications, or

personnel should trend and evaluate skin and clothing procedure revisions should be taken to prevent contaminations monthly for generic causes and to '

recurrence of spills.

i identify personnel who are repeatedly contaminated.

The results of this monthly assessment should be for- Work areas should be cleaned after each job is s warded to responsible station managers for corrective completed. Spills or leaks that spread radioactive action, contamination should be cleaned. After fixing or i~ .

31 4 _ _.

T"- , m

( INPO 88-010 '

I r-E 6 containing leaks, component rooms or cubicles stored, or where contamination boundaries or E should be decontaminated to allow access without postings are located-in areas locked due to s ,protecthe clothing. high radiation lewis, these surveys should only if fuel failures occur, consequences should be evaluated of operating with the failed fuel con-f'ofk' r sidering the added potential for causing small -

• during initial entry into a known or suspected l radioactive particles. The need to repair or remove contamination area and periodically thereafter L failed fuel from the reactor should be determined to determine if conditions have changed -

as soon as possible. Failed fuel should be isolated

[

• at least daily or once per shift at contamination in fuel storage areas to prewnt the spread of small area control points, change areas, or step off pads whenin use To present the generation and spread of particles during maintenance activities, consider imple-

• duringworkinvolvingtheopeningof anyradio-i> menting recommendations from the Electric Power active system or the welding, buming, or grindi ing on equipment containing radioacthe h Research Institute. For example, installation of materials dams in vahes and piping prior to maintenance followed by vacuuming then wiping with a wet

• after a leak or spill of radioacthe materials or towel after maintenance is complete is a prown any time contamination conditions could technique for prewnting radioactie particles fol. changein a work area lowing in place vahe seat maintenance.

• atleastmonthlyinsomeareasoutsideof the Careful monitoring should be performed on previ. radiologically controlled area (i.e., offices, ously used refueling equipment before allowing its shops, and storage areas)-These areas should entry into the plant. The equipment should be be checked on a rotating basis so all areas are cleaned and monitored carefully after use before surveyed at least evey six months. lf contamina.

crossingthe planeof the pooledge. tion is found in these areas, additional surveys should be performed to ensure that no other When particles are known to be in the fuel pool, contamination is outside of controlled areas.-

. use of submersible sub micron filters and fuel pool skimmers should be considered to reduce the con-

• at least daily in lunch / eating areas centration of particles both in the pool and at' Samples from out of the way locations and equip-tached to the pool walls at the water surface, ment and from potential sources of contamination Uncontaminated areas within the RCA should be should be obtained to ensure that a complete as-kept as clean as practical. When a significant frac. sessment of the area is made. Sample locations tion of smears from an area indicate loose contami. should not be restricted to Beneral walkways for nation abow a designated administratiw control routine surwys.

lesel,the area should be cleaned.

Measurements of alpha contamination should be The extent of contaminated areas within the sta. made with instruments such as proportional coun-tion should be tracked. Station ar)d corporate ters or scintillation detectors. Stations that have or -

management should be informed monthly. The base had significant fuel feaks or those that have

. current amount of contaminated areas should be performed chemical decontam!aation of primary compared to previous months and the reasons for systems should check a reprosentative number of f.

increases ordecreasesidentified, smears for alpha e-W,.

-(2) Surwyfrequency Areas with the potential for contamination with As a minimum, surwys for beta / gamma radioactive highly radioacthe particles should be surw>ed

~ contamination should be conducted as follows: weekly when no work is being performed. When

• atleastweeklyinareasfrequently accessed w s cceng,tWqmc#ouhm creased to daily or more often, depending on the where radioactiw materials are handled or l

I 32 i

q INPO 88-010

)

i likelihood of finoing particles and the potential for

• Unless the area is bounded by a set of walls and  !

worker contamination. Standard dry smear tech. doors, a tent, or a containment, entrances to the )

niques are not adequate to collect particles be- area should be marked with )ellow and magenta cause they frequently will not adhere to the smear. rope and signs to signify the presence of radio.

Wet smear, oil impregnated cloth and/or tape, and active contamination.

large area smears should be used for these suneys.

• Pen onnel should not be allowed to eat, smoke, The results of contamination suneys performed to chew, or drink inside a contaminated area. lf assess the adequacy of worker protection should necessary, techniques for providing water to be documented and retained. Each survey record personnel in contaminated areas can be used if should include the following: precautions are taken to ensure that personnel d n tbgestradoactW e dateandtimeperformed

• purpose of survey (reference work permit,if

• w e pen w w n Wn al-lowed access into a contammated area unless app;icab;e) the wound has been cowred to prevent con-

• the type (s) of instrument (s) used and their serial tamination from entering the body through the number (s) (The date of last calibration and any wound. Radiological protection personnel efficiency factors used should be recorded if not should be immediately informed of any wound available elsewhere.) or other injury occurring in a contaminated area s the injury can be checked for contamination.

• asketchordescriptionof theareaorcompo- Actions necessary for saving a life or providing nent sumed rompt medical attention MUST n at be delayed

• thelocationsof anyradiologicalboundaries by attempts to monitor for contammation.

• the name(s)orsignature(s)ofindividual(s)per.

• Areas with a high potential for hot particles re-forming the suney quire specific radiation work permits, increased ,

radiation protection coverage, and special pro-

• evidence of supervisor revlew(i.e., initials or tectim clothing for entry. Respirators and dou-signature) ble protective clothing may be necessary. The Contamination survey results should be reviewed outer protective clothing layer should either be at least weekly by radiological supervisors. This re- discarded after use or handled separately to view should ensure that all required suneys are avoid cross contamination of other less con-performed and suney documentation is accuiate taminated clothing. The floor cowring, and and complete. Also, trends in contamination levels trash bags used in this area should be handled that require further Irwestigation should be iden- in a special manner to prewnt contamination of tified. personnel, in addition to their normal job coser-age functions, radiation protection technician's (3) Contaminated area posting and work control resp nsibilities for work in an area with high Contamination survey information in the form of p tential for hot particles should include the maps, signs, or stickers should be posted conspicu-

- ouslyin or near work areas. ' Assist rkersin removal of the outer protec-For work in areas with known hot particle prob- tive clothing to help asoid contamination of lems, additional precautions such as special post- inner protective clothing and the worker.

- Frequently survey workers to identify and re-

) ing, increased contamination monitoring, and the use of buffer zones should be incorporated to pre- move radioactive particles from protective j

vent the spread of the particles. clothing.

- Clean respirators prior to bagging and

+ Controls for contaminated areas should include rem vaifromthearea.

! the following:

• The area should be conspicuously posted.

33

,- 3 INPO 88-01G

• Stay times should be considered for entry to ccntamination. Receptacles should be placed at areas of most probable contact with hot parti- step.off pads for the segregation of reusable pro-cles. Removal of protective clothing, hand frisk- tectie clothing and trash, ing before entry into the control point and passage through whole body friskers should be (4) RCApostingandworkcontrol required prior to reentry. Controls that should be applied to the radiologi-cally controlled area include the following:

• Protectiw clothing requirements, as well as oth-

, Personnel should not be allowed to eat, drink, er protective and precautionary radiological smoke, or chew. If necessary, techniques for measures, should be included in a radiological work procedure or permit, as discussed in p,,iding water to personnel can be used if Chapter Vlit. precautions are taken to ensure that personnel do notingest radioactivity.

• Protecthe clothing should be wom by person.

nel entering contaminated areas, as follows:

• Personnel should not normally be allowed to

- Personnel entering a contaminated area trawrse the radiologically controlled area in should wear a complete set of protective potentially contaminated protecth'e clothing.

clothing. This consists of a head cover, cover.

• Each entryinto the radiologically controlled alls, glows, bootics, and rubber or cloth owr- area should be controlled by a radiological shoes. Cotton liners can be worn undemeath work or access permit (see Chapter Ylil).

plastic gloves for comfort, but they should not be considered protection from contamina-

b. Equipment and MaterialControl tien. If a respirator is worn, the head cover 0) Surveys should not interfere with the seal between Equipment and material being transferred from the face of the worker and the respirator. radiologically controlled areas, contaminated

- If personnel entering a low-level contaminat- areas, and from highly contaminated job locations ed area (e.g., less than 10,000 dpmA00 cm:) should be surveyed for fised and loose contamina-do not perform any hands-on work but are in- tion to ensure limits are met. Materials removed specting or supervising, protective clothing from contaminated areas need not be surveyed if requirements may be less than those recom- precautions appropriate for the expected contami-mended abow. nation level are taken to prevent the spread of con-

- If personnel are working in a contaminated tamination (e.g., bagging disposable protecthe area with significant removable contamina- clothing for transfer to the waste compactor).

tion (for example, in excess of 50,000 Potentially contaminated bulk materials such as dpmA00cm2), additional protect,ve i clothing should be required. lf work involvmg wet or soil should be determined to be free of contamina-greasy materials is expected or encountered, tion prior to release. Representathe samples of plastic coveralls or aprons should be used in bulk materials that are not suitable for normal addition to a full set of regular protective loose and fixed contamination level assessment clothing to protect personnel from wetted techniques should be counted using established procedures and methods to ensure bulk material materials.

releaselimits are met.

• Stringentlaundrymonitoringrequirements should be established to identify any particles For unconditional release surveys, caution should in protective clothing, be exercised to ensure all surfaces of the item are surveyed. inaccessible surfaces should be treated e The exits of contaminated areas should be as contaminated unless the equipment is disman-provided with a step off pad, where all protec- tied, or special surwy techniques are used and all tive clothing should be removed prior to exiting surfaces are monitored. Personal items, such as the area, in areas where more than one set of clip boards or flashlights, for which precautions protective clothing is used, additional step.off have been taken to prevent them from becoming pads should be used to prevent the spread of contaminated, may be surveyed by the owner in 34

F' .

INPO 88 010 o

the same manner used to perform personnel con. c. Instrumentation tamination monitoring. Contamination surwy equipment should be calibrated prior to initial use, at least semiannually, (2) Containercontrols and whenever damage or malfunction is known or sus-Equipment and material with contamination le els pected. The response of instruments used to monitor above control limits should be stored in contam" personnel contamination should be checked at least nated areas or radioactlye storage areas after being each day the instrument is in use. lf more than one de- .

placed in a container with a label indicating radia- tector or alarm circuit may be used, then each detec-I tion levels and/or contamination lesels, date sur- tor / alarm circuit should be tested.

w)ed, and surwyor. items in contaminated areas Commissioning studies for automatic contamina-  ;

for which the RWP does not include adequate pro- tion monitors should include optimization of false i tective precautions should also be contained alarm rates, counting times, alarm levels, and back-properly and a label applied. Containers that are ground count rates for the actual conditions under continuously attended by a radiatiori verker need which the instrument will be used. Additionally, not be labeled. Whenever practical, strong, tight geometry effects, detector balancing, efficiency, and containers should be used. Bags should be sealed voltage plateaus should be tested.

t with tape.

G) Radioactive material area control ~ 4. Records Radioactiw material areas should be approved by Records that document the important activities as-supervision in wnting and posted conspicuously. sociated with this chapter should be maintained in a i

Radioacthe materials removed from the normal retrievable, legible form. Examples of such records radiologically controlled area (except those inside includethefollowing:

• shipping containers ready for off site shipment) should be labeled and stored in a posted radio.

• contaminationsurveyrecords acthe materials area. An administratiw system a contaminationsurveyinstrumentcalibratiori i should be used to track the location of these areas. documentation Each approved radioactive material area outside e information relating to the setup, testing, calibra-the normal RCA should be inspected quarterly to tion, and response checks performed for whole-ensure the following: body or hand / foot contamination monitors ,

• Theareaisstillneeded.

• reports of skin, clothing, and area contami.

nations-Skin contamination reports should be

• The condition of the area is such that radioac.

tive materials are not subjected to water leaks, filed in the individual's radiation exposure records, extreme temperatures, fire hazards, or other en. A central file of all reports should be maintained vironmental conditions that could degrade the for review by radiological protection personnel, i p

protective wrapping of the materials.

• The radioacthe material wrappings are intact.

• Flammable liquids, gases, or mixtures are not

- stored in or near radioactiw material storage areas. Areas used as approwd radioactiw mate-rial storage areas should be analyzed for fire t' loading to identify any fire protection precau-tions required. Smoking should not be per.

e mitted in radioactive materials areas.

l6

• The area is locked when unattended to ensure

[

that radioactive materials are not subject to un-

[ authorized removal.

35 -