ML20128B632

Work Plan for Soil Remediation of National Park Svc Property Located Near Pawling,New York for Chevron Usa,Inc

ML20128B632
Person / Time
Site:	07000903
Issue date:	11/30/1992
From:	Abelquist E, Reisenweaver D, Wolff J CHEVRON U.S.A., INC.
To:
Shared Package
ML20128B622	List: ML20128B619 ML20128B632 ML20128B645
References
PROC-921130, NUDOCS 9212040034
Download: ML20128B632 (49)

Text

I I

I WORK PLAN g

g FOR THE SOIL IEMEDIATION I

OF THE I

NATIONAL PARK SERVICFs PROPERTY I

LOCATED NEAR PAWLING, NEW YORK I

FOR THE I

CHEVRON USA, INCORPORATED g

I I

I NOVEMBER 1992 I

PREPARED.AND SUBMITTED BY:

INTEGRATED ENVIRONMENTAL SERVICES DIVISION OF NbCLEAR ENERGY SEPVICES JI

!A 2888A 3n884 a c

PDR

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WORK PLAN

.l FOR TIIE SOIL REMEDIATION OF TIIE NATIONAL PARK SERVICE PROPERTY I

LOCATED NEAR PAWLING, NEW YORK

^

FOR TIIE CIIEVRON USA, INCORPORATED I

NOVEMBER 1092

, *i Prepared by:

b... M.' b ' #642

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Eric W. Abelquist, Project Manager I

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Approved by:A' Mff'._

W/WV I Dennis W. Reisenweaver, Department Minag'er I

Approved by: -<Sb a k lt[

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Jot (n Wolff, Chev d[ USA, Incorporated Representative I

TAllLE OF CONTENTS

- I 1.

SCOPE.....................................................................J U.

S ITE CO N D ITI O N S....................................................... !

Ill.

CONTR A CTOR RELATIONS H I PS................................... 1 IV.

WORK PLA N CONTR OL S YSTEM.................................. 2 V.

PERSONNEL...............................................................3 l

VI.

RA DIOLOG IC AL PROTECTION..................................... 4 Vll.

CONTA M I N ATION CONTROL......................................,4 I

Vill. W O R K TA S K S..............................................................,5 Task 1 - Engineering...................................................... 5 Task 2 - Obtain Shipping Containers.................................... 5 Task 3 - M obilization...................................................... 5 I

Task 4 - Initial Site Inspection /S u rvey................................... 6 Tas k 5 - Soil Ex cavation................................................... 6 g

Task 6 - Soil Sam pling..................................................... 7

's Task 7 - S hip men t of Waste............................................. 7 Task 8 - De mobilization.................................................... 7 Task 9 - Prepare Final Reports........................................... 8 IX.

RADIOLOGICAL INSTRUMENTATION............................. 8 X.

SHIPPING AND DIS POS AL............................................. 9 R EF ER EN C ES....................................................................... ] 1 APPENDICES A - Procedure 82A8037, " Airborne Radioactivity Program" B - Procedure 82A8026, " Soil Sample Preparation for Gamma Spectroscopy" I

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1.

SCOPE The purpose of this work plan is to provide a logical and safe method for soil I

remediation at the Nuclear Lake Site. Soil remediation is the Drst phase of the Nuclear 12ke site decommissioning project.

This work plan is to be used as a guide in performing the soil remediation operations.

Soil remediation will consist of removing the isolated " hot spots" as identined in the Oak Ridge Associated Universities (ORAU) radiological report (Ref.1).

The overall project has been divided into tasks which are discussed in detail in Section Vill of this plan.

The goal of this plan is to remove and dispose of the contaminated soil so that the I

affected outside areas may be released for unrestricted use. At the conclusion of the Nucleat Lake site decommissioning project, a final release survey will be performed on the remediated area to verify that remediation efforts have been successful in achieving the release criteria. Specifically, soil contamination levels will comply with the U.S. Nuclear Regulatory Commission (USNRC) agreed upon limits of 25 pCilg for plutonium and 15 pCi/g for Cs-137.

II.

SITE CONDITIONS I

The Nuclear Lake site has been characterized by ORAU in their 1988 radiological.

survey. ORAU determined that contamination levels existed in several building and soil locations that exceed current guidelines for unrestricted use.

The soil contamination consisted of several small areas of Cs-137 and Pu-239/240 identified outside the Plutonium Facility and Waste Disposal Building.

With few exceptions, exposure rates throughout the site wue in the range of background radiation.

III.

CONTRACTOR RELATIONSillPS A.

Chevron USA, Incorporated 1.

Chevron USA, Incorporated and the National Park Service will be the waste generators for the purposes of manifesting the radioactive waste shipments.

.l 2.

The USNRC approval of this plan implies that the Chevron USA, I

I Incorporated and the National Park Service can act as shipper for the radioactive waste under an enforcement option. Therefore, a license is not required.

B.

Nuclear Energy Services / Integrated Environmental Services (NES/IES) 1.

NES/IES will provide all personnel, equipment and other resources necessary to remediate the contaminated soil identified by the ORAU radiological survey.

2.

NES/IES will manifest all radioactive waste shipments in accordance with USNRC and Department of Transportation (DOT) regulations.

3.

NES/IES on behalf of the Chevron USA, incorporated and National l

Park Service has the responsibility for safety during the remediation operations.

IV.

WORK PLAN CONTROL SYSTEM All activities and tasks must be conducted in accordance with this work plan and/or the appropriate NES/IES procedures. The overall work plan will be prepared by the Project hianager and approved by the designated Chevron representative and the Nuclear Regulatory Commission.

Any major changes which involve the deletion or addition of tasks, adverse impact on scheduling, or possible creation of new or greater potential hazards must be approved by both the Project hianager and the NES/IES Radiological Services Department hianager, hiajor changes must be reviewed by the Chevron representative, hiinor changes to the work plan (i.e., reordering of specific steps, allowing j

simultaneous tasks to be performed) must be approved by the Site Supervisor and the Project hianager.

All changes will be documented and attached to the work plan.

Implementation of changes will be entered into the project journal and the journal will be made available at all times at the work site for review.

I 2

V.

PERSONNiiL A.

Training 1,

Health Physics Technicians will be trained to meet the requirements of ANSI /ANS 3.1-1981.

2.

Decontamination Technicians will be provided radiation worker training, which will include the following topics:

a.

Fundamentals of Radiation and Radioactivity.

b.

Biological Effects of Radiation, c.

Detection and Measurement of Radioactivity.

d.

Radiological Controls.

e.

Personnel Responsibilities.

l f.

Emegency Response.

B.

Plan of the Day g

1.

At the start of each day a work briefing will be conducted. This 3

meeting will be administered by the Site Supervisor or his designee.

2.

The purpose of this briefing is to review work that was performed the I

previous day, discuss potential problem areas, and ensure that everyone understands the tasks that are to be performed during the current day.

3.

The briefing will be used to check the following:

a.

The necessary tools and equipment are available.

b.

Each worker knows how to perform their assigned tasks.

c.

Each worker understands the radiological conditions of the area in which they will be working.

C.

Key Personnel 1.

Project Manager - Eric W. Abelquist 3

(

i

2.

Site Srpervisor - William Needrith 1

3.

Radiological Services Department Manager - Dennis W. Reisenweaver VI, RADIGIDGICAL PROTECTION A Radiation Work Permit (RWP)is a means of providing the radiological conditions under which work in a radiologically controlled area will be performed. The RWP provides controls to ensure the work is accomplished in a radiologically safe manner while maintaining personnel radiation exposure as low as reasonably achievable l

(ALARA).

The RWP will be prepared by the Health Physics Technician based on expected and l

surveyed conditions. The RWP will be approved by the Site Supervisor prior to the start of the task.

All personnel making an entry under an RWP shall comply with the requirements, instructions and precautions of the RWP. All personnel entering the controlled area will be monitored using a thermolurninescent dosimeter (TLD) and self-reading dosimeter (SRD). A log of individual exposures will be maintained.

I VII.

CONTAMINATION CONTROL The radiologically controlled areas (RCAs) will be isolated from the general work 1

I areas through the use of radiation barrier rope and warning signs. RCAs will be established to encompass each soil excavation location. A step-off pad will be placed at the entrance of each RCA.

A container will be provided for the disposal of contaminated clothing and waste, y

Personnel will wear protective clothing prior to entering the controlled area.

l Protective clothing requirements will be specified in the appropriate RWP.

l l

Personnel leaving the controlled area shall survey themselves with the appropriate instrumentation prior to leaving the RCA. The Health Physics Technician will be contacted if it is determined that an individual has become contaminated.

l All material leaving the controlled area will be surveyed to ensure that the item is either not contaminated or properly handled for either decontamination or disposal as radioactive waste.

Airborne contamination may be generated during the course of the soil remediation operations. Air samples will be taken downwind of the excavation site both on a 4

I

continuous, routine basis and as specified in the appropriate RWP. For operations 7

with an increased potential of generating airborne contamination, a high volume air sample will be collected. If warranted by the air sampling results, the soil will be sprayed with water to minimize the generation of airborne contamination during the soil remediation efforts.

Although it is extremely unlikely that respiratory protection will be necessary, it will be required if air concentrations exceed 3E-12 pCi/ml for alpha emitters (conservatively based on Pu-238, Pu-239 and Pu-240 Class W compounds) and 6E-8 pCi/ml for beta / gamma emitters (based on Cs-137). Table 4-2 of NES/IES procedure 82A8037, " Airborne Radioactivity Program" contains further respiratory protection requirements (refer to Appendix A).

Respirator fit testing will be administered to all individuals required to wear a respirator. A qualitative fit test will be accomplish on site using a challenge atmosphere (e.g., irritant smoke test). In addition to the fit test, negative and positive pressure tests will be performed by each individual cach time a respirator is g

donned.

Vill. WORK TASKS TASK 1 - ENGINEERING NES/IES will provide procedures governing the work to be performed at the Nuclear l

Lake Site, including this specific Work Plan. These procedures will be on-hand prior to our on-site mobilization and will be implemented as part of the site activities.

TASK 2 - OBTAIN SHIPPING CONTAINERS Low specific activity (LSA) shipping containers will be fabricated and delivered by an approved vendor. Volume of these containers has been determined to accommodate maximum packing efficiency and minimize weight surcharges.

TASK 3 - MOBILIZATION This task includes:

Travel of workers to the site.

Receipt of materials and equipment.

Staging of equipment.

5 I

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Set up of6ce.

Familiarize personnel wit.1 site.

Setup radiological instrumentation.

Training and site orientation.

TASK 4 - INITI AL SITE INSPECTION / SURVEY This task includes:

Identify the krations reported by ORAU as exhibiting elevated soil contamination levels of Cs-137 and/or Pu-239/240.

Obtain soil background samples.

Isolate the area to be excavated with radiation rope. Establish a step-off pad at the RCA entrance.

I Setup personnel surveying instrumentation at the RCA entrance.

Ilaseline air monitoring.

Perform photographic survey.

TASK 5 - SOIL EXCAVATION This task requires the issuance of a Radiation Work Permit (RWP) prior to task-commencement. The RWP will include the protective clothing requirements and the placement of low volume air samplers at locations on the perimeter of the RCA.

I-Initially, the " hot spots" identiDed by ORAU will be located with the assistance of the reference grid system and survey instrumentation. A 1 meter radius will be marked for excavation from the " hot spot" location.

I Personnel must wear self-reading dosimeters and thermoluminescent dosimeters during the soil excavation. A small backhoe and/or shovels will be used to perform the soil excavation. The soil excavation will be guided through the use of Held survey instrumentation. Specifically, as the soil is removed, the HP Technician will scan the freshly exposed soil for the presence'of contamination. Low energy gamma

.l-detectors (e.g., Eberline PG-2) and alpha probes (e.g., Eberline AC-3-8) will facilitate the detection of the plutonium isotopes. Beta / gamma probes (e.g., Ludlum 44-9 GM pancake probes) will allow detection of Cs-137 in the contaminated soil.

6 I

The resulting holes from soil excavation will not be filled. Soil samples from the hole will be collected during the Gnal site release survey to conRrm that the remediation efforts were successful, The holes will be covered with plywood and conspicuously marked in accordance with OSHA requirements.

j The exutvated soil will be placed in an LSA container. Once filled, the LSA container will be surveyed and shipped to the Barnwell, SC burial site. Refer to the Shipping and Disposal section for more detailed information.

TASK 6 - SOIL SAMPLING Soil samples may be collected prior to the soil excavation to facilitate determination of the vertical and horizontal extent of soil contamination. NES/IES soil sampling procedures will be followed.

Soil samples will also be collected for purposes of manifesting the quantity of each l

radionuclide shipped to the Barnwell disposal sita.

The soil samples may be analyzed for gamma emitters with a Ge detector in accordance with NES/IES procedure 82A8026, " Soil Sample Preparation for Gamma Spectroscopy" (refer to Appendix B). Soil samples will be sent to an approved laboratory for isotopic plutonium analysis.

TASK 7 - SHIPMENT OF WASTE This task includes:

Prior to the conclusion of NES/IES soil remediation activities, all wastes associated with this specific work plan will have been shipped off-site and disposed of appropriately.

All records of contaminated and clean waste shipments will be turned over to the client.

l TASK 8 - DEMOBILIZATION This task includes:

All equipment will be surveyed and decontaminated, as required, prior to shipment off-site.

7 I

All released NES/IES equipment, supplies and material will be packaged and shipped to the home office in Danbury, CT.

Upon conclusion of the remediation activities, the site will be cleaned according to the NES llousekeeping procedure, 82A8039.

All materials used for contamination control will be disposed of as clean or contaminated waste as appropriate.

The post remediation status of the affected areas will be photographed.

TASK 9 - PREPARE FINAL REPOEIS This task includes:

The final report will be prepared in Danbury and submitted to Chevron.

The final report will include records of all laboratory sample analyses, survey data, soil remediation operations and calculations of activity shipped to the disposal site.

IX.

RADIOLOGICAL INSTRUMENTATION The following table indicates the type of radiological protection equipment that will be I-used to monitor the radiological conditions during the soil remediation operations. In addition, survey instrumentation that will allow the field determination of the extent of the soil contamination is listed.

Instrument ihg Self-reading dosimeter Daily personnel exposure Eberline RAS 1 Routine air samples during soil excavation Lnw volume air sampler I

SAIC/Radeco H-809 VI Air samples as specified by RWP High volume air sampler

<l Ludlum 2220 w/Eberline AC-3 Personnel survey for alpha contamination probe l

Ludlum 3 w/44-9 GM probe Personnel survey for beta / gamma 8

1 t

contamination l

Bicron Micro-Rem meter General area exposure rate measurement-Ludlum 2929 phoswich detector Alpha, beta / gamma smear counter

~

Eberline ESP-1 w/PG-2 probe Low energy gamma soil scan (i.e., Pu-239/240)

Ludlum 2220 w/Eberline PG-2 Low energy gamma soil scan Ludlum 2221 w/44-9 GM probe Beta / gamma soil scan (i.e., Cs-137)

Canberra GC1020 Ge detector Scil saraple analysis w/ multichannel analyzer (MCA)

J X.

SillPPING AND DISPOSAL A.

Packaging i

1.

All material (e.g., contaminated soil, personnel protective equipment) will be placed in the disposal containers. Depending on the quantity of material being disposed of, either full or half-size LSA boxes or 55 gallon drums may be used.

2.

No liquids will be packaged for shipping and disposal.

B.

Shipping 1.

Each disposal container will be surveyed and the results documented prior to shipping.

2.

Shipments will be made in accordance with 49 CFR and 10 CFR requirements.

3.

A certified radioactive waste transporter will be used as the waste g

hauler.

4.

As a contingency, if it is not economically feasible to ship the radioactive waste that is generated during the soil remediation activities in a separate shipment, then the waste containers will be stored inside the Plutonium Facility. This material /ill be shipped along with the l

waste generated during the building decontamination operations.

9 l

i.

I 1

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C.

Disposal 1.

All radiologically contaminated material from the soil remediation efforts will be disposed of at the Barnwell Site in South Carolina.

2.

Disposal will be handled by ChemNuclear.

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s itEFERENCES 1.

Berger, J.D. et al. " Radiological Survey of the Nuclear Lake Site, Pawling New York," Oak Ridge Associated Universities; 1988.

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APPENDIX A I

Airborne Radioactivity Program

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q NUCLEAR ENERGY SERVICES DOCUMENT NO.

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I M M PAGE OF AIRIlORNE RADIOACTIVITY PROGRAM P

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- Froga Aponcaton Copy Ney Assignea To GE:!ERIC APPROVALS g

TITLE / DEPT. - SIGNATURE - DATE I ' REV NO PREPARED BY REVIEWED BY APPROVED BY PROJ. MGR.

DEPT, MGR, l.

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1 Eric Abelquist l

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82A8037 REVISION LOG o o Cu u sin tio._

A OF tiUCLEAR Et4ERGY SERVICES, It4C.

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E D E SC RIP T!ON APPROVAL i

DATE I

1 8/21/92 p.,1,,,., 7, y,. p g a. 4 p.

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CRA 842'

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10/16/92 6

CRA 8486 - incorporated Fidd Chance 001 I

into the rroredure.

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FopW # NES 306 SW T

I DOCUMENTNo.

82Ae03-l NUCLEAR ENERGY SERVICES PAGE 3

0F

'M TABLE OF CONTENTS PAGE 1.

INTRODUCTION 4

I 1.1 Scope 4

1.2 General Back round 4

F 1.3 References 4

I 2.

LIMITS FOR AIRBORNE RADIOACTIVITY 5

2.1 Federal Limits 5

3.

MONITORING AIRBORNE RADIOACTIVITY 5

3.1 Routine Air Sampling 5

3.1.1 Sampling Tecnniques 5

3.1.2 Sampling Frequencies 5

iA 3.1.3 Counting Air Samples 6

(4D 3.2 Environmental Sampling 7

3.3 Records and Reports 7

3.4 Calibration 8

4.

CONTROLLING AIRBORNE RADIOACTIVITY

-8 I-4.1 Personnel Exposure 8

4.2 Respiratory Protection 10 4.2.1 Genem!

10 4.2.2 Wearing Respiratory Protection Equipment 10 4.2.3 Respiratory Protection Maintenance Program 11 4.2.4 Respiratory Protection Training Program 11 l-4.3 Use of High Efficiency Particulate Air Filter 12 ll APPENDIX A Airborne Safety Assurance Program Al I

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i FOIM WNES 205 7/90

~ I DOCUMENT NO.

gypnn NUCLEAR ENERGY SERVICES PAGE 3

-OF 1A

1. INTRODUCTION 1.1 SCOPE This procedure specifies the methods to be employed for maintaining concentrations of I

airbome radioactivity below established limits. This procedure shall be employed by Nuclear Energy Services (NES).

I 1.2 GENERAL BACKGROUND INFORM ATION Airbome radioactivity is the presence of radioactive particles or gases in the air. Control of airbome radioactivity is necessary to limit the internal radiation exposure that can result from the inhalation of radioactive material.

The respiratory protection program is the responsibility of the Radiological Controls Supervisor. The Radiological Controls Technicians implement the program. Although airbome radioactivity is not expected to exceed the concentrations permitted by 10CFR20.

Appendix B, Table 11. respiratory protection requirements and use is discussed.

Airbome radioactivity concentrations shall be minimized to the extent practicable by the I

use of engineered controls (containment, ventilation, etc.). When establishing radiological controls for work involving potential airbome radioactivity, the first consideration should be to use techniques which will prevent airborne radioactivity and maintain loose surface contamination in controlled areas to as low as reasonably achievable levels.

1.3 REFERENCES

l 1.

Title 10, Code of Federal Reculations, Part 20. " Standards foc Protection Acainst Radiation."

l 2.

NES," Surface Contamination Program.

3.

L.A. Cume. " Limits for Qualitative Detection and Quantitative Determination,"

1968.

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FORM #NES 205 7/90

g DOCUMENT NO.

32Acnr 5m NUCLEAR ENERGY SERVICES PAGE OF u

e

2. LIMITS FOR AIRBORNE RADIOACTIVITY 2.1 FEDERAL LIMITS Radionuclide concentrations in air are the limited by the Code of Federal Regulaticio, Title I

10, Part 20 (10 CFR 20), for work in controlled areas. Exposure for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week throuchout the year to any of these concentrations will be approximately equivalent to 5 e per year of whole body radiation exposure.

3. MONITORING FOR AIRi10RNE RADIOACTIVITY l

3.1 ROUTINE AIR SAMPLING 3.1.1 c tmoline Technioues b

Routine air samples shall be collected with a both low and high volume portable air samplers with appropriate filter papers. Hich volume air samplers will be run for a I

minimum of 5 minutes and low volume air samples for a minimum of 10 minutes for adequate collection, as determmed by the Radiciogical Controls Supervisor.

I Personnel (lapel) a'r samplers will be used, as required, when deemed necessary by t

the Radiological Controls Supervisor.

The sampler head shall be placed as close to the work area as possible and within the breathing zone of the workers in order to best collect a sample that is representative of th. air that the workers are breathing. The location for air samples shall be based on the type of work being performed (e.g., grining) and the containment enciasure arrangement used. The radiolocical controls supervisor will ensure that the air-sample is collected from the proper location.

Care should be taken to avoid contamination of the air sampler or filter while in use.

Such contamination would be falsely interpreted at airbome contamination.

3.1.2 Samoline Frecuencies I

The frequency for air sampling will conform to the following:

1.

At least every four hours in occupied spaces, if the air particle detector in that space is required to be operanve but is inoperative.

mm wuns mn

DSCUMENTNO, 82A8037 NUCLEAR ENERGY SERVICES PAGE 6

op 16 l

2.

At least every four hours in (1) radiological facilities when radioactive work 1

is performed,(2) during radioactive work which has been known to cause or l

is expected to cauc-airborne mdioactivity, and (3) in occupied areas where surface contamination exceeds the limits of Reference 3. These portable samples are not required if continuous monitoring is performed. Continuous monitoring shall be performed according to an approved procedure. If the installed continuous air particle detector for a ventilation exhaust is I-inoperative and adioactive work is being performed, portable sampling every four hours is required.

I 3.

When opening a radioactive system to the atmosphere fer naintenance.

However, portable air samples are not required during normal liquid sampling operations or when opening the system into a containment enclosure equipped with a high efficiency filter.

.I 4.

Before initially entering tanks or voids containing potentially radioactive piping.

5.

Whenever airborne radioactive levels above the limit of Section 2 are suspected.

3.1.3 Countine Air Samples l

b The air samples will be counted on the smear counter (e.g., Ludlum 2929 or equivalent) to determine gross alpha and beta / gamma airborne radioactivity levels.

Air sample results will be entered onto the Air Sample Log Sheet (Figure 2) and the Gross Alpha / Beta Analysis of Air Particulates Analysis Data Sheet (Figure 3).

The minimum detectable count mte (MDCR) is the smallest count rate that has a -

-l 95% probability of being detected. The minimum detectable concentration (MDC) is the MDCR corrected by the factors needed to convert sanrple counts per minute (cpm) to concentration units. Both the MDCR and MDC will be calculated as illustrated in Figure 1 and recorded on the data sheet in Figure 3.

l The quantity of self-absorption by the air sample filter depends on the type of radiation involved, the type of filter used, and th, quality of the air being sampled.

The conversion factor on the Analysis Data Sheet in Figure 3 assumes an alpha self-absorption factor of 1.5.

That is. the measured activity concentration is

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FOR D #NES 205 7/90

l DOCUMENT NO, 82A8037 NUCLEAR ENERGY SERVICES PAGE 7

OF 16 l

increased by a factor of 1.5 due to the expected absorption of alpha particles within the air sample filter No significant self-absorption is assumed to occur for -

Ll beta / gamma emitters.

3.2 ENVIRONMENTAL SAMPLING NES shall monitor and record airborne particulate radioactivity by using a portable air sampler. The frequency of air sampling shall be as necessary.

NES shall use a regulated air sampler (e.g., Eberline RAS-1.), or equivalent, with 47mm glass fiber filter paper for environmental monitoring.

NES shall count the sample filters using a low background gas proponional counter, or I

gamma spectrometry system, depending on the type of analysis needed.

g.

33 RECORDS AND REPORTS All records of airborne radioactivity surveys required by the Airborne Radioactivity Program shall be maintained neatly, retained by NES and tumed over to the client at the end of the job. In addition.copics of all records will be provided to the client's representative, as appropnate. These records shall include at least the following information:

A.

Date and time of measurement.

B.

Location C.

Reason for measurement.

D.

Instrument used or equivalent E.

Results of most recent response check and background radiation level when survey meters are used for measuring portable samples I

F.

Airborne radioactivity in pCi/ml.

l G.

Remarks.

H.

Signature of surveyor.

1.

Signatures of persons reviewing recork A report of any incident involving high airborne radioactivity other than fallout or natural background in areas occupied by personnel not wearing respiratory equipment shall be sent

I FOQM #NES 205 7/90

DOCUMENT NO.

82A8037 NUCLEAR ENERGY SERVICES PAGE R

OF 16 to the client within ten days. He incident will be investigated as to the cause of the high airbome, immediate actions taken, methods to prevent a future ocemrence, and results of l

internal monitoring of personnel involved.

An incident report shall also be conducted in cases where workers are exposed to concentrations of airbome radioactivity which exceed the protection - provided by respiratory protection equipment being worn.

3.4 CALIBRATION The calibration of the air sampling equipment will be done in accordance with the I

appropriate operation and maintenance manual, or an approved procedure.

The calibration /re-calibration of the air sampling equipment will be done annually and after instrument repair by a RCT.

NES will maintain calibration certificates as part of the permanent project file.

4. CONTROLLING AIRBORNE RADIOACTIVITT 4.1 PERSONNEL EXPOSURE Personnel exposure to airbome rad 20 activity is controlled using contamination containments, ventilation systems, and respiratory equipment. When workinF n areas with i

l high levels of surface contamination (e.g.,22.000 dpm/100 cm2 beta / gamma or 1100 dpm/100 cm2 alpha) respiratory equipment will be used because of the likelihood that this surface contamination could become airborne. This requirement may be waived depending on the radiological conditions by agreement of the Radiological Controls Technician and Radiological Controls Supervisor.

I s

Contamination contamments shall be used to the maximum extent practicable to prevent personnel from being exposed to airbome radioactivity above the limits of Section 2.1.

These containments are required during radioactive work which has been known to cause or is expected to cause airborne radioactivity.

Personnel shall wear respiratory equipment in accordance with Section 4.2 in areas where airbome radioactivity exceeds the applicable limit of Section 2.1.

Signs shall be posted at entrances to areas where respiratory equipment is required. This requirement to wear respiratory equipment also shall be included on a sign with the anti-contamination clothing requirements.

I FO;M #NES 205 7/90

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_l When personnel not wearing respiratory e'f ) ment are likely to be exposed to airborne radioactivity above a limit in Section 2.1, a ventilation system shall be operated which will remove airbome particulate radioactivity to a controlled ventilation system or other system with a high efficiency Siter. For example, during such operations as machining contaminated surfaces, vacuum cleaners fitted with high ef5ciency filters, portable exhaust blowers fitted with high efnciency filters, or flexible ducts connected to a filtered ventilation exhaust shall take suction from within about one foot of the work. Experience I

has shown that some operations within containments, such as grinding on highly contaminated components, require exhausting the containment through a ventilation system with an installed high efficiency Elter, such as by using a vacuum cleaner, to prevent high airborne radioactivity outside the containntent.

High ef6ciency particulate air (HEPA) filters shall be installed in the ventilation exhaust from radiological facilities in which work which could cause airbome radioactivity is in progress to preveat discharge of airbome radioacuvity to the environment.

HEPA filters shall oe installed in the exhaust from contamination containments to prevent I

personnel from being exposed to high airborne radioactivity.

HEPA filters shall be installed in vacuum cleaners used around loose surface contamination.

HEPA ventilation exhaust filters are m required if all radioactive work that could cause airbome radioactivity greater than a limit of Section 2.1 is performed within a contamination containment enclosure.

Monitoring for airbome radioactivity shall be performed in accordance with Section 3.1.

As shown in Table 1 (Ref. 2). full-face filtered air respirators will be worn by personnel when the alpha airbome concentration is greater than IE-Il pCi/ml or when the beta / gamma airbome concentration is greater than IE-10 Ci/ml.

Full-face supplied air respirators or hoods will be wom by personnel when the alpha airbome concentration is greater than 5E-10 pCi/ml or when the beta / gamma airborne concentration is greater than 5E-9 pCi/m!.

Personnel will a be allowed to enter into areas when the alpha airborne concentration is greater than 2E-8 Ci/mi or when the beta! gamma airbome concentration is greater than 2E-7 pCi/ml.

FORM #NES 205 7/90

DOCUMENT NO.

82A8037 NUCLEAR ENERGY SERVICES PAGE 10 OF 16 If personnel entry is required to these areas, containment or filtered ventilation will be used to reduce airborne radioactivity levels to below 1,000 times trie limit of Section 2,1.

l 4.2 RESPIRATORY PROTECTION 4.2.1 General I

NES management personnel who have subordinate personnel working in controlled

- I areas art. sponsible for maintaining concentrations of airborne radioactivity below the established limits in Section 2, The RCT will provide technical direction in placement and type of contmuous and periodic air sampling equipment required to I

detect and evaluate the levels of airborae radioactivity in work areas.

The respiratory pro.ection program is the responsibility of the Radiological Controls Supervisor (RCS). The RCS' responsibility is to implement the program.

Respiratory protection equipment requirements will be specified.

Airbome radioactivity concentrations shall be minimized to the extent practical by the use of engineereo controls (containment, ventila: ion, etc.). When establis! ting radiological controls for work involving potential airborne radioactivity, the first consideration should be to use techniques which will prevent airbome radioactivity and maintain loose surface contamination in controlled areas to as low as reasonably achievable levels.

I-4.2.2 Wearine Reseiratorv Protective Eauiement When airborne radioactivity concentrations-exceed the limits in Section 2.1, respiratory equipment muw be used to protect personnel, The protection factor for a full-face filtered air respirator is -50. As shown in Table 1, full-face filtered air respirators will not be worn in airborne concentrations greater than 50 times the

. alpha or beta-gamma limit.

In situations where airborne concentrations of radioactive material exceeds the

(

stated concentration guides for filtered air respirators in Table 1, the supplied air respirator will be used. An air supply system will be used by NES to provide breathing air, As shown in Table 1, supplied air respirators will not be worn in airbome concentrations Freater than 2,000 times the alpha or beta-gamma limit.

The protection factor for particulates, gases, and vapors ariorded by a continuous flow or pressure demand, full-face supplied air respirator is 2,000.

F;"M WNES 205 7/90

1 Lg-DOCUMENT NO.

82A8037 NUCLEAR ENERGY SERVICES PAGE 11 0F 16 As shown in Table 1, no other respiratory equipment will be used at airbome concentrations 2,000 times the limit of of Section 2.1.

All respirators will meet NIOSH/MS A approval.

4.2.3 Rgmiratory Pmtection Maintenance Promm Al.1 respirators will be maintained in accordance with the manufacturer's recommendations for repairs, cleaning, and disinfection.

All respirators and auxiliary equipment will be surveyed after cleaning by a RCT prior to packaging for issue. All respirators will be decontaminated by an RCT prior to packaging.

Prior to packaging a respirator, the RCT will inspect the respirator for damage and will seal it in a plastic bag for personnel issue.

I The RCS will issue respirators only to respirator qualified personnel.

The air supply system will be inspected by the RCT prior to use.

4.2.4 Remiratory Protection Trainint' Premm Trainiiig is provided to all respirator users and individuals who airect the work of l-users in respirators. The training is conducted by NES.

The individual conducting tne r spitatory protection program training is a qualified and experienced instructor with a thorough knowledge of the application and use of respiratory protective equipment and the hazards associated with radioactive l

airbome contaminants and experience in selection and use of respirators.

The training is provided annually at appropriate times to maintain a high degree of

I proficiency. Training and fitting records will be maintained by Radiological Controls personnel.

'j 4.3 USE OF HIGH EFFICIENCY PARTICULATE AIR FILTER l

Systems containing high efficiency paruculate air (HEPA) aall be at least 99.957o efficient for filtration of 0.3 micron dioctvlphthalate (DOb r ucelates.

l HEPA filters shall be 99.97Fc efficient.

l FORM #NES 205 7/90

F DOCUMENT NO, ' DAM 037 L

NUCLEAR ENERGY SERVICES PAGE 12 OF 16 F

Il The following requirements for venulanon system high ef6ciency particulate air filters l,

apply:

A.

IIEPA filters shall be purchased to specificanons at least equivalent to Military Specification Mll.-IL51068 senes, " Filter Particulate, liigh Efficiency, Fire l

Resistant".

11.

The llEPA filters are fragile. Any penetrahon of the media is a direct opening from one side of the filter to the other. Therefore,llEPA filters shall te handled carefully.

C.

Great care shall te used in installing IIEPA filters to ensure the filter material I

separutors are in the vertical position, tight seals are made around the edges of the filters, and that filters are not damaged dunng installadon.

D.

liccause slicht damage can greatly reduce their efficiency, llEPA filters shall te inspected befort installation by esreful visual examination. Af ter installation, the filter system shall be tested and ne equal to or greater than 99.95% efficient for 0.3 micron particles.

E.

hstalled IIEPA filters in use shall be DOP tested annually. If a filter installahon coes not pass the DOP test sausfactorily, the cause of leakag shall be determined and conected prior to further system operation.

F.

A IIEPA filter shall be replaced when: (1) the pressure drt vemy.t e.vceds the limit specified for the filter, (2) the flow of air from the system it ativices is redwed so as to ineffectively exhaust an area, (3) the extemal gamma raa aion le* cl f' the filter exceeds allowable radiadon levels in the area in which the filter is lac, or (4) the filter is damaged.

I FORM #NES 205 ?/90

p DOCUMENT NO. - g n rnt-NUCLEAR ENERGY SERVICES PAGE M

OF M

l FIGURE 1

/

MDC/51DCR CALCULATIONS A.

h1DCR CALCULATION:-

I h I' l

h1DCR = @h NB NH

& 3.29 I( Tn Ts j

+

l l

where:

h1DCR minimum detectable count rate (cpm)

=

R9 background count rate tcpm)

=

Ta background count time (min) r

=

Ts sample count time (mini

=

NOTE. These equations ensure that h1DCR is calculated at the 95Ce confidence level.

B.

hiDC CALCULATION -

MDC=

MDCR (V)(EcK2.22E6)

I where:

hiDC minimum detectable concentration (pCi/ml)

=

V air sample volume in ml

=

l Ec counter efficiency (decim:tl form) a 2.22E6 conversion t' rom dpm to pCi

=

NOTE: If the sample net count rate is less than h1DCR and the volume is at least 1,0E6 mi, enter "< h1DC"in the log book. lf the sample net co int rate is less than h1DCR and the sample volume is less than 1.0E6 ml, recalculate h1DC using the actual sample volume.

I i

2 Based on statistical concepts presented bv L.A. Currie in Ref. 3.

I I

FORM #NES 205 7/90

DOCUMENT No, _ g7Agn3-NUCLEAR ENERGY SERVICES PAGE_

u op a

l FIGUl(E 2 Allt SAMI'LE 1.OG SilEET ACTIVITY RECOUNT ACTIVITY I

DATE SAMPLE TIME LOCATION DATE/ TIME ALPHA BETA ALPHA DETA I

I I

l l

l I

I I

I I

I I

I I

I l'I I

I I

\\

\\

I FORM #NES 205 7/90

-. + -,,

--.-m m

I I

g DECUMENT No.

99 A Rh?

j 3 NUCLEAR ENERGY SERVICES PAGE H

OF 16 l

FIGURE 3 GROSS ALPilA/DETA ANALYSIS OF AIR PARTICULATES ANALYSIS DATA SilEET

)

SAMPLING DATA SAMPLE NO.:

g Locatior'.

Reason:

Collecti.'t gle Sampler ID:

Date/ Time On:

Flow Rate (CFM) On:

Date/ Time Off:

Flow Rate (CFM) Off:

l COUNTING DATA ALPHA BETA Countino System I

I Serial Number Countina Date/ Time 1

Gross Counts Samole Count Time (Min)I I

Gross Counts (com)

Backaround counta I

Bko Count Time (Min)

Bka Counts (com)

I Net Counts (com)

Counter Ethciency ConversiortFactorv ac:

6.76 E;7 6.76 E-7 6.76 E47 "4SE 7" c 4.5 E:7 m 45 E:7 l

Volume (ml)

ActMtv (uCi/ml)

MDCR (com)

MDC (uCi/ml)

I l

Comments:

Technician:

Date:

Reviewed by:

Date:

NOTE: (ft3)(2.83E4) = ml l

Activity (uCi/m/ ) = (Net com) (Conv. Factor)/(Counter Eff) (Vol mi )

FcRM NNES 205 7/90

M M

M M

M M

. B,

a E

G TAllI.E I i

5 REQUIRED RESPIRATORY l'ROTECTIVE DEVICES 5

a Type of Concentration Guide 1.irnit 8 Type of Radioactivity in ttCi/cc Ikvice z

C O

Alpha Einitters a.

O to 1 x 10-11 a.

None required Q

b.

>lx10-33 to 5 x 10-10 b.

Full-face filtered g

air respirator fprotection factor of $01 g

o c.

>5 x 10- 1" to 2 x 10 8 Full-face supplied us c.

air respirator (protection factor of 2(MMy

$So d.

>2 x 10 x d.

None anowed - no curry Heta/(lannina limitters a.

O to 1 x 1831" Nonc resp:; red a.

T U

0 b.

> 1 x 10-30 o 5 x 10 9 b.

Full-face filtered g

t air respirator (protection factor of 50) l g

m

>5 x 10-9 o 2 x 10J t

c.

Full-face supplied

<5 k

i t

c.

z air respirator (protection factor of 2(XXI)

.o j

d.

>2 x 104 I

o n

d.

None allowed - no entry r

.j 1 Dased on 10 CFR 20 Appendix B liinits and the protection factors of 10 CFR 20.

5 U

DOCUMENT NO.

R?ARn17 NUCLEAR ENERGY SERVICES PAGE Al OF _Ain l

APPENDIX A AIRilORNE SAFETY ASSURANCE PROGRAM

1. SCOPE I

The Airbome Safety Assurance Program has been established to provide protection against airborne hanrds and to provide the basis of all training and record keeping necessary to ensure that safety.

l

2. GENERAL The following program is excerpted from the corporate Occupadonal Health Manual. Section 17.

I This program is in compliance with the requirements of the federal Occupational Safety and Health Administration (OSHA) and incorporates the guidelines of the Amencan Nuclear Standards Institute ANSI-Z88.2. Exposures of workers to airoome radioactive matenals in restncted areas shall follow the guidelines of Regulatory Guide S.I.%

I

3. RESPIRATORY PROTECTION PROGRAM 3.1 RESPIRATORY PROTECTION REQUIREMENTS I

The Occupational Safety and Health Administration has set maximum exposure standards for many airbome toxic matenals. If employee exposure to these substances exceeds the standard, federal law requires that feasible engineering controls and/or administrative I

controls be installed or instituted to reduce employee exposure to acceptable levels. If these controls do not prove feasible, or while they are being installed / instituted, NES shall provide appropriate respiratory protection for employees.

Respiratory protection is also necessary for routine but infrequent operations, non-routine I

operations in which the employee is exposed briefly to high concentrations of a hazardous substance, e.g., during maintenance or repair activities, or during emergency conditions.

3.2 RESPIRATORY PROTECTION PROGRAM Providinc respiratory protective equipment to the employee, however,is only one aspect of NES' responsibility pertaining to the use of respiratory protective equipment as a control measure. A respiratory protection program must be implemented.

FOIM WNES 205 7/90

I DOCUMENT NO.

M ARnD g

NUCLEAR ENERGY SERVICES PAGE A'

OF_ Ain 3.3 RESPIRATORY PROTECTIVE EQUIPMENT SELECTION I

Respirator selection is critical to an effcctive program. The proper selection of respiratory protective equiptnent involves three hug steps:

l 1.

The identification of the hazard.

2.

The evaluation of the hazard.

I 3.

The selection of the appropriate appmved respiratory equipment based on the first two considerations.

3.4 IDENTIFICATION AND EVALUATION OF THE HAZARD Identification and evaluation of the hazard forms the basis for a decision on the need for the respiratory program. If a survey of operations and work environments indicates that no employees are being exposed to contamment concentrauons exceeding established limits (OSHA standards) then a respirator program is not required, in-house evaluation with an industrial hygiene sutvey may have indicated the need for respiratory protection equipment.

This applies to both radiological and non-radiological hazards.

A walk-through survey of the worksite to identify processes, or worker environtnents where respirators may be required, is the next step in the respirator selection process.

3.5 APPROVED RESPIRATORY PROTECTIVE EQUIPMENT When purchasing respiratory protective equipment, be sure to purchase anoroved equipment for the particularcontainment. An approved respirator is one that has been tested and found to meet minimum performance standards by the Mine Safety and Health Administration and the National Institute for Occupational Safetv and Health (NIOSH).

A NIOSH approved respirator contains the following:

1.

An assigned identification number placed on each unit, e.g., TC-21C-101, 2.

A label identifying the type of hazard the respimtor is approved to protect against.

I 3.

Additional information on the label which indicates limitations and identifies the component parts for use with the basic unit.

- FORM 8NES 205 7/90

j DOCUMENT NO.

e Arnt'

' NUCLEAR ENERGY SERVICES PAGE A1 0F Ain 3.6 ISSUANCE OF RESPIRATORY PROTECTIVE EQUIPhiENT Where practical, the user should be given respiratory protective equipment for his/her exclusive use. A record of issuance shall be maintained. Any respintor permanently assigned to an individual shall be permanently marked to indicate to whom it was assigned.

3.7 ITITING OF RESPIRATORY PROTECTIVE EQUIPh1ENT I

It is essential that respiratory protective equipment be properly fitted to the employee when it is issued. For that reason. NES shall provide seveml respirators from which to choose.

There are two types of fitting tests - qualitative and quantitative tests. Qualitative tests are fast, usually simple, but not as accurate an indicator of improper fit as the quantitative test.

The quantitative test requires testing equipment setup and a specially trained operator.

Two qualitative fit tests, the positive pressure fit test and the negative pressure fit test, can be I

used as a quick check of the fit of the respirator facepiece before beginning or during work in the hazardous atmosphere. These tests would apply only to air-purifying respirators.

g Facial hair lying between the sealing surface of a respirator facepiece and the wearer's skin will prevent a good seal. Beards and sideburns can prevent satisfactory sealing and shall be I

removed prior to respirator use. The negative pressure developed in the facepiece of non-powered air-purifying respirators during inhalation can lead to leakage of contaminants into the facepiece when there is a poor seal. Individuals who have stubble -

even a few days' growth may permit excessive leakage of containment. - a moustache, sideburns, or a beard that passes between the skin aad the sealing surface shall not wear a respirator.

Industrial safety glasses may cause a fitting problem, if they interfere with the seal.

I Contact lenses shall not be worn while wearing a trspirator. A properly fitted respirator I

(primarily a full facepiece respirator) may stretch the skin around the eyes, thus incitasing the possibility that the contact lens will fall out. Contaminants also penetrate the respirator clouding soft lenses and may cause severe discomfort.

3.8 h1AINTENANCE OF RESPIRATORY PROTECTIVE EQUIPh1ENT On-going maintenance of respiratory protective equipment is an important part of the program. Wearing poorly maintained or malfunctioning equipment may be as dangerous as not wearing a respirator.

I FK,M NNES 205 7/90

DOCUMENT NO, re-I NUCLEAR ENERGY SERVICES PAGE u

op _ A!n While OSilA places a strong emphasis on inc importance of an adequate maintenance program, it does permit the tailoring of the maintenance program to the type of plant and l

hanrds involved. All maintenance programs should follow manufacturer's instmetions and should include provisions for:

Cleaning and disinfecung of equipment Storage Inspection for defects Repair Cleaning and disinfecting -

When respirators are used daily for several hours, they should be cleaned and disinfected daily. When they are used occasionally, periodic cleaning and disinfecting is appropriate. Individual workers who maintain their own respirator l

should be trained in the cleaning of respirators.

Respirators should be washed in a detergent containing a bactericide. To prevent dermatitis, the respirators should be rinsed thoroughly in clean water. Dry on an open rack.

Storage -

After cleaning and drying the respirator, it should be placed in a rescalable plastic bag. A wall-mounted cabinet or an employee's locker shelf is appropriate for storing when not in use.

Repair -

Replacement of pans and repair of air-purifying respirators should,in most cases, present little problem. Replacement parts must be those of the manufacturer of the equipment and repairs made by qualified individuals.

NOTE: REGULATIONS REQUIRE SELF-CONTAINED BREATHING APPARATUS EQUIPMENT BE RETURNED TO THE MANUFACTURER-FOR ADJUSTMENT OR REPAIR.

l F;ZM WNES 205 7/90 -

I DOCUMENT No.

22A?n

NUCLEAR ENERGY SERVICES I

PAGE u

OF A!n l

Inspecuon -

An important pan of a respirator maintenance program is the inspection of the devices. If performed carefully, inspections will identify damaged or malfunctioning repairs.

All respiratory protective equipment must be inspected -

before and af ter each use; and during cleaning.

Equipment designated for emergency use must be inspected -

after each use during cleaning; and at least monthly.

3.9 RECORD KEEPING-INSPECTION l

A record must be kept of inspection dates and findings for resrirators maintained for emercency use.

l Listed below are some of the primary defects to look for in inspection of the components of the respirator. When appropnate. informanon within the parentheses are suggestem actions l

to be taken.

1.

Disposable respirator-check for:

- holes in the air filter (obtain new disposable respirator).

- straps for elasticity and deterioration (obtain new disposable respi-rator).

2.

Air-purifying respirators Rubber facepiece-< heck for:

excessive din (clean all dirt from facepiece) cracks, tears or holes (obtain new facepiece)

I

- distortion (allow facepiece to " sit", free from any constraints and see if distortion disappears; if not, obtain new facepiece)

I FCM NNES 205 7/90

I D2CUMENT NO.

. gnpu -

g NUCLEAR ENERGY SERVICES PAGE u

0F _.,ge lleadstmps-check for:

breaks or tears (replace headstraps) loss of elasticity (replace headstraps) broken or malfunctioning buckles or attachments (obtain new parts)

I Inhalation valve. exhalation valve-check for:

detergent residue, dust panicles, or dirt on valve (clean residue with soap and water) missing, damaged or defective valve cover (obtain valve cover from manufacturer)

I Filter element (s)-check for:

- proper filter for the hazard

- approval designation missing or worn gaskets (order replacement) worn threads (replace filter or facepiece, whichever is applicable) cracks or dents in filter housing (replace filter)

4. RESPIRATORY PROTECTION EVALUATION Two imponant aspects of the respirator program are the periodic surveillance of the work areas requiring usage of respirators.and an evaluation of the overall respirator program for effectiveness.

Many things such as changes in operation or process, implementation of engineerine controls, temperature, and air movement can affect the concentration of the substance (s) which originally l

required the use of respirators. To determine the continued necessity of respiratory protection or l

need for additional protection. measurements of the contaminant concentration should be made

.whenever the above changes are made or detected. A record of these measurements shall be kept.

l'

= FORM #NES 2e5 W90

I DUCUMENT NO. _.g2Ayne NUCLEAR ENERGY SERVICES PAGE

(,

OF _ i!n E

The following are quesdons to be answered by the Radiological Controls Supervisor (RCS) when the program is evaluated, at least annually - or when changes are made in its implementation.

1.

Is program responsibility vested in one individual who is knowledgeable and who j

can coordinate all aspects of the program?

2.

What is the present status of the implementation of engineering controls. if feasible, to alleviate the need of respirators?

3.

Are there written crocedures covenne the various asocets of the reroirator crocram?

4.

Are work area condidons and employee exposures properly surveyed?

l 5.

Are respirators selectea on the basis of hazards to which the employee is exposed?

6.

Are selections made by individuals knowledgeable of selecdon procedures?

7.

Are only approved respirators purchased and used and do they provide adequate protecdon for the speciBe hn7ard nnd concentration of the contaminant?

8.

lias a medical evaluadon of the prospective user been made to detennine ability to wear respiratory protective equipment?

9.

llave respirators been issued to the users for their exclusive use, and are there

n. cords covering issuance?

10.

Is the best fitting respirator issued?

11.

Is the fit tested at frequent intervals?

I 12.

Are those users who require corTective glasses properly fitted?

13.

Are users prohibited from wearing contact lenses when using respirators?

14.

Are respirators cleaned and disinfected after each use or as frequendy as needed?

15.

Are proper methods of cleaning and disinfecting utilized?

16.

Are respirators stored properly?

17.

Are respirators inspected before and after each use and during cleaning?

FORM WNES 205 7/90

DOCUMENT NO. mAgnt-NUCLEAR ENERGY SERVICES I

PAGE A9 0F aan 18.

Are qualified individuals / users ins:ructed in inspection techniques?

19.

Is replacement or repair only done by experienced persons with pans daigned for I

the respirator?

20.

Are workers tniined in proper respirators usage and care?

4.1 hiEDICAL PROGRAhi FOR RESPIRATOR USER So that the examining physician can render a qualified opinion regarding respirator usage by an employee, the physician, initially, should be given the following information:

- Type of equipment to be used.

Tasks that the employee will perform while wearing the respirator.

- Length of time the user will wear the equipment.

Substance to which the employee will be exposed.

The following medical tests should be considered by the examining physician in the evaluation:

Pulmonary function test.

Eye test.

- General physical exanunation.

Electrocardiogram.

4.2 hiEDICAL FACTORS 4.3 hiedical factors to be considered by the examining physician in determining the prospective user's ability to wear a respirator are:

- Emphysema.

Asthma.

Chronic bronchitis.

Hean disease.

Deep facial scars.

Poor eyesight or hearing.

Lack of use of fingers or hands.

Claustrophobia.

Lack of teeth or dentures.

4 m

FKM #NES 20$ 7/90

DOCUMENT NO. __gare I

NUCLEAR ENERGY SERVICES PAGE Ao 0F

• In 4.4 Ti!E FTITING OF RESPIRATORS I

For safe use of any respiratory protective device. it is essential that the user be properly instructed in its use. Supervisors as well as workers must be so instructed by competent persons.

OSilA requires that all employees be trained in the proper use of the device assigned to them.

Each respirator wearer should be given training which would include:

an explanation of the respiratory hazard and what happens if the respirator is not a.

used properly.

I b.

a discussion of what engineering and ad'ninistradve controls are being used and why respirators still are needed for protection.

an explanation of why a particular type of respirator has been selected.

c.

d.

a discussion of the function, capabilities, and limitations of the selected respirator.

instruction in how to don the respirator and to check its fit and operanon. instruction c.

I in the proper wearing of the respitator.

g.

instrucuon in respirator maintenance.

h.

instruction in recognizing and handling emergency situadons.

Supervisory personnel should periodically monitor the use of respirators to insure that they are worn and maintained properly.

I The employee. sing the respirator tests it for fit each time it is put on. The respintor tit can be checked by one of the following methods:

Positive Pressure Test:

Close the exhalation valve and gently exhale into the facepiece. The facepiece fit _is considerrd satisfactory if a slight positive pressure can be built up inside the facepiece without any evidence of outward leakage of air at the seal. For most respirators, this method of leak testing requires that :he wearer first remove the exhalation valve cover and then carefully replace it af ter the test.

I

~:M WNF A ?M 7/90 FO

DOCUMENT NO. mgn -

NUCLEAR ENERGY SERVICES I

PAGE un OF A, l n Negative Pressure Test:

Close off the inlet opening of the canister or cartridgets) by covering with the palm of the I

hand (s) or by replacing the seal (s). Inhale gently so that the facepiece remains in its slightly collapsed condition and if no inward leakage of air is detected, the fit of the respirator is considered satisfactory.

Stannic Chloride Smoke Test:

The most frequently used qualitative fit test is the irntant smoke test. An irritant smoke tube l

(glass tube 12cm long by lem diameter, filled with stannic chloride-impregnated pumice) is used to produce a very imtating smoke w hen air is blown through the tube. The smoke is directed at the facepiece seal and leakage is indicated by irritation of the throat and lungs. If the respirator does not fit properly, the trntatmg " smoke" will be inhaled and the wearrr will cough or sneeze involuntarily. The fact that the fit test is measured by an involuntary reaction on the part of the wearer makes this test more acceptab!c.

To carry out this test in a " controlled" condition a large plastic bag can be hung from the ceiling and the wearer can step under it. The respirator wearer should close his ;yes during the fit test. Light puffs of smoke can be introduced into the top and side of the plastic bag away from the wearer's face. If there is no evidence of leakage, the smoke tube should be held closer to the wearer's face and smoke density increased. Any time leakage is detected, the tester should stop and the wearer should adjust the facepiece and head straps of the respirator. NOTE: Only 3 or 4 puffs of" smoke" are required. CliARCOAL FILTERS must be used on the respirator for this test.

I I

I FOCM WNES 205 7/90

I I

i g

APPENDIX B Soil Stunple Preparation f

for Gannua Spectroscopy I

I I

I I

I

~

L I

PAGE OF h

I l

SOIL SAMPLE PilEPARATION

'FOR GAMMA SPECTROSCOPY I

I I

I a

E Project Applicanon Copy No.

Assgneo io l

APPROVALS TITLE / DEPT. - SIGNATURE - DATE REV NO PREPARED BY REVIEWED BY APPROVED BY DIRECTOR.

PROJECT MGR.

DEPT. MGR.

OPERATIONS 0

(w 0k+kewt

?

a 1

2 a

E a

E 5

I 7

Ia 10 11 luw.....

m

82As 26 R

" C "" -

311EL4,-ee EVISION LOG mevme.,,,c.

I

,ajg P,jjE D E S C RIP TION APPROVAL DATE I

I I

I I

i I

i I

I l

I l

I

.I I

I i

I i

I I

I i

j t

i i

.i I

i g _....

DOCUMENT NO.

82A8026 NUCLEAR ENERGY SERVICES PAGE 3

op 7

TAllLE OF CONTENTS IMGE 1.

PURPOSE 4

2.

RESPONSIBILITIES 4

3.

PROCEDURE 4

I 3.1 Prerequisites 4

g 3.2 Equiptnent and Materials 4

3.3 Soll Standard Preparation 5

3.4 Vendor Laboratory Sample Preparation 5

3.5 Sample Preparation 5

3.6 Dackground Determination 6

3.7 Soll Analysis 6

4.

RECORDS 6

5.

REFERENCES 7

I P

I lI I,.

a, s,,,,

i I

DOCUMENT NO.

82A8026 NUCLEAR ENERGY SERVICES 4

7 PAGE OF I

1. PURPOSE I

The purpose of this procedure is to identify the steps required in preparing a soil sample for analysis.

2. RESPONSIBILITIES I

It is the responsibility of the Site Health and Safety Officer or his designee to canare implementation of this procedure, it is the responsibility of the NES Laboratory Technician to perform sample preparation with care and in accordance with Jiis procedure.

I

3. PROCEDURES 3.1.

PREREQUISITES l

3.1.1. Samples are collected in accordance with the NES Soil Sampling Procedure.

I 3.1.2. Soil will be surveyed for alpha and beta-gamma contamination prior to removal from the drilling area.

l 3.1.3. Soil will be placed in a p.astic bag or other scalable container and marked.

3.2.

EQUIPMENT AND MATERIALS I

3.2.1. Mortar & Pestle 3.2.2. Metal Pans 3.2.3. Drying Oven 3.2.4. Scale 3.2.5. Sieves 3.2.6. Ottawa Sand 3.2.7. 1 Liter Marinelli Beakerts)

I,em._ees..

DOCUMENT NO, 82A8026 NUCLEAR ENERGY SERVICES PAGE 5

_op 7

I 3.2.7. 1 Liter Marinelli Beaker (s) 3.2.8. Canberra liPGe System 3.3.

SOIL STANDARD PREPARAT10N 3.3.1. Weigh an empty I liter Marinelli beaker and lid. Lug the weight.

3.3.2. Fill the Marinelli beaker from 3.3.1 with Ottawa sand and cover it.

3.3.3. Weigh the beaker with the sand and log that result.

3.3.4. Subtmet the weight of the empe ocakerin 3.3.1 from the weight of the full beaker in 3.3.3 to detennine the weight of the Ottawa soil standant.

3.4.

VENDOR LABORATORY SAMPLE PREPARATION OF NEEDED) l 3.4.1. Weigh out 50-100 grarns of soil (depending on the original sample size).

3.4.2. Remove all rocks exceeding I cm in size.

3.4.3. Place the soil into a sieve to remove other large material (e.g.; stones the size of gravel or larger).

3.4.4. Place the sieved soil into a plastic container.

3.4.5. Label the container with the core number and sample date.

l 3.4.6. Log the sample numbers in the laboratory log book and send the sample (a group of samples) to the laboratory.

3.5.

SAMPLE PREPARATION 3.5.1 Remove all rocks exceeding i em in diameter.

3.5.2. Place the soilinto a metal mixing pan.

3.5.3. Place the pan of soilinto tairying oven and heat at about 150-175' C until soil is dry, l.

3.5.4. Place the soil into a mortar and crush / grind it with the pestle.

3.5.5 Mix the soil.vell.

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3.5.6. Weigh the remaining soil and log the weight 3.$.7. If the soil quantity from 3.5.6 is not enough to fill the Marinelli beaker, Ottawa sand l

will be added to the sample.

3.5.7.1. To add Ottawa sand:

A.

Weigh out enough Ottawa to fill the remaining Marinelli space.

B.

Place the Ottawa sand with the soil sample into a large mouthed container or bowl.

C.

Stir the mixture until homogeneous.

D.

Place the homogeneous mixture into the Marinelli beaker and seal l

the beaker.

3.6.

BACKGROUND DETERMINATION 3.6.1. Place the Ottawa sand standard into the HPGe well and count for 600 seconds.

l NOTE: A background determination for the Ottawa sand is needed only once, prior to counting any soil samples. Further background counts are only needed if all power is lost to the counting system and some damage or memory loss has occurred.

3.6.2. Store the background count for use with each soil sample counted.

NOTE: If no background from the Ottawa sand standard is detected, background h

subtraction will not be used. A printout of the background data will be filed with the remaining core bore information.

3.7.

SOIL ANALYSIS So;l samples will be ploced into the HPGe well and analyzed in accordance with NES Procedure Number 82A8024. Gamma Spectral Analysis.

4. RECORDS 4.1.

A hardcopy record from each soil core sample will be maintained in duplicate by the NES Ra M m Controls Supervisor (RCS) until job completion. The RCS will turn the ong!M' twer to the client upon job completion.

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5. REFERENCES I

f 5.1, NES Soil Sampling Procedure I

5.2.

NES Surface Contamination Control and Survey Procedure 5.3.

NES Gamma Spectral Analysis Procedure g

5.4.

Canbena liPGe System. Operators Manual.

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