ML20034F506
| ML20034F506 | |
| Person / Time | |
|---|---|
| Site: | 07000903 |
| Issue date: | 02/28/1993 |
| From: | Abelquist E INTEGRATED ENVIRONMENTAL SERVICES |
| To: | |
| Shared Package | |
| ML20034F498 | List: |
| References | |
| NUDOCS 9303030324 | |
| Download: ML20034F506 (20) | |
Text
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DECOMMISSIONING PLAN I
FOR THE 1
PLUTONIUM FACILITY j
AND MULTIPLE FAILURE BUILDING OF THE NATIONAL PARK SERVICE PROPERTY i
LOCATED NEAR PAWLING, NEW YORK.
FOR CHEVRON USA, INCORPORATED FEBRUARY 1993 PREPARED AND SUBMITTED BY:
INTEGRATED ENVIRONMENTAL SERVICES DIVISION OF NUCLEAR ENERGY SERVICES j
44 Shelter Rock Road Danbury, CT 06810
$030$no!K bo$No3 C
PDR j
I DECOhBfISSIONING PLAN FOR TIE i
PLUTONIUM FACILITY AND MULTIPLE FAILURE BUILDING OF TIE NATIONAL PARK SERVICE PROPERTY LOCATED NEAR PAWLING, NEW YORK t
FOR CIEVRON USA, INCORPORATED Prepared by:
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m Eric W. Abelquist, Project Mana),er l
Approved by:
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<w Dennis W. Reisenweaver, Departnfent Manager t
Approved by:
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i John W ff, Chevron USA, I rated Representative m
TABLE OF CONTENTS 1.
SCOPE 1
II.
SITE CONDITIONS 1
III.
CONTRACTOR RELATIONSHIPS 2
IV.
DECOMMISSIONING PLAN CONTROL SYSTEM 2
V.
PERSONNEL 3
VI.
RADIOLOGICAL PROTECTION 4
VII.
CONTAMINATION CONTROL 4
VIII. RELEASE CRITERIA 5
IX.
QUALITY ASSURANCE 6
X.
WORK TASKS 6
Task 1 - Engineering 6
Task 2 - Obtain Shipping Containers 6
Task 3 - Mobilization 7
Task 4 - Initial Radiological Survey 7
Task 5 - Setup Radiologically Controlled Areas 7
Task 6 - Concrete Decontamination 8
Task 7 - Other Decontamination 9
Task 8 - Preparation / Shipment of Waste 9
Task 9 - Demobilization 9
Task 10 - Prepare Final Reports 10 XI.
RADIOLOGICAL INSTRUMENTATION 10 XII.
SHIPPING AND DISPOSAL 11 1
REFERENCES 12 EXHIBIT A - RADIATION WORK PERMIT EXHIBIT B - IRRITANT SMOKE OR BANANA OIL TEST EXHIBIT C - NEGATIVE PRESSURE TEST FOR TIGHT-FITTING FACEPIECE i
t
I.
SCOPE The purpose of this decommissioning plan is to provide a logical and safe method for the decontamination of the Plutonium Facility and the Multiple Failure Building at the Nuclear Lake Site.
This decommissioning plan is to be used as a guide in performing the building decontamination operations. The building decontamination will consist of remediating the regions of elevated surface contamination as identified in the Oak Ridge Associated Universities (ORAU) radiological report (Ref.1) and the initial radiological survey of the two buildings.
The initial building survey will consist of random d.irect and removable contamination measurements. Specifically, several measurements will be obtained from each floor, wall and ceiling surface within the two buildings. These measurements will be documented on survey forms and will be used as a guide in performing the decommissioning activities. Paint, water and sludge samples will also be collected during the initial radiological survey to assist in the identification of the building areas requiring decontamination.
The overall project has been divided into tasks which are discussed in detail in Section X of this plan.
The goal of this plan is to remove and dispose of the contaminated building materials so that the two buildings may be released for unrestricted use. At the conclusion of the Nuclear L.ake site decommissioning project, a final release survey will be performed within the two buildings to verify that decontamination efforts have been successful in achieving the release criteria. Specifically, building surface contamination levels will comply with the U.S. Nuclear Regulatory Commission (USNRC) guidelines as expressed in Regulatory Guide 1.86 (Ref. 2).
II.
SITE CONDITIONS i
t 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 Plutonium Facility exhibited several areas that had significantly elevated surface contamination and exposure rate levels. The Multiple Failure Building contamination consisted of one small floor area of elevated, fixed beta-gamma surface contamination.
With few exceptions, exposure rates throughout the site were in the range of 1
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1 background radiation.
I III.
CONTRACTOR RELATIONSIIIPS 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.
2.
The USNRC approval of this plan implies that the Chevron USA, 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 decontaminate the building areas identified by the 1988 ORAU radiological survey and the initial radiological survey.
2.
NES/IES will manifest all radioacdve waste shipments in accordance with USNRC and Department of Transportation (DOT) regulations.
3.
NES/IES on behalf of the Chevron USA, Incorporated and National Park Service has the responsibility for safety during the decontamination operations.
IV.
DECO 513flSSIONING PLAN CONTROL SYSTEM All activities and tasks must be conducted in accordance with this decommissioning plan and/or the appropriate NES/IES procedures. The overall decommissioning plan will be prepared by the Project Manager and approved by the designated Chevron representative and the U.S. 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, in writing, by both the Project Manager and the NES/IES Radiological Services Department Manager. Major changes must be reviewed and approved by the Chevron USA, Inc. and National Park Service representatives, as well as the USNRC.
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d Minor changes to the decommissioning plan (i.e., reordering of specific steps, allowing simultaneous tasks to be performed) must be approved by the Site Supervisor and the Project Manager.
All changes will be documented and attached to the decommissioning 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.
V.
PERSONNEL A.
Training 1.
Health Physics Technicians will be trained to meet the requirements of ANSI /ANS 3.1-1981 (Ref. 3).
1 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.
f.
Emergency Response.
B.
Plan of the Day t
1.
At the start of each day a work briefing will be conducted. This meeting will be administered by the Site Supervisor or his designet..
2.
The purpose of this briefm' g is to review work that was performed il e previous day, discuss potendal problem areas, and ensure that everyone understands the tasks that are to be performed during the current day.
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3.
The briefing will be used to check the following:
i 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 2.
Site Supervisor - William Needrith 3.
Radiological Services Department Manager - Dennis W. Reisenweaver VI.
RADIOLOGICAL 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 (ALARA).
The RWP will be prepared by the Health Physics Technician based on expected and 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 thermoluminescent dosimeter (TLD) and self-reading dosimeter (SRD). A log of individual exposures will be maintained.
Exhibit A provides an example of the Radiation Work Permit (RWP).
VII.
CONTAMINATION CONTROL F
The radiologically controlled areas (RCAs) will be isolated from the general work areas through the use of radiation barrier rope and warning signs. RCAs will be established to encompass each building decontamination location. A step-off pad will be placed at the entrance of each RCA.
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A container will be provided for the disposal of contaminated clothing and waste.
Personnel will wear protective clothing prior to entering the controlled area.
Protecdve clothing requirements will be specified in the appropriate RWP.
Personnel leaving the controlled area shall be surveyed 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.
All material leaving the controlkd 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 building decontamination operations. Air samples will be taken during decontamination activities both on a continuous, routine basis and as specified in the appropriate RWP.
For operations with an increased potential of generating airborne contamination (e.g.,
floor scabbling operations), a high volume air sample will be collected. If warranted by the air sampling results, mitigation techniques, such as holding the head of a HEPA vacuum next to the scabbled surface, will be performed to minimize the generation of airborne contamination during the decontamination 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 Ci/ml for beta / gamma emitters (based on Cs-137).
Respirator fit testing will be administered to all individuals required to wear a respirator. A qualitative fit test will be accomplished 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 each time a respirator is donned.
Procedures for irritant smoke or banana oil test are contained in Exhibit B. The instructions for performing the negative pressure test for a tight-fitting facepiece is provided in Exhibit C.
VIII. RELEASE CRITERIA l
The release criteria established for the Nuclear Lake site decommissioning project include compliance with the surface contamination levels presented in USNRC Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors."
Specifically, the surface contamination in the two buildings, as well as the residual contamination on tools and equipment, will comply with the following USNRC guidance.
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For beta-gamma emitters (e.g., Cs-137):
2 2
5000 dpm/100 cm, average (over 1 m ) fixed plus removable contamination, 2
1000 dpm/100 cm, removable contamination, and 2
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15,000 dpm/100 cm, maximum (not more than 100 cm ) f xed plus removable contamination.
For transuranic contamination (e.g., plutonium isotopes):
2 2
100 dpm/100 cm, average (over 1 m ) fixed plus removable contamination, 20 dpm/100 cm, removable contamination, and 2
2 2
300 dpm/100 cm, maximum (not more than 100 cm ) fixed plus removable contamination.
In addition to the USNRC Regulatory Guide 1.86 requirements, exposure rates may not exceed background by more than 5 R/ h, measured at 1 meter from building surfaces.
IX.
OUALITY ASSURANCE The Quality Assurance Program Plan (QAPP) will be implemented during the Nuclear Lake site decommissioning project. The elements of this plan include, in part, controlled procedures for performing all decommissioning activities, daily instrument performance checks, data review including routine surveys, shipping manifests, radiation work permits, and the use of properly calibrated instrumentation.
There will be at least one NES/IES audit of the decommissioning activities and records. The audit will verify compliance with the requirements of the QAPP and its referenced procedures.
X.
WORK TASKS TASK 1 - ENGINEERING NES/IES will provide procedures governing the work to be performed at the Nuclear Lake Site, including this decommissioning 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 SIIIPPING CONTAINERS 6
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1 Shipping containers will be fabricated and delivered by an approved vendor. Volume i
of these containers has been determined to accommodate maximum packing efficiency and minimize weight surcharges.
i TASK 3 - MOBILIZATION This task includes:
L Travel of workers to the site.
Receipt of materials and equipment.
Staging of equipment.
Set up office.
Familiarize personnel with site.
Setup radiological instrumentation for sample analysis in low background area.
Present training and site orientation.
Perform photographic survey for historical purposes.
TASK 4 - INITIAL RADIOLOGICAL SURVEY This task includes:
Identify the locations reported by ORAU within the two buildings as exhibiting
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elevated surface contamination levels.
Establish grid systems for referencing survey locations.
Obtain random direct and removable contamination measurements of the floor, wall and ceiling surfaces within the two buildings.
L Collect paint, water and sludge samples to assist in the identification of the i
building areas requiring decontamination.
Baseline air monitoring.
TASK 5 - SETUP RADIOLOGICALLY CONTROLLED AREAS Establish a step-off pad at each RCA entrance.
l Setup personnel surveying instrumentation at each RCk entrance.
Place a waste container at each RCA entrance for potentially contaminated I
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P clothing and supplies.
i TASK 6 - CONCRETE DECONTAMINATION 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 air samplers at locations on the perimeter of the RCA. Personnel must l
wear self-reading dosimeters and thermoluminescent dosimeters during the concrete decontamination.
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The elevated concrete surface contamination locations will be decontaminated using a
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l Vacu-Blaster. The Vacu-Blaster operates by pressure blasting the concrete surface with coarse abrasive. The abrasive and generated debris are recovered at the blast l
'l point in a dust-free operation. Large particles of debris are trapped on a vibrating screen just above the hopper, while dust particles are drawn to the cyclone dust l
collector and deposited in a collection jar for disposal. Clean air is discharged into 1
the atmosphere through a cloth filter bag. A HEPA vacuum will be used to collect 3
any remaining debris on the floor from the blasting operation.
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The effectiveness of the decontamination will be determined immediately through the j
i use of field survey instrumentation. Specifically, as the concrete is scabbled, the HP
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Technician will scan the freshly exposed concrete surface for the presence of further j
contamination. Low energy gamma detectors (e.g., Eberline PG-2) and alpha probes j
i-(e.g., Eberline AC-3-8) will facilitate the detection of the plutonium isotopes.
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Beta / gamma probes (e.g., Ludlum 44-9 GM pancake probes) will allow detection of l
Cs-137 in the contaminated concrete. Any remaining " hot spots" will be identified and removed.
!!!! CAUTION !!!!
j WEAR RESPIRATORY PROTECTION WHILE EMPTYING THE FILTER BAG AS AIRBORNE CONTAMINATION MAY BE l
GENERATED. PERFORM THIS TASK WITHIN THE RCA.
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The scabbled concrete debris will be placed in a disposal container. The collected dust l'
will be carefully deposited into a bag, sealed and placed into the disposal container.
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Once filled, the container will be surveyed and shipped to the Barnwell, SC burial site, or other approved site. Refer to the Shipping and Disposal section for more detailed information.
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At the end of each shift, the Site Supervisor will measure and record the quantity of decontaminated concrete.
TASK 7 - OTIIER DECONTAMINATION The initial radiological survey may indicate the contamination of surfaces other than concrete. Painted surfaces may be decontaminated using detergents and cloths or strippable coatings. Wood surfaces may be planed to remove the outer 1/4" and leave a releasable surface in most cases.
This task would also require the issuance of a Radiation Work Permit (RWP) prior to e
task commencement. The RWP will include the protective clothing requirements and the placement of air samplers at locations on the perimeter of the RCA. Personnel must wear self-reading dosimeters and thermoluminescent dosimeters during the decontamination activities.
TASK 8 - PREPARATION /SIIIPMENT OF WASTE I
This task includes:
Radioactive waste packaging.
Radiological survey of waste containers and documentation of results.
Prior to the conclusion of NES/IES building decontamination and soil remediation activities, all wastes will have been shipped off-site and disposed of appropriately.
All records of contaminated and clean waste shipments will be turned over to Chevron USA, Inc. and the National Park Service.
Non-radioactive waste will remain on-site for disposal by the National Park Service.
TASK 9 - DEMOBILIZATION This task includes:
All equipment will be surveyed and decontaminated, as required, prior to shipment off-site.
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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 of all rubbish generated by the work activities.
All materials used for contamination control will be disposed of as clean or contaminated waste as appropriate.
The post-decontamination status of the affected areas will be photographed for historical purposes.
l TASK 10 - PREPARE FINAL REPORTS This task includes:
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The final report will be prepared in Danbury and submitted to Chevron USA, j
Inc. and the National Park Service.
The final report will include records of all laboratory sample analyses, survey data, building decontamination operations and calculations of activity shipped
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to the disposal site.
XI.
RADIOLOGICAL INSTRUMENTATION The following table indicates the type of radiological protection equipment that will be used to monitor the radiological conditions during the building decontamination operations. In addition, survey instrumentation that will allow the determination of the effectiveness of the building decontamination is listed.
i Instrument lhe Thermoluminescent dosimeter Permanent record of radiation exposure t
Self-reading dosimeter Daily personnel exposure Eberline RAS-1 Routine air samples during building (Low volume air sampler) decontamination SAIC/Radeco H-809 VII Air samples as specified by RWP (High volume air sampler) 10 i
4 a
Ludlum 2220 w/Eberline AC-3-8 probe Personnel survey for alpha contamination Ludlum 3 w/44-9 GM probe Personnel survey for beta / gamma contamination Bieron Micro-Rem meter General area exposure rate measurement t
Ludlum 2929 proswich detector Alpha, beta / gamma smear counter Eberline ESP-1 w/PG-2 probe Low energy gamma scan (i.e., Pu-239/240)
Ludlum 2220 w/Eberline PG-2 low energy gamma scan j
Ludlum 2221 w/44-9 GM probe Beta / gamma scan (i.e., Cs-137)
Canberra GC1020 Ge detector Sample analysis w/ multichannel analyzer (MCA)
XII.
SHIPPING AND DISPOSAL A.
Packaging 1.
All material (e.g., contaminated building debris, soil, personnel protective equipment) will be placed in approved disposal containers.
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 serve as the waste hauler.
4.
The waste containers will be stored inside the Plutonium Facility while awaiting transportation to the disposal site. The building material will be shipped along with the waste generated during the soil remediation operations.
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C.
Disposal e
All radiologically contaminated material from the building decontamination effons will be disposed of at the Barnwell Site in South Carolina, or other approved site.
REFERENCES f
1.
Berger, J.D. et al. " Radiological Survey of the Nuclear Lake Site, Pawling l
New York," Oak Ridge Associated Universities; 1988.
2.
U.S. NRC Regulatory Guide 1.86. " Termination of Operating Licenses for Nuclear Reactors;" 1974.
3.
ANSI /ANS-3.1. "American National Standard for Selection, Qualification and Training of Personnel for Nuclear Power Plants;" 1981.
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4 EXHIBIT A RADIATION WORK PERMIT
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RADIATION WORK PERMIT l
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LOCATON d
f EQUIPMENT NAMUNUMBE R INITIATED BY ESTIMATED PE RSON HOURS DATE W FORCE f
.CB DE SCRIPTON (BE SPECIFC)
DATE EXPIRES l
EST PERSON-REW TOTAL EXPOSURE-REM RADIOLOGICAL CONDITIONS gin CONTAMINATON LEVEL MAX CONTAMhATONLEVEL GEN AREA RADATON LIVEL HOT SPOT RADIATON LEVEL pCv100 am?
pCv100 am?
MRE M4w RE M4w j
AIRBORNE PARTCULATE ACT GASEOUS ACTMTY RADolODNE ACTMTV TOTAL NO al M P C 's uCurrd wCvml uC.*rd I
SURVEYED BY DATE RADIOLOGICAL PROTECTION SUPPORT O INffiAL O ON CALL O NTERWITTENT O CONTNUOUS PROTECTIV i CLOTMNO DOSIMETRY t AH COAT l
COTTON GtOVES l
Ft' W RAY:r CivvFRAlts 1m O rw O RussER otovFS - s wO
?w O tow RArz coSiMrTER PtfLSTC SUrt top SUROCA!. Gt OVES WeGH RANGE EOS!MFTER PLoSTC SufTBOTTOW DOSF RATE METER POPE R COVE RAl l.S RESPIRATORY CEAR TLD BADGF HOOD FULL MASK FILTER NEUTRON METER T ACE SwlFt D SUPPilED AIR MASK NFUTRON GADGE RUEBE R OVE RSwC4 S SUPPLIED AIR HOOD MUL TM ADGE PLASTC SHOE Mcw PAPER EFTREtSTV COVE RS ty SCRA TlO'RhG l.esi W TLD' RING - Rgen Hand NCE PROTECTWE CLOT)4NG FILM BADGE /TLD.Left Foot COTTONtwERS l l SURGEON CA.P l
FILM BADGE /TLD-Rght Foot i
SPECIAL INSTRUCTIONS D TAPE GLOVES AND FOOTWEAR TO COVERALLS O FILTERED EXHAUSTVENTILATION REQUIRED D WEAR DOslMETER ON INNER COVERALLS O JOB PLAN MEETING O SET UP LOCAL CONTROL ZONE (Radiabon or Contaminaton)
O ENCLOSED CONTAINMENT REQUIRED D WEAR DOSIMETRY ON HEAD D OUTER PERSONAL CLOTHING NOT TO BE WORN O A!RBORNE SAMPLE TO BE TAKEN AS SPECIF!ED D EVALUATE LOCATION OF WHOLE BODY DOSIMETRY 3
O FIRE WATCH REQUIRED O RADIOLOGICAL OR HAZARDOUS CONDITIONS TO BE l
0 CONFINED SPACE ENTRY CONTROLS RE-EVALUATED AFTER WORK COMMENCES O HARD HATS REQUIRED D CHEMICAL HAZARD D INDUSTRIAL HAZARD MfTIGATION (SPECIFY)
O SCAFFOLDING SAFETY O HEARING PROTECTION REQUIRED l
D EYE PROTECTION REQUIRED I
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RWP APPROVEDDATE RWP APPROVED DATE RWP CLOSE DATE s
i RCs sS RCS 2 RouTwE 3 sPE CAL
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M AIN'ENANCE MA W'ENANCE PROCESSNG WSPECTON WSPECTON i
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IRRITANT SMOKE OR BANANA OIL TEST P
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EXHIBIT B IRRITANT SMOKE OR BANANA OIL TEST This test is to be administered by a Health Physics Technician or Site Supervisor in a well-ventilated area. The Isoamyl Acetate (banana oil) test requires organic vapor l
cartridges to be installed on the mask.
1.
Instruct the individual to breath gently at first and keep his eyes closed.
2.
Direct smoke from the tube or swab dipped in banana oil toward the sealing surfaces of the mask starting at approximately one foot from the seal.
3.
If no odor or irritation is detected, move the smoke tube or swab to within two l
inches from the facepiece. Ensure all sealing areas and points of possible leakage are tested.
!!!! CAUTION !!!!
The smoke (starmic chloride) is highly irritating. If the subject shows any indication of irritation, stop the test immediately.
4.
If the test is used in lieu of a quantitative fit test, continue as follows:
a.
Instruct the wearer to breath deeply.
b.
Continue to direct smoke or the swab toward the facepiece while the wearer performs the following: repeated deep breathing; turning head side to side /up and down; frowning; talking; and running in place.
c.
Recheck the seal at normal breathing rate.
5.
If the wearer detects an odor or irritation, readjust the facepiece and repeat the process.
6.
If no leakage is detected by the wearer, the fit is acceptable.
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1 EXHIBIT C NEGATIVE PRESSURE TEST FOR TIGHT-FITTING FACEPIECE r
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4 EXIIIBIT C NEGATIVE PRESSURE TEST FOR TIGIIT-FITTING FACEPIECE This test is to be performed by the wearer for each issue of a tight fitting facepiece respirator prior to use.
1.
Inspect the mask and don as required by the use procedure for that device.
i 2.
Ensure that the mask is worn such that it affords maximum comfort. Straps adjusted too tight can cause headaches or irritation when worn for extended periods.
3.
When the mask is in place and adjusted for comfort, perform the negative pressure test as follows:
a.
Place the palms on the canisters or breathing inhalation ports.
b.
Inhale genny so that the mask collapses inward toward the face. If any leakage is detected around the facepiece, leadjust the mask and repeat.
c.
If no leakage is detected during inhalation, hold your breath for 10 seconds checking for leakage. If there is still no detectable leakage, the test is acceptable.
d.
Remove palm (s) from the inhalation ports of the cartridge or inlets.
4.
If after approximately three attempts a fit cannot be obtained, notify the Health Physics Technician or the Site Supervisor for assistance and/or get another respirator.
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