ML20027D952
| ML20027D952 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 08/17/1982 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17053D344 | List: |
| References | |
| PROC-820817, NUDOCS 8211100441 | |
| Download: ML20027D952 (11) | |
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I NINE MILE POINT NUCLEAR STATION t
EMERGENCY PLAN AND PROCEDURES PROCEDURE NO. EPP-12
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RE-ENTRY PROCEDURE b
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DATE AND INITIALS APPROVALS SIGNATURES REVISION 4 REVISION 5 REVISION 6 Chemistry & Radiation Management Superintendent d* gf2_
l E. W. Leach
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Station Superintende
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NMPNS T. W. Roman pad 4
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General Superintendent l;
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Nuclear Generation O'
Chairman of S.0.R.C. N fil.
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F T. J. Perkins
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Summary of Pages l!
l Revision 4, dated May 1982, consists of pages i, 1-9, with changes on pages 1, 1, 3-9.
NIAGARA MOHAWK POWER CORPORATION i
THIS PROCEDURE NOT TO BE USED AFTER August 1984 SUBJECT TO PERIODIC REVIEW.
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8211100441 821028
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EPP-12 O
RE-ENTRY PROCEDURE Section Contents
_Page 10 Purpose 1
2.0 References 1
3.0 Responsibility 1
I 4.0 Equipment 2
50 Re entry Team Composition 3
i 6.0 Radiological Precautions 3
7.0 Site Re-entry Procedure 4
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7.1 Site Approach 4
i 7.2 Site Boundary Survey 5
6 7.3 Site Survey 7
l 8.0 Station Re-centry Survey Procedure 7
8.1 Entry 7
8.2 Station Surveys 8
8.3 Survey Evaluation 8
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l 9.0 NMP-2 Survey 8
Figure 1 Inplant/ Downwind /Re-entry 9
Survey Data Sheet I
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l l O EPP-12 -i May 1982 l
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r EPP-12 RE-ENTRY PROCEDURE l
l.0 PURPOSE The purpose of the Re-entry Procedure is to outline the method used to re-enter potential radioactively contaminated areas caused by a l
radiation emergency at the NMP Site.
Re-entry surveys are not to 4
take the place of downwind surveys for evaluating radiological i
releases.
The objective of these re-entry surveys is to evaluate hazards to personnel approaching the Site from the Alternate I
Emergency Operations Facility and to perform a comprehensive survey l
of the Station to define radiological problem areas.
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2.0 REFERENCES
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a.
EPP-7 Down Wind Radiological Monitoring y
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EPP-10 Emergency Equipment Inventories and Check Lists f
c.
EPP-15 Health Physics Procedure 3.0 RESPON.1,1BILITY 3.1 Radiolotical Assessment Coordinator a.
Respansible to the Emergency Director for managing the radiological monitoring and assessment aspects of a re-entry operation.
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t b.
Provides technical and administrative direction to the Station Survey / Sample Team Coordinator and staff during re-entry 4
l operations.
ll 32 Station Survey / Sample Team Coordinator
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f a.
Responsible to the Radiological Assessment Coordinator for providing technical and administrative direction to re-entry survey teams.
l 3.3 Re-entry Survey Teams e
a.
Responsible to the Station Survey / Sample Team Coordinator for performing appropriate re-entry radiation surveys and assessment of radiological problem areas.
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EPP-12
-1 May 1982
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4.0 EQUIPMENT O{
i 4.1 Equipment Location i
The equipment used to make a re-entry survey can be found in the Alternate Emergency Operations Facility Emergency Kit located at the l
NMPC Oswego Service Center.
9 4.2 Equipment Summary The complete description of the equipment contained within the Alternate EOF is contained in EPP-10,
" Emergency Equipment l
Inventories and Checklist".
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4.2.1 Protective Clothing I
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The following protective clothing is avai2able and may be worn if necessary.
a.
Coveralls l
b.
Boot Covers j
c.
Rubber Boots d.
Hoods f
e.
Rubber or Cotton Gloves i
f.
Respirators with Charcoal Cartridges i
g.
Self-Contained Breathing Apparatus (Scott Pak II) j 4.2.2 Survey Equipment The following equipment is available and should be used for the survey.
a.
Count Rate Meter (GM type) b.
Dose Rate Meter (Ion Chamber type) c.
High Volume Air Sampler (DC) d.
Fiberglass Particulate Filters Charcoal Sampling Cartridges e.
f.
Silver Zeolite Cartridges g.
Emergency Procedures Binder with Survey Logs and Maps h.
Film Badges and Dosimeters i.
Environmental Cabinet Key 4.2 3 Communication Equipment a.
High Band Portamobile Radio 4.2.4 Transportation a.
Whenever possible, all re-entry surveys should be performed in radio-equipped company vehicles.
Currently three such vehicles are driven by Site On-Call Supervisors and would be made available to the Re-entry Team (s).
O EPP-12
-2 May 1982
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. 1 5.0 RE-ENTRY TEAM COMPOSITION O-When possible, re-entry team (s) will be composed of a Chemistry and Radiation Management Department Supervisor and a Chemistry and Radiation Protection Technician.
If this staffing is impossible the team (s) shall be comprised of one Chemistry and Radiation Management Department personnel and another individual.
Re-entry surveys should always be made in pairs and never alone.
6.0 RADIOLOGICAL PRECAUTIONS The following radiological precautions should be adhered to during l
u re-entry surveys 6.1 High Radiation Levels a.
If the degree of urgency permits, thoroughly survey the area to be entered to determine radiatica levels.
b.
Wear a Film Badge and a 0-5R direct-reading dosimeter.
h c.
Use time, distance and shielding whenever possible to minimize exposure to search and rescue personnel.
j d.
If beta radiation levels are high, wear heavy protective clothing and eye protection, if not already being worn, for shielding.
e.
If exposures exceeding 10 CFR 20 limits will be necessary, ensare that the guidanca and requirements of EPP-15 " Health l
"hysics Procedure" are followed.
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6.2 High Airborne Radioactivity Concentrations fi a.
If the degree of urgency permits, take air samples in the area f
to be entered to determine the airborne radioactivity concentrations.
b.
Wear protective clothing, as required.
c.
Wear respiratory protective equipment commensurate with the airborne concentration in the area. If the concentration in the area is unknown, wear self-contained breathing equipment.
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j EPP-12
-3 May 1982 4
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6.3 High Surface Contaminaton Levels O
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If the degree of urgency permits, survey the area to be entered a.
to determine the surface contamination levels.
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b.
Wear protective clothing commensurate with the contamination j
levels known or expected to exist in the area.
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Wear respiratory protective equipment if contamination levels L
2 are unknown or exceed about 25,000 dpm/100 cm,
7.0 SITE RE-ENTRY PROCEDURE The following procedure will be used during off-hour radiation emergencies which may affect off-site personnel.
Under these conditions, the Site emergency personnel may be required to assemble at the Alternate Emergency Operations Facility.
The survey outlined below will be made a soon as possible so as to facilitate moving the g
emergency operations center to the On-Site Technical Support Center or Near-Si te Emergency Operations
- Facility, and to define radiological problems that may be encountered by subsequent emergency i
teams (e.g., damage control, search and rescue, etc.)
7.1 Site Approach The survey teau should use available vehicles (either NMPC or h
private) to approach the site from the up-wind direction.
The wind direction at the site should be ascertained via telephone or radio contact with the control room.
7.1.1 Preparation The following preparation will be made by the survey team before l
leaving the Alternate Emergency Operations Facility:
l a.
Obtain a briefing from the Emergency Director, Radiological Assessment Coordinator or Station Survey / Sample Team Coordinator regarding:
4 l 1) required monitoring location data 2) anticipated levels of radiation and contamination enroute i.
3) suggested routes t'
4) required protective gear f'
5) exposure limits allowed for the re-entry 6) reporting location for survey results, samples, and data sheets b.
Don protective clothing:
1)
Coveralls 2)
Boot covers 3)
Rubber boots 4)
Hood 5)
Rubber or cotton gloves EPP-12
-4 May 1982
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7.1.1 Preparation (Cont.)
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c.
Clip on film badge and dosimeter d.
Place poly sheet on front seat of vehicle.
e.
Place clipboard with Survey Log Sheet in car.
f.
Turn on the following survey meters and place in vehicle.
1)
Dose Rate Meter (Ion Chamber type) 2)
CM Survey Meter (Cn type) g.
Place the following sampling equipment in the vehicle:
i 1)
High volume air sampler (12 v d-c)
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2)
Charcoal and glass fiber filters 3)
Silver zeolite cartridges h.
Place charcoal cartridge respirator and self-contained breath".ng apparatus (one for each surveyor) in vehicle.
Not required until exiting from vehicle to make first survey.
Determination to which type of respiratory protection to use when exiting as at the Site should be based on surveys taken while approaching j
Site.
NOTE:
If the vehicle ventilation system (heater) is on or if the vehicle has a continuous ventilation system, don respirator if instruments indicate the plume is being O
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approached.
Significant deviation in open window and, closed window readings indicates possible 'S exposure.
Otherwise, the respirator need not be donned until exiting from the vehicle to make the first survey.
i.
Prior-to leaving equipment storage
- location, ensure all equipment is operational.
l 7.1.2 Observations i
While traveling to the Site, the survey meters should be turned on in l
the vehicle and observed by the passenger.
If any readings I
significantly above background are observed, the vehicle should be halted and a survey made as outlined below.
7.2 Site Boundary Survey t
When the Site boundary is reached, the vehicle should be halted and after putting on a respirator, the following surveys should be made at the roadside.
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l EPP-12
-5 May 1982
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s 7.2.1 Gamma Dose Rate Measurements Iwo different readings (ground level and waist level) are taken at each survey point. These two readings should assist in evaluation of whether the activity is coming from an overhead plume or a ground l
deposit. Reading will be taken af ter air sampler has been started at j
a given locetion, if air sample is required.
NOTE:
Take an air sample only if there is significant deviation between "open" and " closed" window readings.
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Ground Level Readings t
Ground level reading should be taken at approximately 3 in. from the ground using a Count Rate Meter.
Readings over 20,000 c/m should be taken with a Dose Rate Meter; record open window and closed window readings.
Waist Level Readir.gs i
Take waist level readings (a pproximately 3 ft. from the ground) at each of the locations where a ground level reading is taken.
Readings over 20,000 c/m should be taken with a Dose Rate Meter; record open windou and closed window readinge.
7.2.2 Air Sample Measurerents a.
Using a portable high volume air sampler with both particulate g
filter and Iodine collection cartridge obtain a 5-10 minute sample (approximately 15 cubic feet).
Record Flow Rate and the time the, sampling is started and stopped.
NOTE:
Silver Zeolite Sampling Cartridges shall be used until it has been determined that noble gas interference of air sample measurements is not a problem.
b.
Label the sample envelopes for location and times.
c.
After obtaining samples, travel to an area of low background l
( < 100 cpm) and run high volume air sampler for approximately i
1 minute to clear inert gases from the cartridge.
NOTE:
If sample has been taken on Silver Zeolite Cartridge (s) the post-sampling purge is not required.
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d.
Obtain a background count using a count rate meter and count the l
particulate filter and Iodine cartridge separately.
During 4
counting hold the probe approximately 1/2 to 3/4 inch from the cartridge or filter and count for a total time of 1 minute. Log l
the maximum count rate observed on the Survey Data Sheet (Figure
- 1).
Iodine sample count greater than 10,000 cpm should be returned for GeLi analysis expeditiously.
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EPP-12
-6 May 1982 i.,,.__,
7.2.2 Air Sample Measurements (Cont.)
O e.
Return labeled air sample filters and cartridges to the location specified in 6.1.1.a for GeLi analysis.
i NOTE:
Sample analysis may be performed onsite at the Station k
Chemistry laboratory or at the JAFNPP Station or Environmental Chemistry I4boratory.
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7.2.3 Reporting Results of Re-entry Surveys As surveys are completed record results on Figure 1 and transmit l
results to the AEOF or the location specified under 6.1.1.a.
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7.2.4 Survey Evaluation i
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As survey results are received from the survey teams the Radiological l
Assessment Coordinator or the Station Survey / Sampler Team Coordinator will calculate dose rates and airborne concentrations using the methodology and figures described in EPP-7 Step 5.2.7.
t The results will be evaluated by the Radiological Assessment Coordinator and appropriate recommendations made to the Emergency Director.
7.3 Site Survey
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l Af ter the Site boundary survey has been performed (radiation survey
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and airborne activity), and the data transmitted to the Station
- l Survey / Sample Team Csordinator at the AEOF or the location described
'i in 6.1.la, the survey team will proceed to perform additional surveys l
if conditions permit ( < 100 mr/hr).
Locations where additional surveys should be performed include l
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't a.
Nearsite EOF l
b.
Security Building i
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8.0 STATION RE-ENTRY SURVEY PROCEDURE 6
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8.1 Entry l
1 The survey team should enter the Administration Building (still wearing protective equipment) making dose rate measurements as they go.
Upon entering the building they should contact the control room l
to inform them that they are present and are ready to make a survey of the emergency centers. Areas to be surveyed should include the:
a.
TSC and Administration Building, 277' Elevation 4
b.
OSC and Administration Fuilding, 266' Elevation l
c.
Station Chemistry Laboratory i
EFP-12
-7 May 1982
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8.2 Station Surveys t
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ll An evaluation of surface contamination levels, Beta gamma dose rates, and airborne activity should be performed at each of the locations l
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'l described in St.ep 8.1.
As surveys are corrpleted, record results in l
Figure 1 and transmit to the Station Survey / Sample Team Coordinator j
at the AEOF or location described in 6.1.la.
l 8.3 Survey Evaluation f
The survey results will be calculated and evaluated by the i
Radiological Assessment Coordinator or the Stetion Survey / Sample Team l
Coordinator using the methodology described in EPP-7 and EPP-8.
Af ter evaluation of the survey results, the Radiological Assessment 4
Coordinator will provide appropriate recommendations to the Emergency l
Director on the advisability of moving emergency personnel back to i
the onsite emergency facilities.
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i During the evaluation of onsite conditions, the Emergency Director l
shall assemble, as appropriate, necessary emergency teams (eg Damage Control, Inplant Survey Teams, etc) for possible assignment to the j
site once habitable conditions have been verified.
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9.0 NMP 2-RE-ENTRY SURVEY When the evaluation of the NMP-1 areas have been completed, direction will be provided to the re-entry survey team (s) to evaluate 4
g radiological conditions at the NMP-Unit 2 Construction Site.
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EPP-12
-8 May 1982
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i EPP-6, FICURE 1. EPP-7. FICULE 1. EPP-12. FICURE 1 I.
1 INPLANT/DOWNWII.'D/ REENTRY SURVET DATA Si1EET l
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/
/Inplant Survey Survey Heter Model I SR I Area Radiation Monitor Hodel i SR i
/ / Downwind Survey Count Rate Heter Model i SR I' Continuous Air Honitor Model #
SR #
I / Reentry Survey High volume Air Sampler Model f SR f High Range Survey Heter Model #
SR #
Ceneral Area Radiation Data Air Sampling Data Exposure Control Data W.O.
W.C.
Reading Reading Survey (mR/hr)
(mR/hr)
Beta Flow Sample Count Exposure Cumulative Date/
Survey or or Correction Sample Start Stop Duration Rate Bksd Rate (cpe)
Surveyor's Team Received Exposure Time Location (CPH)
(CPH)
Factor IDI Time Time (min)
(cpe)
(cpe) Part Iodine Initials Hesbers (aren)
(arem)
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HOVING SURVET DATA / ARH/ CAM DATA Time Location Survey Data f
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- fint reported vis voice communication.
- Recorded only for Downwind Surveys.
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