ML20040D154

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures CP/1/A/2002/4A Re post-accident Liquid Sampling of RCS & CP/1/A/2002/4B Re post-accident Liquid Sampling of LPIS
ML20040D154
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 12/28/1981
From:
DUKE POWER CO.
To:
Shared Package
ML16162A309 List:
References
PROC-811228-01, NUDOCS 8201300333
Download: ML20040D154 (68)
v • d • e


Text

. __ _ _ . . _ _ - _ _ _ ._ _ _ . _ - . - _ _ . . . _ .

2 ,

l' TABLE OF CONTENTS

{

I l Emergency, Telephone Numbers - (09/30/81, Rev. 4)

AP/0/A/1000/01 Event Index - (08/20/81)

AP/0/A/1000/02 Unusual Event - (08/20/81) i AP/0/A/1000/03. Alert - (08/20/81)

AP/0/A/1000/04 Site Area Emergency - (08/20/81)

AP/0/A/1000/05 General Emergency - (08/20/81) i AP/0/A/1000/06 Procedure for Initiating Protective Action

Guides for the General Public in the Emer-gency Planning Zone - (08/20/81)

, AP/0/A/1000/08 Procedure for Response Actions for Accidents /

j Emergencies - (10/15/81) ,

AP/0/A/1000/10 Procedure for Emergency Evacuation of Station '

Personnel - (08/20/81)

Station Directive 2.9.1 Station Assembly and Evacuation Procedure---

. (08/20/81, Original Issue)

Station Directive 2.9.2 Emergency Response Organization and Training -

(08/20/81, Original Issue) l Station Directive 3.8.5 - Offsite Dose Calculation - (08/20/81)

Station Directive 5.1.3 Personal Injury Procedure - (10/19/81)

, PT/0/B/2000/04 Procedure for Establishment and Inspection l- of the Technical Support Center - (10/15/81) 4 '

l CP/1/A/2002/04A Post Accident Liquid Sampling of the Reactor i Coolant System (12/01/81)

CP/2/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81)

CP,/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81) .

CP/1/A/2002/04B Post Accident Liquid Sampling of the Low '

Pressure Injection System (12/01/81) .

CP/2/A/2002/04B Post Accident Liquid Sampling of the Low .

Pressure Injection System (12/01/81)

  • O Wh M $

7 8201300333 820119 f PDR ADOCK 05000 F

Page 2

% i Table of Contents (Implementing Procedures bontinued)

CP/3/A/2002/04B Post Accident Liquid Sampling of the Low (mV) Pressure Injection System (12/01/81)'

CP/0/B/4003/01 Procedure tor Ecvironmental Survei))ance Folloving,a large Unplanned Reicase of' Caseods Radioactivity' - (08/20/81)

CP/0/B/4003/02 The Det'ermination of Plume Direction and Sector (s) to be Maaitored Following a Large Unplanned t Release of'Gaseoue 1 Activity - (08/20/81)

HP/0/B/1009/09 '

Procedure for Determining the Inplant Airborne Radioiodine Concentration During Accident Conditions - (07/09/81)

HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases

,Through. Steam Relief Valves Under Post-

' Accident. Conditions - (07/08/81)

HP/0/B/1009/11 Projection of Offsite Dose from the Uncon-trolled' Release of Radioactive Materials 1t -Through'a init Vent - (07/08/81)

N HP/0/B/1009/12 Distribution of Potassium Iodide Tablets in the Ehents of a Radioiodine Release - (06/10/81)

() HP/0/B/1009/13 ' Procedure for Implementation and Verification for the Availability of a Back-Up Source of s . Meteorological Data - (07/08/81)

HP/0/B/10')9/15 Procedute'iorQdantifyingHighLevelGaseous Radioactivity Releases During Accident Condi-tions - (08/07/81)

HP/0/B/1009/16 '

Procedure for Emergency' Decontamination of Personnel and' Vehicles on-site and from-Off-site Remote Assembly Area - (10/12/81)

IP/0/B/1601/03 Environmental Equipment Checks - (02/25/81)

JM/ MET /AT/WD/VS M7.00 .keekly Check and Calibration Procedure for 4

s

\

the' Meteorological Monitoring System - (03/02/81, Rev. 0) -

s N

)

\

l 4 ., m 4

& , + .

\_ v [. ,.

,' Revision; December 28, 1981 k

CONTROL COPY Form SPD-1002-1 DUKE POWER

  • COMPANY (1) ID No: CP/1/A/2002/04A PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: ncnnon Nucione c;eetion (3) PROCEDURE TITLE: Post Accident Liquid Samuling of the Reactor Coolant System (4) PREPARED BY: th a i _ h DATE: II-D- % I

' (5) REVIEWED BY: DATE: [ d  ! _

Cross-Disciplinary Review By:,h cv 1 N,t hera /R: ~

( (6) TEMPORARY APPROVAL (IF NECESSARY):

l l ('N By: (SRO) Date:

b By: A Date:

(7) APPROVED BY: Date: lb!/f71 (8) MISCELLANEOUS:

~

Reviewed /',,- U By: /7I [ c w ,Date: //-- 347 - //

Reviewed /6 -m By: Date:

l l

tm.,

l\ J/

, CP/1/A/2002/04A

, Pass 1 of 9 s

DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT LIQUID SAMPLING OF THE REACTOR COOLANT SYSTEM 1,0 Purpose 1.1 To define the steps necessary to sample the RCS when fuel damage is estimated to be greater than 1%.

2.0 Limits and Precautions 2.1 VALVE ALIGNMENTS SHALL NOT BE MADE AND SAMPLES SHALL NOT BE TAKEN WITHOUT PRIOR AUTHORIZATION FROM THE TECHNICAL SUPPOR' T 7 ENTER (TSC)!

2.2 DO NOT ATTEMPT ANY PHASE OF SAMPLING OR ANALYIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGEl 2.3 Radiation exposure to an individual during all phases of sampling should be limited so as not to exceed a quarterly accumulative ex-(N posure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4

( rems extremities respectively. All personnel will need prior author-ization from TSC to knowingly exceed any exposure limit. The exposure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radiation work.

2.3.1 If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.

2.3.2 If necessary to save lives or prevent loss of life and/ or extensive damage to property (voluntary b sis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of wholebody; i or 375 rems extremities.

i 2.3.3 For Outside Services Personnel the Planned Emergency Exposure t will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems extremities; or 15 rems other single organ.

2.4 Radiation levels of the sampling area shall be measured continuously during all phases of sampling, and sample preparation and analysis.

, ,s 2.4.1 Air activity should be determined by use of installed air

\ monitors or through the use of portable air sampling (s equipment.

2.4.2 Area dose rates should be esbablished by the use of in-stalled radiation monitors or by portable radiation survey instrument.

CP/1/A/2002/04A Pagn 2 of 9 2.5 Portable shielding, remote handling equipment, video equipment, etc., shall be used where practical during sampling, sample preparation, and sample analysis.

2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. Those valves followed by (0) in this pro-cedure shall be controlled by Operations. Those valve numbers in parenthesis ( ) are already aligned per normal operating procedures and should only require operator verification when sampling flow problems are encountered.

3.0 References 3.1 NUREG-0737 3.2 DPC System Health Physics Manual 3.3 Radiological Health Handbook, U.S. Dept. of HEW (1970).

3.4 Radiation Safety Technician Training Course, H.J. doe, ANL-7291 Rev. 1 (1972).

4.0 Equipment

,. 4.1 Shielded Sample Container i

4.2 Sample Tongs

(

4.3 Poly bottles - 60ml (2oz.) size 4.4 Carboy - ~ 1 gal.

5.0 Procedure 5.1 Initial Conditions 5.1.1 Verbal / written direction for sampling the Reactor Coolant System (RCS) has been recieved from the Technical Support Center (TSC).

5.1.2 The specific post-accident analysis requested by TSC:

Boron -

Chloride Isotopic Analysis for Iodines Cesiums Noble Gases Non-Volatile Fission Products Other (specify)

cP/1/A/2002/04A Paga 3 of 9 5.1.3 Determine by detail planning meeting, the exact  !

/ course of action and data required.

5.1.4 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel in the sample hood.

5.1.5 Determine and use the required respiratory equip-ment and protective clothing to prevent.or minimize internal exposure in any Planned Emergency situation.

Use high range and/or extremity dosimetry if ,

required.

5.1.6 Request HP to designate a low dose waiting area while sample is flushing to the LDST.

Low dose area designated:

5.1.7 Request HP to designate a route from the sample hood to the lab for the sample shield containing the RCS sample.

s Sample route designated:

O 5.1.8 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel, in the lab for the required analysis.

. 5.1.9 Request HP to perform a constant radiation survey during valve alignment, sample withdrawn, sample transportation and analysis.

5.1.10 Prepare two (2) 60 ml (2 oz.) poly bottles. Label one as "RCS Flush" bottle. Label the other bottle as "RCS Sample" bottle. Label both bottles with tae date and time of sample prior to entering the sample hood.

5.1.11 Prepare one (1) carboy (~ 1 gal.). Label as " Post Accident Lab Waste".

5.2 Valve Alignment 5.2.1 Request HP to determine the stay time in the sample

/s room for person performing valve alignment for (j sample recirculation. The stay time should represent the maximum time a person may remain in proximity of the sample hood while performing the valve

CP/1/A/2002/04A Paga 4 of 9 O alignment for sample recirculation. The stay time can vary (with rad levels) as you progress thru the valve line-up.

5.2.2 Perform the following valve alignment within the calculated stay time from Step 5.2.1:

5.2.2.1 Close RC-63 (C)

RC-151 (C)

RC-89 (C)

RC-88 (C)

RC-87 (C)

RC-85 (C)

RC-56 (C)

RC-143 (C)

RC-144 (C)

RC-145 (C)

RC-146 (C)

RC-147 (C)

RC-148 (C)

RC-53 (C) 5.2.2.2 Open O' (HP-282) (0)

(HP-281) (0)

(RC-57) (0)

RC-149 (C)

RC-150 (C)

RC-86 (C)

(RC-64) (0) 5.2.3 Record the pressure across the capillary tube on PG-14 (inlet press) and PG-15 (outlet) press.).

PG-14 psig PG-15 psig

( 5.2.4 Retreat to the low dose area outside the sample room, as designated by HP, to wait while sample is flushing to the LDST.

5.3 Sample Withdrawal I

5.3.1 When the radiation levels on the sample lines peak at maximum, request HP to determine the stay time in the sample room for person taking sample. The stay time should represent the maximum time a l 'g person may remain in proximity of the sample hood

,j while drawing the sample and in proximity of the l sample until it is placed in the sample shield.

The stay time can vary (with rad levels) as you progress thru the sample with'drawal.

CP/1/A/2002/04A

- Paga 5 of 9 5.3.2 Perform the following sample withdrawal and storage within the calculated stay time from Step 5.3.1:

5.3.2.1 Grasp and position the open "RCS Flush" bottle, at arms length, beneath the sample point using tongs.

5.3.2.2 Carefully OPEN: RC-148 and flush

  • 20 ml into the " Flush" bottle then CLOSE:

RC-148.

5.3.2.3 Tightly cap the " Flush" bottle and set aside.

5.3.2.4 Grasp and position the open "RCS Sample" bottle, at arms length, beneath the sample point using tongs.

5.3.2.5 Carefully OPEN: RC-148 and flush

  • 20 ml into the " Sample" bottle then CLOSE:

RC-148.

5.3.2.6 Tightly cap the " Sample" bottle.

5.3.2.7 Place both poly bottles in the sample g

shield and replace the sample shield plug.

5.3.2.8 CLOSE RC-150 (C)

RC-149 (C)

RC-86 (C) 5.4 Waste Disposal 5.4.1 Determine by detail planning meeting, the exact course of action to be taken. Under no condition will liquid or solid wastes be disposed of without prior specific HP directions. __

5.4.2 Designate a sealable carboy as the " Post Accident Lab Waste" container. This container must be shielded and used as an interim liquid waste dis-posal container for all liquid analytical waste.

5.4.3 Request HP to designate an area where the "RCS Flush" bottle (s), "RCS Sample" bottle (s) and

" Post Accident Lab Waste" container may be

/Ns stored until final disposal.

U Storage area designated

. - - . .- _~ - . _- . . = . . . - _. _. .

CP/1/A/2002/04A Page 6 of 9 5.4.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for

shielding or protective covering to prevent the spread of airborne activity.

5.5 Dose Exposure Evaluation l 5.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden analysis, etc., as required. The exposure received may require an occupational exposu.e penalty.

Higher doses will require a medical decision as to j whether an individual can continue in radiation work.

6.0 Enclosures 6.1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA.

6.3 Conversion Factors l

i i

r i

'. CP/1/A/2002/04A Paga 7 of 9 ENCLOSURE 6.1 SHIELD THICKNESS The following equations can be used as an aid in determining shielding requirements for a sample of RCS after an accident.

given: I=Ie* g Y

where: p = p,p I/I g =emE P*

In(I/I g) = -p,px In(I g/I)

(eq. 6.1.1) p,p where: x = thickness of absorber (cm) p = linear attenuation coefficient (cini )

2 p" = mass attenuation coefficient (cm /g) @ the energy level (Mev) of the source p = density of the absorber material (g/cm ) 3 C\

t I = source intensity w/zero thickness of the absorber (mR/hr or R/hr)

I = source intensity w/an x thickness of the 1 absorber (mR/hr or R/hr) given: (HVL) I/Ig= 1/2 = EP mP*

In(1/2) = -p,px ,

(eq. 6.1.2) g ,0.693 p,p A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As a general rule we add one HVL to our absorber thickness calculations for conservatism:

(eq. 6.1.3) 1"(I o/I) + 0.693 l

l

  • total , p ,p

. . _ _ _ _ - - - _. _ ___. . . _ . _ __ _ . _ _ _ _ . . . ___. _.. . _ _ . _ . _. __ . - = . . - _ . . . - _ _ . _ . _ _

4

, CP/1/A/2002/04A Page 8 of 9 i

i ENCLOSURE 6.2 '

l l 5, A and R Values for 1% Failed Fuel and DBA i i

i  !

] 1% Failed Fuel:

1 l 5% 0.34 MeV/ dis. A

  • 0.293 mci /ml i

R = 0.18 mR/hr-mci @ Im for 5 s 0.34 MeV 1

100% Failed Fuel or Design Basis Accident (DBA) i

! EN 1.14 MeV/ dis. AN 1.324 x 10s pCi/ml i

i R = 0.58 R/hr-Ci @ im for 5 s 1.14 MeV ,

i A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 100%.

4 l

i 4

i l

t t

9 n,y, , - m---- .- ,g, _e.4,_, , , _ _ . ,mw, m. -

mv, e-.. ., ---- , . , - , , , , - - , _ , _ , - , , - - , - - - , . - , --- -,

.. CP/1/A/2002/04A Page 9 of 9

~ ENCLOSURE 6.3 CONVERSION FACTORS Source Activity - (A) 1 Curie (Ci) = 3.7 x 10 10 dis./sec. = 2.22 x 10 12 dpm 1 mci = 3.7 x 10 7 dps = 2.22 x 109 dpm ,

1 pCi -

= 3.7 x 10 4 dps = 2.22 x 10*dpm R _

mR hr-Ci br-mci Density - (p)

(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm 3 i

Mass Attenuation Coefficient - (p,)

(p ) for elements and common materials at varying energy levels (MNe ) for the source can be found on pg. 137 thru 139 of the i " Radiological Health Handbook."

Distance - (d) given: 2 2 Ig /I = d /d g where: I g= Source intensity (mB/hr or R/hr) @ distance (d ) g I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.

I ft.= 0.305 m 3 ft. = 0.914 m l

f l

l I

y- w y -- , , - _ . - - - - 9 m .-- --r, , . ~ + - - m-- - ,_- _ - - - - _ .

1 o COLTTROL Copy Form SPD-1002-1 i

l DUKE POWER COMPANY (1) ID No: CP/2/A/2002/04A PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Post Accident Liquid Sampling of the Reactor Coolant System (4) PREPARED BY: -h DATE: \l- 13 -b l (5) REVIEWED BY: DATE: 8 [/

Cross-Disciplinary Review By: M N/R: //-2.7-f/'

/

(6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

N By: Date:

l (7) APPROVED BY: / ,

Date: /Z!/h /

(8) MISCELLANEOUS:

Reviewed / P d By: M [. Date: //-38-dr#/

Reviewed /=;---9 'd By: Date:

)

o

CP/2/A/2002/04A Page 1 of 9 Q DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT LIQUID SAMPLING OF THE REACTOR COOLANT SYSTEM 1.0 Purpose .

1.1 To define the steps necessary to sample the RCS when fuel damage is estimated to be greater than 1%.

2.0 Limits and Precautions 2.1 VALVE ALIGNMENTS SHALL NOT BE MADE AND SAMPLES SHALL NOT BE TAKEN

  • WITHOUT PRIOR AUTHORIZAH 3N FROM THE TECHNICAL SUPPCRT CENTER (TSC)!

2.2 DO NOT ATTEMPT ANY PHASE OF SAMPLING OR ANALYSIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGE!

2.3 Radiation exposure to an individual during all phases of sampling s should be limited so as not to exceed a quarterly accumulative ex-posure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively. All personnel will need prior author-ization from TSC to knowingly exceed any exposure limit. The exposure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radiation work.

2.3.1 If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.

2.3.2 If necessary to save lives or prevent loss of life and/ or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will l not exceed 25 rems wholebody; 150 rems skin of wholebody; or 375 rems extremities.

2.3.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems extremities; or 15 rems other single organ.

2.4 Radiation ?.evels of the sampling area shall be measured continuously

'~'g during all phases of sampling, and sample preparation and analysis.

(Q 2.4.1 Air activity should be determined by use of installed air monitors or through the use of portable air sampling equipment.

l

CP/2/A/2002/04A '

Page 2 of 9 2.4.2 Area dose rates should be established by the use of in- ,

i stalled radiation monitors or by portable radiation survey

.s _,/ instrument.

2.5 Portable shielding, remote handling equipment, video equipment, etc., shall be used where practical during sampling, sample preparation, and sample analysis.

2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. Those valves followed by (0) in this procedure shall be controlled by Operations. Those valve numbers in paren-thesis ( ) are already aligned per normal operating procedures and should only require operator verification when sampling flow problems are encountered.

3.0 References 3.1 NUREG-0737 3.2 DPC System Health Physics Manual 3.3 Radiological Health Handbook, U.S. Dept. of HEW (1970).

3.4 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev.

1 (1972).

s 4.0 Equipment 4.1 Shielded Sample Container 4.2 Sample Tongs 4.3 Poly bottles - 60ml (20z.) size 4.4 Carboy - ~ l gal.

5.0 Procedure l

l 5.1 Initial Conditions l

l 5.1.1 Verbal / written direction for sampling the Reactor Coolant

' System (RCS) has been recieved from the Technical Support Center (TSC).

5.1.2 The specific post-accident analysis requested by TSC:

Boron Chloride s

Isotopic Analysis for Iodines i

l

l

, CP/2/A/2002/04A Page 3 of 9 Cesiums .

Noble Gases Non-Volatile Fission Products Other (specify) 5.1.3 Determine by detail planning meeting, the exact 3

course of action and :'. - required.

5.1.4 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel in the sample hood.

5.1.5 Determine and use the required respiratory equip-ment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation.

Use high range and/or extremity dosimetry if required.

5.1.6 Request HP to designate a low dose waiting area while sample is flushing to the LDST.

~s Low dose area designated: _

5.1.7 Request HP to designate a route from the sample hood

( to the lab for the sample shield containing the RCS sample.

Sample route designated:

5.1.8 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel, in the lab for the required analysis.

5.1.9 Request HP to perform a constant radiation survey during valve alignment, sample withdrawn, sample transportation and analysis.

5.1.10 Prepare two (2) 60 ml (2 oz.) poly bottles. Label one as "RCS Flush" bottle. Label the other bottle as "RCS Sample" bottle. Label both bottles with the date and time of sample prior to entering the sample hood.

{}

N.se 5.1.11 Prepare one (1) carboy (~ 1 gal.). Label as " Post Accident Lab Waste".

l

CP/2/A/2002/04A Page 4 of 9 5.2 Valve Alignment 5.2.1 Request HP to determine the stay time in the sample room for person performing valve alignment for sample recirculation. The stay time should represent I the maximum time a person may remain in proximity l of the sample hood while performing the valve alignment for sample recirculation. The stay time can vary (with rad levels) as you progress thru )

the valve line-up.

5.2.2 Perform the following valve alignment within the calculated stay time from Step 5.2.1:

5.2.2.1 Close 2RC-63 (C) 2RC-151 (C) 2RC-89 (C) 2RC-88 (C) 2RC-87 (C) 2RC-85 (C) 2RC-56 (C) 2RC-143 (C) 2RC-144 (C) 2RC-145 (C) f3 N/

m 2RC-146 (C) 2RC-147 (C) 2RC-148 (C) 2RC-53 (C) 5.2.2.2 Open 1

(2HP-282) (0)

(2HP-281) (0)

(2RC-57) (0) 2RC-149 (C) l 2RC-150 (C) 2RC-86 (C) l (2RC-64) (0) 5.2.3 Record the pressure across the capillary tube on 2PG-14 (inlet press) and 2PG-15 (outlet) press.).

2PG-14 psig 2PG-15 psig 5.2.4 Retreat to the low dose area outside the sample room, as designated by HP, to wait while sample is flushing to the LDST.

' 'g 5.3 Sample Withdrawal G 5.3.1 When the radiation levels on the sample lines peak at maximum, request HP to determine thE ' stay time

CP/2/A/2002/04A Page 5 of 9 in the sample room for person taking sample. The

['~'h stay time should represent the maximum time a person (s_,/ may remain in proximity of the sample hood while drawing the sample and in proximity of the sample until it is placed in the sample shield. The stay time can vary (with rad levels) as you progress thru the sample withdrawal.

5.3.2 Perform the following sample withdrawal and storage within the calculated stay time from Step 5.3.1:

5.3.2.1 Grasp and position the open "RCS Flush" bottle, at arms length, beneath the sample point using tongs.

5.3.2.2 Carefully OPEN: 2RC-148 and flush

  • 20 ml into the " Flush" bottle then CLOSE:

2RC-148.

5.3.2.3 Tightly cap the " Flush" bottle and set aside.

5.3.2.4 Grasp and position the open "RCS Sample" bottle, at arms length, beneath the sample point using tongs.

, ; 5.3.2.5 Carefully OPEN: 2RC-148 and flush

  • 20 ml into the " Sample" bottle then CLOSE:

2RC-148.

5.3.2.6 Tightly cap the " Sample" bottle.

5.3.2.7 Place both poly bottles in the sample shield and replace the sample shield plug. -

5.3.2.8 CLOSE l 2RC-150 (C) 2RC-149 (C) 2RC-86 (C) 5.4 Waste Disposal 5.4.1 Determine by detail planning meeting, the exact course of action to be taken. Under no condition j will liquid or solid wastes be disposed of without l prior specific HP directions.

l l

5.4.2 Designate a sealable carboy as the " Post Accident Lab Waste" container. This container must be j ('~'N_, )- shielded and used as an interim liquid waste l disposal container for all liquid analytical l waste.

l

CP/2/A/2002/04A Page 6 of 9 u .

5.4.3 Request HP *,o designate an area where the "RCS g Flush" bottle (s), "RCS Sample" bottle (s) and

" Post Accident Lab Waste" container may be stored until final disposal.

Storage area designated 5.4.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.

5.5 Dose Exposure Evaluation 1

5.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden

. analysis, etc., as required. The exposure received i may require an occupational exposure penalty.

Higher doses will require a medical decision as to whether an individual can continue in radiation work.

6.0 Enclosures 6.1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA.

i 6.3 Conversion Factors

(

)

i

.-g-a--e7n~-

--,-------r-,. v.. --m - , . - , , , , , - m - , , - - -- . . . . . . - , - - - - - -. w. ,- -, -w~- - - - - --- .- - _ . - - _ - - - - _ _ - - - - - - ---

CP/2/A/2002/04A Page 7 of 9 ENCLOSURE 6.1 SHIELD THICKNESS The following equations can be used as an aid in determining shielding  ;

requirements for a sample of RCS after an accident.

given: I=Ie* g E

where: p = p,p i I/I g =em E P*

I

in(I/I )g = -p,px i in(I g/I)

(eq. 6.1.1) p,p where: x = thickness of absorber (cm) y = linear attenuation coefficient (cm ) i 2

i p* = mass attenuation coefficient (cm /g) @ the energy level (Mev) of the source p = density of the absorber material (g/cm3 )

l I U= source intensity w/zero thickness of the absorber I f (mR/hr or R/hr) l I = source intensity w/an x thickness of the absorber (mR/hr or R/hr) given: (HVL) I/I = 1/2 = e YP g m*

l In(1/2) = -p,px -

(eq. 6.1.2) , ,0.693 p,P A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As a general rule we add one HVL to our absorber thickness calculations for conservatism:

i l (eq. 6.1.3) _

In(I o/I) + 0.693

  • total - p,p i

V l

CP/2/A/2002/04A Page 8 of 9 '

ENCLOSURE 6.2 5, A and R Values for 1% Tailed Fuel and DBA  ;

4 1% Failed Fuel:

5
  • 0.34 MeV/ dis. AN 0.293 mci /ml i

i R = 0.18 mR/hr-mci @ Im for 5

  • 0.34 MeV  ?
i 100% Failed Fuel or Design Basis Accident (DBA)
i

) Es 1.14 MeV/ dis. A

  • 1.324 x los pCi/ml '

R = 0.58 R/hr-Ci @ Im for 5

  • 1.14 MeV
A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 100%.

i

)

4

  • p L

l l

i  !

l i

i 8

l 1

e I

i.__ . . . - . . _ _ . , , _ _ _ _ . _ . _ _ _ _ _ . . _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ . . . _ _ . _ _ _ . . _ , . _ _ _ _ . . _ .

. CP/2/A/2002/04A

. Page 9 of 9 ENCLOSURE 6.3 CONVERSION FACTORS i

Source Activity - (A) 1 Curie (Ci) = 3.7 x 10 10 dis./sec. = 2.22 x 1012 dpm 8

1 mci = 3.7 x 10 7 dps = 2.22 x 10 dpm 8

1 pCi = 3.7 x 10 4 dps = 2.22 x 10 dpm R _

d br-Ci hr-mci Density - (p) l (p) for elements and common materials can ce found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm 3 Mass Attenuation Coefficient - (p,)

x'

) for elements and common materials at varying energy levels (p*V)

(Me for the source can be found on pg.137 thru 139 of the

" Radiological Health Handbook."

Distance - (d) given: 2 2 Ig /I = d /d g where: I g= Source intensity (mR/hr or R/hr) @ distance (d g)

I = Source intensity (mR/hr or R/hr) @ distance (d)

m. = 3.281 ft. = 39.37 in.

I ft.= 0.305 m 3 f t. = 0.914 m O .

g c CONTROL COPY Form SPD-1002-1 DUKE POWER COMPANY (1) ID No:_cp/3/A/2002/04A PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Post Accident Liquid Sar:pling of the Reactor Coolant System (4) PREPARED BY: /b et k W h DATE: Il-- 2.1 -b i (5) REVIEWED BY: DATE: / d 8/

Cross-Disciplinary Review By: k C N/R:

(6) TEMPORARY APPROVAL (IF NECESSARY):

Date:

p By: (SRO)

By: _

Late:

(7) APPROVED BY: /

( _" - Date: /2///7 /

(8) MISCELLANEOUS:

Reviewed /f = A By: MM Date: / 7/3 [/

Reviewed /typsumM By:N[ m_ Date: // ((

t

\_)

CP/3/A/2002/04A

, Pega 1 of 9 i DUKE POWER COMPANY  ;

OCONEE NUCLEAR STATION

]

POST ACCIDENT LIQUID SAMPLING OF THE

] REACTOR COOLANT SYS!EM l 1.0 Purpose 4 -

4 1.1 To define the steps necessary to sample the RCS when fuel damage is estimated to be greater than 1%.

2.0 Limits and Precautions 2.1 VALVE ALIGNMENTS SHALL NOT BE MADE AND SAMPLES SHALL NOT BE TAKM WITHOUT PRIOR AUTHORIZATION FROM THE TECHNICAL SUPPORT CENTER (TSC)!

2.2 DO NOT ATTEMPT ANY PHASE OF SAMPLING OR ANALYSIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGE!

, 2.3 Radiation exposure to an individual during all phases of sampling should be limited so as not to exceed a quarterly accumulative ex-posure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 j' rems extremities respectively. All personnel will need prior auth-orization from TSC to knowingly exceed any exposure limit. The ex-

, posure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radi-ation work.

2.3.1 If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for i

Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.

2.3.2 If necessary to save lives or prevent loss of life and/ or ,

I extensive damage to property (voluntary basis only), the  !

Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of wholebody; or 375 rems extremities.

, 2.3.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems extremities; or 15 rems other single organ.  :

2.4 Radiation levels of the sampling area shall be measured continuously during all phases of sampling, and sample preparation and analysis.

2.4.1 Air activity should be determined by use of installed air

\

monitors or through the use of portable air sampling equipment.

CP/3/A/2002/04A Paga 2 of 9 2.4.2 Area dose rates should be established by the use of in-stalled radiation monitors or by portable radiation survey

\ instrument.

2.5 Fortable shielding, remote handling equipment, video equipment, etc., shall be used where practical during sampling, sample preparation, and sample analysis.

2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. Those valves followed by (0) in this pro-cedure shall be controlled by Operations. Those valve numbers in parenthesis ( ) are already aligned per normal operating procedures and should only require operator verification when sampling flow problems are encountered.

3.0 References 3.1 NUREG-0737 3.2 DPC System Health Physics Manual 3.3 Radiological Health Handbook, U.S. Dept. of HEW (1970).

3.4 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev. 1 (1972).

4.0 Equipment 4.1 Shielded Sample Container 4.2 Sample Tongs 4.3 Poly bottles - 60ml (2oz.) size 4.4 Carboy - ~ 1 gal. '

5.0 Procedure 5.1 Initial Conditions 5.1.1 Verbal / written direction for sampling the Reactor .

Coolant System (RCS) has been recieved from the Technical Support Center (TSC).

5.1.2 The specific post-accident analysis requested by TSC:

Boron Chloride i

s

CP/3/A/2002/04A Page 3 of 9

,-s Isotopic Analysis for Iodines

Cesiums Noble Gases Nca-Volatile Fission Products Other (specify) i 5.1.3 Determine by detail planning meeting, the. exact

, course of action and data required.

5.1.4 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel in the sample i hood.  !

5.1.5 Determine and use the required respiratory equip-ment and protective clothing to prevent or minimize .

~

internal exposure in any Planned Emergency situation. '

Use high range and/or extremity dosimetry if required.

5.1.6 Request HP to designate a low dose waiting area while sample is flushing to the LDST.

t Low dose area designated:

5.1.7 Request HP to designate a route from the sample-hood to the lab for the sample shield containing the RCS ,

sample.

Sample route designated:

5.1.8 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the ,

I exposure to personnel, in the lab for the required analysis.

5.1.9 Request HP to perform a constant radiation survey during valve alignment, sample withdrawn, sample i

transportation and analysis.

5.1.10 Prepare two (2) 60 ml (2 oz.) poly bottles. Label one as "RCS Flush" bottle. Label the other bottle

'h as "RCS Sample" bottle. Label both bottles with

. the date and time of sample prior to entering the .

sample hood. l I

i I

CP/3/A/2002/04A Paga 4 of 9 5.1.11 Prepare one (1) carboy (~ 1 gal.). Label as " Post Accident Lab Waste".

5.2 Valve Alignment 5.2.1 Request HP to determine the stay time in the sample room for person performing valv.e alignment for sample recirculation. The stay time should represent the maximum time a person may remain in proximity of the sample hood while performing the valve alignment for sample recirculation. The stay time can vary (with rad levels) as you progress thru the valve line-up.

5.2.2 Perform the following valve alignment within the calculated stay time from Step 5.2.1:

5.2.2.1 Close 4

3RC-63 (C) -

3RC-151 (C) 3RC-89 (C) 3RC-88 (C) 3RC-153 (C) 3RC-87 (C) 3RC-85 (C) 3RC-56 (C)

\ 3RC-143 (C) 3RC-144 (C) 3RC-145 (C) 3RC-146 (C) 3RC-147 (C) 3RC-148 (C)

) 3RC-53 (C) 5.2.2.2 Open (3HP-282) (0)

(3HP-281) (0)

(3RC-57) (0) 3RC-149 (C) 3RC-150 (C) 3RC-154 (C) 3RC-86 (C)

(3RC-64) (0) 5.2.3 Record the pressure across the capillary tube on 3PG-14 (inlet press) and 3PG-15 (outlet) press.).

3PG-14 psig 3PG-15 psig O

,r-.. _,

. . ~ . _ . _ _ _ . _ _ . _ _ _ ,

CP/3/A/2002/04A Pags 5 of 9 ,

5.2.4 Retreat to the low dose area outside the sample room, as derignated by HP, to wait while sample is flushing to the LDST.

5.3 Sample Withdrawal 5.3.1 When the radiation levels on the sample lines peak at maximum, request HP to determine the stay time in the sample room for person taking sample. The stay time should represent the maximum time a person may remain in proximity of the sample hood while drawing the sample and in proximity of the sample un-til it is placed in the sample shield. The stay time can vary (with rad levels) as you progress thru the sample withdrawal.

5.3.2 Perform the following sample withdrawal and storage within the calculated stay time from Step 5.3.1:

5.3.2.1 Grasp and position the open "RCS Flush" bottle, at arms length, beneath the sample point using tongs.

5.3.2.2 Carefully OPEN: 3RC-148 and flush

  • 20 ml into the " Flush" bottle then CLOSE:

g, 3RC-148.

4 ,

, 5.3.2.3 Tightly cap the " Flush" bottle and set aside.

5.3.2.4 Grasp and position the open "RCS Sample" bottle, at arms length, beneath the sample point using tongs.

5,3.2.5 Carefully OPEN: 3RC-148 and flush

  • 20 ml into the " Sample" bottle then CLOSE:

3RC-148.

5.3.2.6 Tightly cap the " Sample" bottle. __

5.3.2.7 Place both poly bottles in the sample shield and replace the sample shield plug.

5.3.2.8 CLOSE ,

l 3RC-150 (C) i 3RC-149 (C) 3RC-86 (C) 3RC-154 (C)

/3 l (__ /

CP/3/A/2002/04A Page 6 of 9 s

5.4 Waste Disposal n  !

5.4.1 Determine by detail planning meeting, the exact course of action to be taken. Under no condition will liquid or solid wastes be disposed of without prior specific HP directions.

5.4.2 Designate a sealable carboy as the " Post Accident Lab Waste" container. This container must be shielded and used as an interim liquid waste dis-posal container for all liquid analytical waste.

5.4.3 Request HP to designate an area whera the "RCS Flush" bottle (s), "RCS Sample" bottless) and

" Post Accident Lab Waste" container may be stored until final disposal.

Storage area designated 5.4.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.

) 5.5 Dose Exposure Evaluation

\ ,j 5.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden analysis, etc., as required. The exposure received may require an occupational exposure penalty.

Higher doses will require a medical decision as to whether an individual can continue in radiation I

work.

6.0 Enclosures 6.1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA.

6.3 Conversion Factors i

i b

O I

CP/3/A/2002/04A

. . Paga 7 of 9 ENCLOSURE 6.1 SHIELD THICKNESS The folicwing equations can be usco as an aid in determining shielding requirements for a sample of RCS after an accident.

given: I=Ie* g E

where: p = p,p N0 *

I/I,'= e m in(I/I g )'= -p,px .,

In(I g/I)

~* *

(eq. A.1.1) p,p where: x = thickness'of absorber (cm)

.1 p = linear attenuation coefficient (c51) p* = mass attenuation coefficient (cm 2/g) @ the energy level (Mev) of'the source

. p = density of the absorber material (g/cm 3)

' p\ I = source intensity.w/zero thickness of the absorber (mR/hr or R/hr) ,"

I = source intensity w/an x thickness of the absorber '(n.R/hr or R/hr)' - .

given: (HVL) I/Ig= 1/2 = EY mP*

In(1/2) = -4,px~

. s (eq. 6.1.2) 0.69q ~

p ,p' s

s ,

A half value . layer .(HVL) is thats. thickness.. (x) of an absorber that will reduce the intensity of the Source"to 1/2 of its initial value.

As a general rule we add one HVL to our absorber thickness calculations for conservati:,m:

y (eq. 6.1.3) . In(Io/I) + 0.593 '

,- g total ,

p,f:

U

.~

\s 4

4, , - . - . , . _. ,..c. , .- ._. .- . - - . ,

l .

CP/3/A/2002/04A

^'

  • I Page 8 of 9

,,,.- y,

~

ENCLOSURE 6.2 j E,.A and R Values for 1% Failed Fuel and DBA i . .

e j! t t

1% Failed Fuel: .<

5

  • 0.34 MeV/ dis. A
  • 0.293 mci /ml i

R = 0.18 inR/hr-mci @ Im for 5 % 0.34 MeV i

100% Failed Fuel or Design Basis Accident (DBA) 5 s 1.14 MeV/ dis. AN 1.324 x 105 pCi/ml

^

R = 0.58 R/hr-Ci @ Im for 5 N 1.14 MeV A direct proportion should exist between E and R for any failed fuel '

value greater than 1% and less than 100%.

i e

I i

l 1

i t

l l

l l

l i

.- CP/3/A/2002/04A Pags 9 of 9  :

ENCLOSURE 6.3 CONVERSION FACTORS Source Activity - (A) 1 Curie (Ci) = 3.7 x 1010 dis./sec. = 2.22 x 1012 dpm I mci = 3.7 x 10 7 dps = 2.22 x 10 9 dpm

1 pCi = 3.7 x 10 4dps , = 2.22 x 10sdpm R _

mR hr-Ci hr-mci Density - (p)

(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm 3 Mass Attenuation Coefficient - (p,)

(p ) for elements and common materials at varying energy levels (MEV) for the source can be found on pg. 137 thru 139 of the

! "Ra'diological Health Handbook."

Distance - (d) l given: 2 2 Ig /I = d /d g where: Ig = Source intensity (mR/hr or R/hr) @ distance (d g)

I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.

I ft.= 0.305 m 3 ft. = 0.914 m

~Y

l CONTROL COPY o

t V

i Form SPD-1002-1  !

l DUKE POWER COMPANY (1) ID No: CP/1/A/2002/04B PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Post Accident Liquid Sampling of the Low Pressure Injection System (4) PREPARED BY: I nt0 . 4.AA. DATE: 15-7 1-TD l (5)* REVIEWED BY: DATE: //

Cross-Disciplinarf ReviewBy:.dfeta.iA,he am t. 1/R:

^

u u /

(6) TEMPORARY APPROVAL (IF NECESSART):

By: (SRO) Date:

t /

\/ By: _

Date:

1 (7) APPROVED BY: / '

l M  % Date: /k 8/

(8) MISCELLANEOUS:

Reviewed /.'.r c u :-id By: M. [ bx Date: //- 30-f /

' Reviewed /s;, r= ~d By: Date:

l i

v )'

, CP/1/A/2002/04B 1 Paga 1 of 9 DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT LIQUID SAMPLING OF THE LOW PRESSURE INJECTION SYSTEM 1.0 Purpose 1.1 To define the steps necessary to sample the LPI when fuel damage is estimated to be greater than 1%.

2.0 Limits and Precautions 2.1 VALVE ALIGNMENTS SHALL NOT BE MADE AND SAMPLES SHALL NOT BE TAKEN WITHOUT PRIOR AUTHORIZAfiON FROM IHE TECHNICAL SUPPORT CENTER (TSC)!

P 2.2 DO NOT ATTEMPT ANY PHASE OF SAMPLING OR ANALYSIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGE!

1

! '- 2.3 Radiation exposure to an individual during all phases of sampling should be limited so as not to exceed a quarterly accumulative ex-posure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively. All personnel will need prior author-ization from TSC to knowingly exceed any exposure limit. The exposure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radiation work.

2.3.1 If necessary to remedy a situation immediately hazardous to life and property; the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.

2.3.2 If necessary to save lives or prevent loss of life and/ or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems. skin of wholebody; or 375 rems extremities.

2.3.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems extremities; or 15 rems other single organ.

2.4 Radiation levels of the sampling area shall be measured continuously during all phases of sampling, and sample preparation and analysis.

2.4.1 Air activity should be determined by use of installed air monitors or through the use of portable air sampling equipment.

E .

1 CP/1/A/2002/04B Page 2 of 3 2.4.2 Area dose rates should be established by the use of in-stalled radiation monitors or by portable radiation survey (y}

/

instrument.

2.5 Portable shielding, remote handling equipment, video equipment, etc., shall be used where practical during sampling, sample preparation, and sample analysis.

2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. Those valves followed by (0) in this procedure shall be controlled by Operations. Those valve numbers in parenthesis

( ) are already aligned per normal operating procedures and should only require operator verification when sampling flow problems are

~

encountered.

3.0 References 3.1 NUREG-0737 3.2 DPC System Health Physics Manual 3.3 Radiological Health Handbook, U.S. Dept. of HEW (1970).

3.4 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev.

. 1 (1972).

4.0 Equipment 4.1 Shielded Sample Container 4.2 Sample Tongs 4.3 Poly bottles - 60ml (2oz.) size 4.4 Carboy - ~ 1 gal. .

5.0 Procedure 5.1 Initial Conditions 5.1.1 Verbal / written direction for sampling the Low Pressure Injection System (LPI) has been recieved from the Technical Support Center (TSC).

5.1.2 The specific post-accident analysis requested by TSC:

Boron Chloride Isotopic Analysis for Iodines

- - , - - , . - , , , - +-. ,..~ -- --- - - - . - - . -- - - - - - - - - - - - - - -

CP/1/A/2002/04B '

Page 3 of 9 l

Cesiums  ;

1 Noble Gases l Non-Volatile Fission Products ,

Other (specify) 5.1.3 Determine by detail planning meeting, the exact course of action and data required.

. 5.1.4 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel in the sample hood.

5.1.5 Determine and use the required respiratory equip- .

ment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation.

Use high range and/or extremity dosimetry if required.

5.1.6 Request HP to designate a low dose waiting area while sample is flushing to the LPI pump suction.

g Low dose area designated:

l l

5.1.7 Request HP to designate a route from the sample hood to the lab for the sample shield containing the LPI sample.

l Sample route designated:

5.1.8 Evaluate the use of portable shielding, remote handling

, equipment, video equipment, etc., to minimize the

, exposure to personnel, in the lab for the required analysis.

5.1.9 Request HP to perform a constant radiation survey during valve alignment, sample withdrawn, sample transportation and analysis.

5.1.10 Prepare two (2) 60 ml (2 oz.) poly bottles. Label one as "LPI Flush" bottle. Label the other bottle as "LPI Sample" bottle. Label both bottles with s the date and time of sample prior to entering the sample hood.

, CP/1/A/2002/04B Page 4 of 9 5.1.11 Prepare one (1) carboy (~ 1 gal.). Label as " Post

/ Accident Lab Waste".

k 5.2 Valve Alignment 5.2.1 Request HP to determine the stay time in the sample room for person performing valve alignment for sample recirculation. The stay time should represent the maximum time a person way remain in proximity of the sample hood while performing the valve alignment for sample recirculation. The stay time can vary (with rad levels) as you progress thru the valve line-up.

5.2.2 Perform the following valve alignment within the calculated ' stay time from Step 5.2.1:

5.2.2.1 Close LP-53 (C)

LP-89 (C) 5.2.z.2 Open (LP-38) (0)

(LP-39) (0)

LP-49 (0)

(LP-51) (0)

(LP-52) (0) 5.2.3 Retreat to the low dose area outside the sample room, as designated by HP, to wait while sample is flushing to the LPI pump suction.

5.3 Sample Withdrawal 5.3.1 When the radiation levels on the sample lines peak at maximum, request HP to determine the stay time in the sample room for person taking sample. The stay time should represent the maximum time a person may remain in proximity of the sample hood while drawing the sample and in proximity of the sample until it is placed in the sample shield. The stay time can vary (with rad levels) as you progress thru the sample withdrawal.

5.3.2 Perform the following sample withdrawal and storage within the calculated stay time from Step 5.3.1:

5.3.2.1 Grasp and position the open "LPI Flush" bottle, at arms length, beneath the sample point using tongs.

.- CP/1/A/2002/04B Page 5 of 9 5.3.2.2 OPEN: LP-53

\s_,/ 5.3.2.3 Carefully OPEN: LP-89 and flush

  • 20 ml into the " Flush" bottle then CLOSE:

LP-89. l 5.3.2.4 Tightly cap the " Flush" bottle and set aside.

5.3.2.5 Grasp and position the open "LPI Sample" bottle, at arms length, beneath the sample point using tongs.

5.3.2.6 Carefully OPEN: LP-89 and flush

  • 20 ml into the " Sample" bottle then CLOSE:

LP-89.

5.3.2.7 Tightly cap the " Sample" bottle.

5.3.2.8 Place both poly bottles in the sample shield and replace the sample shield plug.

5.3.2.9 CLOSE:

LP-53 (C)

( LP-49 (0) 5.4 Waste Disposal 5.4.1 Determine by detail planning meeting, the exact course of action to be taken. Under no condition will liquid or solid wastes be disposed of without prior specific HP directions.

5.4.2 Designate a sealable carboy as the " Post Accident Lab Waste" container. This container must be shielded and used as an interim liquid waste disposal container for all liquid analytical waste.

5.4.3 Request HP to designate an area where the "LPI Flush" bottle (s), "LPI Sample" bottle (s) and

" Post Accident Lab Waste" container may be stored until final disposal.

Storage area designated 5.4.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for

- shielding or protective covering to prevent the spread of airborne activity.

1

, CP/1/A/2002/04B l Page 6 of 9 1 i

5.5 Dose Exposure Evaluation 5.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden analysis, etc., as required. The exponure received may require an occupational exposure penalty.

. Higher doses will require a medical decision as to whether an individual an continue in radiation work.

6.0 Enclosures 6 . '1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA.

6.3 Conversion Factors 4

t

+

5 s i

l

~ . _ _ _ . , . . _ ._ . - . _ _ . . _ . , _ _ . . _._ __________ _ __.-_......,_____ _ , . _ . _ _ _ . _ _ _ _ , _ _ _ , _ . , . . _ , _ . , - , _ , . - - - _ _ , _ _ _ _ _ . . . - - - - . - _ ,

. .- CP/1/A/2002/04B Page 7 of 9 ENCLOSURE 6.1 SHIELD THICKNESS The following equations can be used as an aid in determining shielding requirements for a sample of RCS after an accident.

given: I=Ie* g E

where: p = p,p I/I g =emY P*

In(I/I g) = -p,px in(I g/I)

(eq. 6.1.1) p,p where: x = thickness of absorber (cm) p = linear attenuation coefficient (cIn l) p" = mass attenuation coefficient (cm 2/g) @ the energy level (Mev) of the source

, p = density of the absorber material (g/cm 3)

) I = source intensity w/zero thickness of the absorber (mR/hr or R/hr)

I = source intensity w/an x thickness of the absorber (mR/hr or R/hr) given: (HVL) I/I = 1/2 = e EPg m*

In(1/2) = -p,px x= 0.693 (eq. 6.1.2) p,P A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As a general rule we add one HVL to our absorber thickness calculations for conservatism:

(eq. 6.1.3) In(I o/I) + 0.693 x total ,

p,p

!O s

l y -- -----

- - - -y,-,.---g- - - - - - - - _m- - - - - , -

- - - - . y , - - - - -

. ,. - CP/1/A/2002/04B Page 8 of 9 ENCLOSURE 6.2 5, A and R Values for 1% Failed Fuel and DBA 1% Failed Fuel:

5

  • 0.34 MeV/ dis. A
  • 0.293 mci /ml R = 0.18 mR/hr-mci @ Im for 5 % 0.34 MeV 100% Failed Fuel or Design Basis Accident (DBA) 5s 1.14 MeV/ dis. A
  • 1.324 x 10s pCi/ml R = 0.58 R/hr-Ci @ la for 5 % 1.14 MeV A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 100%.

l

CP/1/A/2002/04B Page 9 of 9 ENCI.0SURE 6.3 CONVERSION FACTORS Source Activity - (A) 1 Curie (Ci) = 3.7 x 1010 dis./sec. = 2.22 x 1012 dpm 1 mci = 3.7 x 10 7dps = 2.22 x 10 9 dpm 1 pCi = 3.7 x 10 4dps = 2.22 x 10sdpm

, R _

mR hr-Ci br-mci Density - (p)

(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm 3 Mass Attenuation Coefficient - (p,)

(p ) for elements and common materials at varying energy levels (MEV) for the source can be found on pg. 137 thru 139 of the

" Radiological Health Handbook."

Distance - (d) given: 2 2 Ig /I = d /d g where: Ig = Source intensity (mR/hr or R/hr) @ distance (d g)

I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.

I ft.= 0.305 m 3 ft. = 0.914 m s

i

. =

Form SPD-1002-1 p, h 1

)

DUKE POWER COMPANY (1) ID No: co/2/A/?n02/04B PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated )

(2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Post Accident Liould Samolinst of the Low Pressure Injection System (4) PREPARED BY: hh DATE: 1 \ -D -6 I (5) REVIEWED BY: DATE: /[ d /

Cross-Disciplinary Review By: N/R: //-Z.Y4f (6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: Date:

Date: A I I (7) APPROVED BY: [ , h Ns n (8) MISCELLANEOUS:

Reviewed /Aquammmeri By:p. M Ww Date: //- 30 -f /

Reviewed /Apuament By: Date:

l t

l v

l l

(

CP/2/A/2002/04B

, Page 1 of 9 I

DUKE POWER COMPANY OCONEE NUCLEAR STATION ,

POST ACCIDENT LIQUID SAMPLING OF THE  !

LOW PRESSURE INJECTION SYSTEM f

1.0 Purpose -

1.1 To define the steps necessary to sample the LPI when fuel damage is estimated to be greater than 1%.

2.0 Limits and Precautions i

! 2.1 VALVE ALIGNMENTS SHALL NOT BE MADE AND SAMPLES SHALL NOT BE TAKEN WITHOUT PRIOR AUTHORIZATION FROM THE TECHNICAL SUPPORT CENTER (TSC)!

2.2 DO NOT ATTEMPT ANY PHASE OF SAMPLING OR ANALYSIS WITHOUT 'IEALTH PHYSICS APPROVAL AND COVERAGE!

. 3.3 Radiation exposure to an individual during all phases of sampling should be limited so as not to exceed a quarterly accumulative ex-posure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively. All personnel will need prior auth-orization from TSC to knowingly exceed any exposure limit. The ex-posure received may require an occupational exposure penalty and/or a medical decisica as to whether an individual can continue in radia-tion work.

2. 3 .1' If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.

2.3.2 If necessary to save lives or prevent loss of. life and/ or extensive damage to property (voluntary basis only), the j Planned Emergency Exposure for Duke Power Personnel will j not exceed 25 rems wholebody; 150 rems skin of wholebody; I or 375 rems extremities. .

2.3.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; I 75 rems extremities; or 15 rems other single organ.

l 2.4 Radiation levels of the sampling area shall be measured continuously l during all phases of sampling, and sample preparation and analysis.

2.4.1 Air activity should be determined by use of installed air monitors or through the use of portable air sampling equipment.

l l

l l

l _. _ _ _ . . - . _ _ . _ _ _ . . _ . _ _ _ _ _ _ . . _ . _ _ _ . _ _ _ . _ _ _ _ . _ , _ . _ -

CP/2/A/2002/04B Page 2 of 9 2.4.2 Area dose rates should be established by the use of in-stalled radiation monitors or by portable radiation survey j instrument.

2.5 Portable shielding, remote handling equipment, video equipment, etc. , shall be used where practical during sampling, sample preparation, and sample analysis.

2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. Those valves followed by (0) in this pro-cedure shall be controlled by Operations. Those valve numbers in parenthesis ( ) are already aligned per normal operating procedures and should only require operator verification when sampling flow problems are encountered.

3.0 References 3.1 NUREG-0737 3.2 DPC System Health Physics Manual 3.3 Radiological Health Handbook, U.S. Dept. of HEW (1970).

3.4 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev. 1 (1972).

4.0 Equipment 4.1 Shielded Sample Container 4.2 Sample Tongs 4.3 Poly bottles - 60ml (2oz.) size 4.4 Carboy - ~ 1 gal.

5.0 Procedure 5.1 Initial Conditions t

5.1.1 Verbal / written direction for sampling the Low Pres-sure Injection System (LPI) has been recieved from the Technical Support Center (TSC).

5.1.2 The specific post-accident analysis requested by TSC:

Boron

, Chloride O

l

r CP/2/A/2002/04B

. Page 3 of 9

,- Isotopic Analysis for Iodines k, Cesiums Noble Gases Non-Volatile Fission Products Other (specify) 5.1.3 Determine by detail planning meeting, the exact course of action and data required.

5.1.4 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel in the sample hood.

5.1.5 Determine and use the required respiratory equip-ment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation.

Use high rangt and/or extremity dosimetry if required.

5.1.6 Request HP to designate a low dose waiting area

. while sample is flushing to the LPI pump suction.

, s_ Low dose area designated:

1 5.1.7 Requert H2 to designate a route from the sample hood to the lab for the sample shield containing the LPI sample.

Sample route designated:

5.1.8 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel, in~the lab for the required analysis.

5.1.9 Request HP to perform a constant radiation survey during valve alignment, sample withdrawn, sample transportation and analysis.

5.1.10 Prepare two (2) 60 ml (2 oz.) poly bottles. Label one as "LPI Flush" bottle. Label the other bottle as "LPI Sample" bottle. Label both bottles with

['~'}

( ,, the date and time of sample prior to entering the sample hood.

CP/2/A/2002/04B ,

Page 4 of 9 5.1.11 Prepare one (1) carboy (~ 1 gal.). Label as " Post .

/N Accident Lab Waste".

5.2 Valve Alignment 5.2.1 Request HP to determine the stay time in the sample room for person performing valve alignment for sample recirculation. The stay time should represent the maximum time a person may remain in proximity of the sample hood while performing the valve alignment for sample recirculation. The stay time can vary (with rad levels) as you progress thru the valve line-up.

5.2.2 Perform the following valve alignment within the calculated stay time from Step 5.2.1:

5.2.2.1 Close 2LP-53 (C) 2LP-89 (C) 5.2.2.2 Open (iLP-38) (0)

(2LP-39) (0)

- 2LP-49 (0)

(2LP-51) (0)

(2LP-52) (0) 5.2.3 Retreat to the low dose area outside the sample room, as designated by HP, to wait while sample is flushing to the LPI pump suction.

5.3 Sample Withdrawal .

5.3.1 When the radiation levels on the sample lines peak at maximum, request HP to determine the stay, time in the sample room for person taking sample. The stay time should represent the maximum time a person may remain in proximity of the sample hood while drawing the sample and in proximity of the sample until it is placed in the sample shield. The stay time can vary (with rad levels) as you progress thru the sample with-drawal.

5.4.2 Perform the following sample withdrawal and storage within the calculated stay time from Step 5.3.1:

5.3.2.1 Grasp and position the open "LPI Flush" i bottle, at arms length, beneath the sample point using tongs.

l l

l l

l

r CP/2/A/2002/04B Page 5 of 9 5.3.2.2 OPEN: 2LP-53 O' 5.3.2.3 Carefully OPEN: 2LP-89 and flush % 20 mi into the " Flush" bottle then CLOSE:

2LP-89.

5.3.2.4 Tightly cap the " Flush" bottle and set aside.

5.3.2.5 Grasp and position the open "LPI Sample" bottle, at arms length, beneath the sample point using tongs.

5.3.2.6 Carefully OPEN: 2LP-89 and flush

  • 20 ml into the " Sample" bottle then CLOSE:

2LP-89.

5.3.2.7 Tightly cap the " Sample" bottle.

5.3.2.8 Place both poly bottles in the sample shield and replace the sample shield plug.

5.3.2.9 CLOSE:

2LP-53 (C) s 2LP-49 (0) 5.4 Waste Disposal 5.4.1 Determine by detail planning meeting, the exact course of action to be taken. Under no condition will liquid or solid wastes be disposed of without prior specific HP directions.

5.4.2 Designate a sealable carboy as the " Post Accident Lab Waste" container. This container must be

! shielded and used as an interim liquid waste disposal container for all liquid analytical waste.

5.4.3 Request HP to designate an area where the "LPI Flush" bottle (s), "LPI Sample" bottle (s) and l

" Post Accident Lab Waste" container may be I stored until final disposal.

Storage area designated l

  • CP/2/A/2002/04B

. Page 6 of 9 5.4.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.

5.5 Dose Exposure Evaluation 5.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden analysis, etc., as required. The exposure received may require an occupational exposure penalty.

Higher doses will require a medical decision as to whether an individual can continue in radiation work.

6.0 Enclosures 6.1 Shield Thickness 6.2 i, A, and R valves for 1% Failed Fuel and DBA.

6.3 Conversion Factors 4

i i

I i

b

f

! CP/2/A/2002/04B

. Page 7 of 9 C ENCLOSURE 6.1 SHIELD THICKNESS The following equations can be used as an aid in determining shielding requirements for a sample of RCS after an accident.

given: I=Ie* g E

where: p = p,p I/I =g EY P*

m In(I/I g) = -p,px In(I g/I)

(eq. 6.1.1) **

p,p where: x = thickness of absorber (cm) p = linear attenuation coefficient (cin ) i p" = mass attenuation coefficient (cm 2/g) @ the energy level (Mev) of the source p = density of the absorber material (g/cm a)

V Ig = source intensity w/zero thickness of the absorber (mR/hr or R/hr)

I = source intensity w/an x thickness of the absorber (mR/hr or R/hr) given: (HVL) I/I = 1/2 = e NE g m*

In(1/2) = -p,px (eq. 6.1.2) ,0.693 p,P A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As.

a general rule we add one HVL to our absorber thickness calculations for conservatism:

(eq. 6.1.3) I"(I /I) o + 0.693

  • total -_ p ,p O

V l

i

i

CP/2/A/2002/04B Page 8 of 9 ENCLOSURE 6.2 ,

5, A and R Values for 1% Failed Fuel and DBA l

1% Failed Fuel: l E

  • 0.34 MeV/ dis. A
  • 0.293 mci /ml i R = 0.18 mR/hr-mci @ Im for 5
  • 0.34 MeV~

100% Failed Fuel or Design Basis Accident (DBA) 5

  • 1.14 MeV/ dis. A
  • 1.324 x 105 pCi/ml R = 0.58 R/hr-Ci @ Im for 5
  • 1.14 MeV A direct proportion sh,ould exist between 5 and R for any failed fuel

]

value greater than 1% and less than 100%.

1 l

4 l

1 I

4 4

i

CP/2/A/2002/04B

. Page 9 of 9 ,

ENCLOSURE 6.3 h

CONVERSION FACTORS Source Activity - (A) 4 1 Curie (Ci) = 3.7 x id10 dis./sec. = 2.22 x 1012 dpm 1 mci = 3.7 x 10 7 dps = 9 2.22 x 10 dpm 1 pCi = 3.7 x 10 4dps = 2.22 x 10sdpm R _

mR hr-Ci hr-mci Density - (p)

(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm 3 Mass Attenuation Coefficient - (p,) ,

(p"eV)

(M for the source can be found on pg.137 thru 139 of the) for elements and c

" Radiological Health Handbook."

Distance - (d) given: 2 2 Ig /I = d /d g where: Ig = Source intensity (mR/hr or R/hr) @ distance (d g)

I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.

1 ft.= 0.305 m 3 ft. = 0.914 m l

f w--+ m+yvp -

=w -my,w- -- - e-- -e- -- - - w-

l i

2 Form SPD-1002-1 g l

v DUKE POWER COMPANY (1) ID No: CP/3/A/2002/04B 1 PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Post Accident Liquid Sampling of the Low Pressure Injection System (4) PREPARED BY: h DATE: I\-U~Dl (5) REVIEWED BY: DATE: /[ d ((

Cross-Disciplinary Review By: /2-) N/R:

(6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: n Date:

lh Date: k (7) APPROVED BY: }

(8) MISCELLANEOUS:

Reviewed /mqmpesmed By: /MMN Date: // ///

Reviewed /SEEEE::ad By: hf [, Date: //- 3 6 - [/

O V

CP/3/A/2002/04B c

Pagn 1 of 9 DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT LIQUID SAMPLING OF THE LOW PRESSURE INJECTION SYSTEM 1.0 Purpose 1.1 To define the steps necessary to sample the LPI when fuel damage is estimated to be greater than 1%.

2.0 Limits and Precautions 2.1 VALVE ALIGNMENTS SHALL NOT BE MADE AND SAMPLES SHALL NOT BE TAKEN WITHOUT PRIOR AUTHORIZATION FROM THE TECHNICAL SUPPORT CENTER (TSC)!

2.2 DO NOT ATTEMPT ANY PHASE OF SAMPLING OR ANALYSIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGE!

. 2.3 Radiation exposure to an individual during all phases of sampling should be limited so as not to exceed a quarterly accumulative ex-

'h posure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4

,/ rems extremities respectively. All personnel will need prior auth-orization from TSC to knowingly exceed any exposure limit. The ex-posure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radi-ation work.

2.3.1 If necessary to remedy a situation Omnediately hazardous to life and property, the Planned Emergency Exposure for

[ Duke Power Personnel will not exceed 5 rems wholebody; 30 l

rems skin of wholebody; or 75 rems extremities.

2.3.2 If necessary to save lives or prevent loss of life and/ or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of wholebody; or 375 rems extremities.

2.3.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems extremities; or 15 rems other single organ.

l 2.4 Radiation levels of the sampling area shall be measured continuously during all phases of sampling, and sample preparation and analysis.

2.4.1 Air activity should be determined by use of installed air monitors or through the use of portable air sampling equipment.

I

CP/3/A/2002/04B Page 2 cf 9 2.4.2 Area dose rates should be established by the use of in-

-g stalled radiation monitors or by portable radiation survey 1 instrument.

J 2.5 Portable shielding, remote handling equipment, video equipment, etc., shall be used where practical during samplin6, sample preparation, and sample snalysis.

2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. Those valves followed by (0) in this pro-cedure shall be controlled by Operations. Those valve numbers in parenthesis ( ) are already aligned per normal operating procedures and should only require operator verification when sampling flow problems are encountered.

3.0 References 3.1 NUREG-0737 3.2 DPC System Health Physics Manual 3.3 Radiological Health Handbook, U.S. Dept. of HEW (1970).

3.4 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291

, Rev. 1 (1972).

[N 4.0 Equipment V 4.1 Shielded Sample Container 4.2 Sample Tongs 4.3 Poly bottles - 60ml (20z.) size 4.4 Carboy - ~ 1 gal. ,

5.0 Procedure 5.1 Initial Conditions 5.1.1 Verbal / written direction for sampling the Low Pres-sure Injection System (LPI) has been recieved from the Technical Support Center (TSC).

5.1.7 The specific post-accident analysis requested by TSC:

Boron Chloride O

\s 1

CP/3/A/2002/04B )

Pago 3 of 9 j i

Isotopic Analysis for Iodines Cesiums Noble Gases Non-Volatile Fission Products Other (specify) 5.1.3 Determine by detail planning meeting, the exact course of action and data required.

5.1.4 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel in the sample hood. ____

5.1.5 Determine and use the required respiratory equip-ment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation.

Use high range and/or extremity dosimetry if required.

5.1.6 Request HP to designate a low dose waiting area while sample is flushing to the LPI pump suction.

Low dose area designated:

5.1.7 Request HP to designate a route from the sample hood to the lab for the sample shield containing the LPI sample.

Sample route designated:

( 5.1.8 Evaluate the use of portable shielding, remote handling l- equipment, video equipment, etc., to minimize the expo:;ure to personnel, in.the lab for the required analysis.

5.1.9 Request HP to perform a constant radiation survey I during valve alignment, sample withdrawn, sample transportation and analysis, l

l 5.1.10 Prepare two (2) 60 ml (2 oz.) poly bottles. Label l one as "LPI Flush" bottle. Label the other bottle l

I p as "LPI Sample" bottle. Label both bottles with

\ the date and time of sample prior to entering the sample hood.

i i

CP/3/A/2002/04B

. Pagn 4 of 9 5.1.11 Prepare one (1) carboy (~ 1 gal.). Label as " Post Accident Lab Waste".

5.2 Valve Alignmeut-5.2.1 Request HP to determine the stay time in the sample room for person performing valve alignment for sample recirculation. The stay time should represent the maximum time a person may remain in proximity of the sample hood while performing the valve alignment for sample recirculation. The stay time can vary (with rad levels) as you progress thru the valve line-ups.

5.2.2 Perform the following valve alignment within the calculated stay time from Step 5.2.1:

5.2.2.1 Close 3LP-53 (C) 3LP-89 (C) 5.2.2.2 Open (3LP-38) (0)

(3LP-39) (0) 3LP-49 (0)

(-

(3LP-51) (0)

(3LP-52) (0) 5.2.3 Retreat to the low dose area outside the sample room, as designated by HP, to wait while sample is flushing to the LPI pump suction.

5.3 Sample Withdrawal l

5.3.1 When the radiation levels on the sample lines peak at maximum, request HP to determine the stay time

, in the sample room for person taking sample. The stay time should represent the maximum time a person may remain in proximity of the sample hood while drawing the sample and in proximity of the sample until it is l

placed in the sample shield. The stay time can vary (with rad levels) as you progress thru the sample with-

, drawal.

5.3.2 Perform the following sample withdrawal and storage within the calculated stay time from Step 5.3.1:

l l

5.3.2.1 Grasp and position the open "LPI Flush" bottle, at arms length, beneath the sample O,' point using tongs.

l l 5.3.2.2 OPEN: 3LP-53

- ~

g - -

'~

... N CP/3/A/2002/04B Page 5 of 9 >

4 \s,

. s -

s 5.3.2.3 Carefully'OPEN: 3LP-8P and flush N 20 ml I

into the 'Tlush" bottle then ~

s CLOSE:

, ,. . .3LP-89. \ '-

q x y .

5.3.2.4 ~ Tightly cap the " Flush"'b'ttle o and set s aside. s s 'y' 5.3.2.'5 'iGrasp and position the open "LPI Sample"

~ ' '

bottle,,at.arma length,.beneath the .

, , sample gioint using tongs.

Carefully OPEN: 3LP-89'and flush N 20 ml 5.3 3 6 _

into the-" J Sample" bottle then CLOSE:

i ,

3LP-89.N N , , s, -s l

1 .N i

5.3.2.7 . Tightly cap the " Sample" bottle.

i N .

-5.3.2.8 Place both poly bottles'in the sample shield"and replace the sample shield'- -

N ,. plu2 ' , - -

X ': x '

5.3.2.9 CLOSf: ~ ,

, ' 3LP-53[ ' (C) i .s s.3LP-49 ' N "(0) . s

, i s i l

5.4 Waste. Disposal s s 1 , ,

[

\\,

s

, 1 N ' ' \x- 3

,s g 5.4.1 x : Determine by detail plan:iing meeting, the exact 1 course of actio::, tc_be ';teken., Under no condition

.s will liquid or solid wastes be. disposed of without prior specific IIF dire'ctions.

5.4.2 Designateasealable' carbo 57as,the"PostAccident

' Lab Waste" container.' This container must be shielded and used as'an interim liquid waste disposal l

, container for all . liquid analytical waste.

5.4.3 Request HP.to designate an area where the "LPI

- Flush" bottle (s), "LPI Sample" bottle (s) and

" Post Accident Lab Waste" container may be l stored until final disposal.

l Storage area designated 5.4.4 In the event an area i,s grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.

\s

CP/3/A/2002/04B  !

Page 6 of 9 i 5.5 Dose Exposure Evaluation 5.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden ,

analysis, etc., as required. The exposure received may require an occupational exposure penalty.

Higher doses will require a medical decision as to whether an individual can continue in radiation work.

6.0 Enclosores 6.1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA. l 6.3 Conversion Factors r

e i

l l

, - , . , - - - . , . , r . - - - - - , - . . . - - . . - - - . - - , , . - - - - . . - - - - , , - . .

CP/3/A/2002/04B

. Page 7 of 9 ENCLOSURE 6.1 v SHIELD THICKNESS The following' equations can be used as an aid in determining shielding requirements for a sample of RCS after an accident.

given: I=Ie* g Y

where: p = p,p l I/I = g EN mP*

4 In(I/I g) = -p,px In(I g/I)

(eq. 6.1.1) p,p where: x = thickness of absorber (cm) p = linear attenuation coefficient (cIn 1) p" = mass attenuation coefficient (cm 2/g) @ the energy level (Mev) of the source p = density of the absorber material (g/cm 3)

I = source intensity w/zero thickness of the absorber n

(mR/hr or R/hr)

I = source intensity w/an x thickness of the absorber (mR/hr or R/hr) given: (HVL) I/I = 1/2 = e YP g m*

In(1/2) = -p,px (eq. 6.1.2) , ,0.693 p,p A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As a general rule we add one HVL to our absorber thickness calculations for conservatism:

(eq. 6.1.3) In(I o/I) + 0.693

, total ,

p,p G

/

/

/

/

/

/- --

CP/3/A/2002/04B '

. Page 8 of 9 4

l ENCLOSURE 6.2 5,-A and R Values for 1% Failed Fuel and DBA i

1% Failed Fuel:

j 5 s 0.34 MeV/ dis. A

  • 0.293 aci/ml R = 0.18 mR/hr-mci @ im for 5 s 0.34 MeV i

t 100% Failed Fuel or Design Basis Accident (DEA)

5 s 1.14 MeV/ dis. AN 1.324 x 105 pCi/mi i R = 0.58 R/hr-Ci @ im for 5 s 1.14 MeV '

l l A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 100%.

i i

4 t

I I

l l

4 i

I

{

CP/3/A/2002/04B

,. Page 9 of 9 ENCLOSURE 6.3 O CONVERSION FACTORS ,

Source Activity - (A) 1 Curie (CL) = 3.7 x 1010 dis./sec. = 2.22 x 1012 dpm 1 mci = 3.7 x 10 7 dps 9

= 2.22 x 10 dpm 1 pCi = 3.7 x 10 4dps = 2.22 x 10 8 dpm R _

mR hr-Ci hr-mci Density - (p)

(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead >

(Pb) = 11.35g/cm 3 Mass Attenuation Coefficient - (p,)

i (p ) for elements and common materials at varying energy levels j) (MEV) for the source can be found on pg. 137 thru 139 of the

" Radiological Health Handbook."

Distance - (d) given: 2 2 Ig /I = d /d g where: Ig = Source intensity (mR/hr or R/hr) @ distance (d g)

I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.

1 ft.= 0.305 m 3 ft. = 0.914 m O

-

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