ML20079L524

Public Version of Rev 2 to Emergency Plan Implementing Procedure 5.7.4, Site Area Emergency Implementing Procedure, & Rev 2 to Procedure 5.7.26, Long-Term Environ Monitoring

ML20079L524
Person / Time
Site:	Cooper
Issue date:	12/27/1983
From:	Whitman D, Windham R NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20079L503	List: ML20079L524 NLS8400029, Forwards Public Version of Rev 2 to Emergency Plan Implementing Procedure 5.7.4, Site Area Emergency Implementing Procedure & Rev 2 to Procedure 5.7.26, Long- Term Environ Monitoring
References
PROC-831227-01, NUDOCS 8401260198
Download: ML20079L524 (14)

Text

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• l EMERGENCY PLAN I!!PLEMENTTNG PROCEDURE 5.7.26 LONG-TERM ENVIRON!! ENTAL MONITORING I. PURPOSE Methods to be used for evaluating long-term environmental consequences and analysis of trends involving key isotopes of radioactive materici released l from the Elevated Release Point at CNS are described in this procedure.

Immediate collection and analysis of samples from impacted areas following an elevated release shall be conducted in accordance with EPIP 5.7.18, Off-Site And Site Boundary Monitoring. Long-term envirormental monitoring c.ad L t end .olf m. c.. Il Lu cunducted la acuerdance wi6h this prucedute.

Appropriate protective measures are discussed.

II. DISCUSSION Formulations are developed for computing actual or potential doses associ-ated with human intake of key isotopes via the terrestrial food chain, inhalation dose rates, and external dose rates from ground deposition.

Protective actions to limit doses associated with each pathway are dis-cussed.

III. REFERENCE MATERIAL i A. CNS Emergency Plan.

B. NUREG 0654, Revision 1.

C. NRC Regulatory. Guide 1.109.

D. Dose Rate Conversion Factors, D.C. Kocher, Health Physics Volume 38, L

Number 4 Page 543.

E. ICRP 59. Working Breathing Rate.

F. CNS Environmental Sampling Program. ,

i IV. PREREOUISITES l

A. A radioactive materials release has occurred and it is necessary to monitor the long-term environmental hazards.

V. LIMITATIONS I

A. None.

VI. PRECAUTIONS A. Use of appropriate protective clothing and equipment.

~~

8401260198 840118 PDR ADOCK 05000298 J F PDR Ravited Ey/Date Reviewed By/Date r te Rev Procedure' P 1 Of R. Windham 11/28/83 D. Whitman 12/24/83 g pg 2 5.7.26 6 Pages

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'II . EQUIPMENT-

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A. Environeental monitoring equipment, as required.

k VII

I. PROCEDURE

A. 1,ong-Term Environmental Monitoring.

1. The NPPD Environment W Division with support from the Radiological Managerj(Chemistry and' Health Physics Supervisor) shall be respon-sible to.:

4.- .  !

a. Asuring. that environlental samples of impacted areas are e

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3. gathered. ,

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b. Sample analysis.

l ji c . -- Identificatihn of trends involving key isotopes.

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d. Calculatina actual or potential doses associated with:

1) ' Human intake of: key isotopes via the terrestrial food chain.

2) Inh'ala' tion > dose rates.

3) External dose

• rates frots ground depostion.

e. Maintenance of records.

2. Off-site Monitoring Teams. are under the direction of the P.adio-logical Assessment Coordinator. Teams may be assigned one or more of the following sampling or computation tasks:

1

4. , Collection and analysis of samples in-accordance with normal

,7 CNS Environmental Sample Program and EPIP 5.7.18. .

b. External dose' rate and count 3' and 3" above the ground. This information mar;be used to determine: '

1) Whole body dose.

I Whole body dose from dose rate measurements can be deter-mined by using the equation:

D = (DR) x ot Exp

'Where:

D = gamma dose (mr or r)

(DR) = gamma dose rate (mr/hr or r/hr) 4 Proccdure Number 'EPIP 5.7.26 Date O-M-D Revision 2 Page 2 Of 6 Pages

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at Exp = exposure time (hr)

2) Noble gas airborne activity concentrations.

Elf the gamma dose rate is known, one can estimate the airborne activity concentration. If the airborne activity concentration is known, one can estimate the gamma dose rate.

, The following equation is useds.

-(DR) = 0.9 x 100 (E) X Wuere:

-(DR) = gamma dose -rate at the location of interest (ar/hr)

E = average samma decay energy (MeV/ dis) for the isotopic mixture in the cloud. Attachment "D" X = noble gas airbgtne concentration at the location of-interent (Ci/m -or uCi/cc) 6 0.9 x 10 = dose conversion factor (DCF)

If the noble gas air concentration is known, the integrated exposure at the location of interest may be estimated utili-zing the equation:

D.= 0.9 x 10$ (E) at Exp X Where -

D = total. gamma dose at the location of interest (nr) at Exp = duration of exposure to the plume (hr) 0.9~x 10' = DCF. .

s Utilizing Attachment "D". Average Gamma Decay Energy, the above equations may be used for any mixture of gamma emit-ting isotopes. These equations are based upon a semi-infinite cloud.

3) Estimate of the ground deposition.

Knowing the gamma dose rate at 3", the ground depostion can be estimated by utilizing the equation:

CD = Ki (DR)

Where:

'CD = ground deposition (aci/m )

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Proccdure Number EPIP $.7.26 Date ld 5) 7*)f)$ Revision 2 Page 3 Of 6 _ Pages

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(DR) = gamma dose rate at 3' above the ground Ki = conversion factor-(uC1/m )'/(ar/hr) for isotope i Where:

ISOTOPE KJ (uci/m )/(ar/hr)

Te-132 35 s I-131 200 Cs-137 130 Note: After the first week use Ki - Cs-137. Since we are dealing with external dose rates, knowledge of the isotopes is often unimportant since the actual dose rate can be measured by the monitoring teams.

3. Determination of thyroid dose due to ir.halatien and consumption of contaminated foods. ,

If the airborne I-131 concentratioa or the gross iodine conceatra-tion is known and the duration of the exposure is known, the thyroid dose is readily determined.

a. Ceneral dose equations for adults.

The inhalation dose equations (for adults) from the various -

iodino isotopes are given below (for exposure time less than or equal to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />):

• 0 Dg3g,= (1.7 x 10 ) (x 131) (At Exp}

D132 = { . x (x (At Exp) 5 Dg33 = (5 x 10 ) g,g33) g3* Exp D g34 = (3.1 x 10') (x 134) ( At Exp) 5 D g33

= (1.5 x 10 ) (x 135) (at Exp)

W re:

D g = thyroid dose from isotope 1 (rem) due to inhalation X; =' concentration of isotope i (uci/cc or Ci/m )

t = exposure (breathing) time (hr)

~ Proccdure Number EPIP 5.7.26  ; D..te I N-M b ,

Revistan 2 Page 4 Of 6 Pages

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Nota: Tha half lives of isotopes 1-132 I-133, I.134, and I-135

_' are.relatively short; thereby effectively decreasing the X concentration value. If the effective g of the mix-ture 1.s greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the thyroid dose is pri-marily from I-131.

b. Adult thyroid dose for an unknown isotopic mixture if the I-131 air concentration is known (Attachment "C").

c, Inhalation thyroid dose to children.

anu worst ag is b cuutits tu 1 year old ano tne dose at enis age f rom a given exposure is about .7 times higher than that calculated for an adult.

d. Determination of thyroid dose from food chains.

Both iodine and particulate settle out'of a plume and result in ground contamination. They enter the various food chains when either animals or humans eat contaminated food-stuffs. This results in irradiation of all organs, but the thyroid dose fzom iodine is usually limiting. -In this section we will discuss the estimation of thyroid dose from fadine via the various food chains.

1) Grass-cow-milk-human chain.

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t This chain represents the limiting case. Once deposition Q

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has occurred, the iodine concentration in milk slowly increases until it reaches maximum concentrations 2 days later. The iodine concentration in milk gradually de-creases to zero over a 3 week period. If the milk from this source is banned within 2 days, approximately 90% of this dose can be prevented.

The approximate relationship between ground deposition and peak iodine concentration in milk is:

uCi of Iodine a uCi of Iodine Litar of Milk 8 m' of Pasture Specific doses may be calculated in accordance with NRC Regulatory Guide 1.109, March 1976. Doses will be cal-culated for 7 month old infants (heaviest milk drinkers) assoming milk was consumed exclusively from cows which grazed on the contaminated land.

Note: A ground survey will yield gross contamination rather than I-131 contamination. .It is recommended that the gross contamination data be assumed to be entirely I-131 for purposes of these calculations.

U =j Procedure Number EPIP $.7.26 Date O -W D Revision 2 Page 5 Of 6 Pager.

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12) - Feed-chicken-egg-human ~ chain. 5 Consumption of eggs from chickens which feed on the conta- '

J, minated ground is another potential dose pathway. Approxi- '

' mately 90% of this dose can be eliminated if the eggs are .

banned within 5 days. Doses may - be calculated in accor- l

-dance with NRC Regulatory Guide 1.109.

3) Vegetable-human-or feed-cow chain.

This . path represents another. potential dose pathway. The -

Jose stow thiu vusev may bu rwouced by 961 ti ta= consump-tion of contaminated crops are banned within 1 day. .

4. ' Determination of radiological effects of particulates.

- Because the particulates vary so widely in their radiological and metabolic characteristics, the exact interpretation of particulate

-results requires-that the isotopes be identified. ,

5 .

.The only isotopes ingested to any significant degree vfaithe food -

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chain pathways are Sr-89 Sr-90, I-131, I-133, Cs-134, and Cs-137. 1 i . Estimates of esounts of various types of food.actually ingested and doses should be determined in accordance with NRC Regulatory

, Guide .1.109 or toalth : Physics Journal, November,1981. Volume 41 1" ~#5,' Page 735. .Dvse calculations should be' determined assuming all'

t ' g; . ingested food is from the contaminated area unless the following

- L' data'is available:.

q ,..n F . a. ' Contamination level ' of particular food-stuff (uci/ga) deter-mined in accordance with EPIP 5.7.18, Off-Site And Site Boun-

-dary Monitoring.

b. . Actual daily intake of particular' food-stuff. are known- (if unknown,' refer to Regulatory Guide 1.109)..

.c. Dose calculation factors for ingestion and inhalation of l

.various isotopes are summarized in' Attachments "A" and "B".

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IX. ATTACHMENTS fA. Attachment "A", Ingestion Dose Conversion Factors.

i B. Atcachment B", Inhalation Dose Conversion Factors (DCF) For Whole Body.

'C. Attachkent "C", Ratio Of Thyroid Dose-Rates From All Iodines To Thyroid

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Dose' Rates From I-131 Versus Effective Age Of Mixture.

'D.- Attachment "D", Average Gamma Decay Energy-Far' Noble Gas Mixtures.

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EMERCE'!CY PLAN IMPLEMENTING PROCEDt'RE 5.7.26 LONG-TERM ENVIRONMENTAL MONITORING INGESTION DOSE CONVERSION FACTORS l

TOTAL DOSE CONVERSION FACTORS (Rem /Ci/INCESTED)

ISOTOPE BONE GI THYROID MARR0'4 LUNG TRACT c_36 - - - - - - . _ ______

C-60 - - - - - - - - -- -- --

Sr-89 2

5.26 x 10 3 5.81 x 10 2 8.53 x 10 4 5.81 x 10 Sr-90 3

2.87 x 10 5 3.74 x 10 3 8.12 x 10 3.26 x 10 Ru-10 ---------- ----- ----------

Ru-106 ---- - - - - - - - - - --- -

Te-132 - - - - - - - --------- - - - - - - -

I-131 2.87 x 10 2 1.56 x 10 2 1.91 x 10 3

1.68 x 10 6 I-132 -- -- - - - - - - - - -- -

I-133 1.48 x 10 2 1.58 x 10 2 1.82 x 10 2 3.21 x 10 5 I-135 - - - - - - - - - - --

4 4 4 Cs-134 4 7.34 x 10 7.31 x 10 9.33 x 10 7.33 x 10 4 4 Cs-131 4 5.61 x 10 5.59 x 10 6.64 x 10 4 5.55 x 10 Ba-140 - - - - - - -

Procedure Number EPIP 5.7.26 Date 2 -n-? 3 i Revision 2 raa. 1 Or i rages

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INHALATION DOSE CONVERSION FACTORS (DCF)

FOR WHOLE BODY, THYROID, AND LUNC WHOLE BODY TilYROID LUNG DCF (a) DCF (a) DCF ISOTOPE (Rem /C1) (Rem /C1) (Rem /Ci)

ADULT INFANT ADULT INFANT- ADULT INFANT l

I-13 12.56 + 3 1.40 + 4 1.49 + 6 1.06 + 7 2.67 + 2 (b) 1.47 + 3 (c)

I-132 - - - - - - - - - - - - - - - -

1.43 + 4 1.21 + 5 1.61 + 3 (b) 8.85 + 3 (c)

I-133 5.65 + 2 4.00 + 3 2.69 + 5 2.54 + 6 '4.30 + 2 (b) 2.36 + 3 (~c)

I-134 ------ -- - - - - - - - -

3.73 + 3 3.18 + 4 1.87 + 3 (b) 1.03 + 4 (c)

I-135 3.21 + 2 1.98 + 3 5.60 + 4 4.97 + 5 1.19 + 3 (b) 6.54 + 3 (c)

Te-132 2.02 + 1 1.26 + 2 2.37 + 1 1.99 + 2 3.60 + 4 (a) 2.43 + 5 (a)

Xs-133 2.60 + 1 (b) 1.60 + 2 (c) - - - - - - - - - - -- ---- --

.. .Xa-135 1.93 + 2 (b) 1.19 + 3 (c) ---- ---- - - - - - --

8 6.38 + 2 (b) 3.94 + 3 (c) - - - - - - -- -

1.53 + 3 (b) 8.41 + 3 (c)

Cs-134- 9.10 + 4 5.32 + 4 ---- ------

1.22 + 4 (a) 5.69 + 4 (a)

Cs-137 5.35 + 4 3.78 + 4 - - - - - - ---- - -

9.40 + 3 (a) 5.09 + 4 (a)

Ru-106 - - - - - - - - - - - - - - - - - - -------- -------

1.17 + 6 (a) 3.94 + 5 (a)

Cc-144 - - - - - - - - - - - - - - - - - - - - ------- - - - - - -

9. 72 + 5 (a) 7.03 + 6 (a)

(a) From NRC Regulatory Guide 1.109 unless foot .oted by (b).

(b) ' From D.C. Kocher, dose-rate conversion factors- for internal exposure to photon and electron radiation from radionuclides occurring in routine releases from nuclear fuel cycle facilities, in Health Physics . Volume 38, Number 4. Page 543, 4/80. The values from D.C. Kochg wgre divided by the breathing rate (BR) to get the DCF in res/Ci. The BR = 2.32 x 10 m /Sec.

-(c) The DCFs are based on the size and density of the organ in question, on the breathing rate, and on specific isotcpic retention factors for that organ. Because retention

~ factor data was not available for infants, the infant DCFs were calculated assuming a ratio of infant to adult DCFs.for other isotopes, for the noble gas whole body, and noble' gas and iodine lung DCFs. This method is not considered to accurately calculate

.DCFs.

.v Preesdure Number EPIP 5.7.26 .Date O -N-Id_ Revision 2 Page 1 Of 1 Pages

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COOPER NUCLEAR STATION OPERATIONS MANUAL EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.7.4 SITE AREA EMERCENCY IMPLEMENTING PROCEDURE s

e. n I. PURPOSE A. The purpose of this procedure is to provide a series of implementing actions to be taken upon declaration of a SITE AREA EMERGENCY.

B. This procedure also directs personnel to use some additional procedures to adequately respond to those conditions classified as a SITE AREA EMERGENCY.

II. DISCUSSION A. A SITE AREA EMERGENCY indicates an event which involves likely or actual major failures of station functions needed for the protection of the public. Radioactive releases may occur but are not expected to require implementation of EPA Protective Action Guidelines.

B. Station resources are anticipated to be sufficient to cope with a SITE AREA EMERGENCY. General Office and necessary contract support resources will be mobilized with selected members dispatched to the site. All emergency response facilities are activated. All non-essential per-sonnel will be evacuated from the site.

C. The decision to make an immediate initial declaration rests with the Emergency Director. Prompt notification is made to the off-site governmental authorities to ensure that sufficient emergency response personnel are mobilized and respond to the event in accordance with their respective emergency plan arrangements.

D. Representatives from Nebraska and Missouri may be dispatched to the EOF. Assessment of off-site radiological pare. meters will be made to determine the type of protective measures necessary for protection of the general public. The general public will be notified of the event by media facilities and periodic updates of information will be re-leased.

E. Station representatives will close out, escalate, or reduce the emer-gency classification as conditions warrant. Written summaries of the event will be provided to off-site authorities.

III. REFERENCE MATERIAL A. CNS Emergency Plan.

B. NUREG 0654, Revision 1.

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Rsvised By/Date deviewed Py/Date Ap Rev Procedure ggprovedBv/Dategyg Page 1 Of R..Windhan 11/21/83 _D. Whitman 12/23/83 .g3 2 5.7.4 3 Pages

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IV.. PREREQUISITES-A. A - SITE AREA EMERGENCY has been declared per EPIP 5.7.1 Emergency Classification.

V. ' LIMITATIONS e

A. None.

VI. PRECAUTIONS A. Ensure all non-essential personnel are evacuated from the site.

VII. EQUIPMENT

/. . None.

VII

I. PROCEDURE

A. Immediate Actions.

~

1.- The Shift Supervisor assumes the role of Emergency Director.

2. The Shift Supervisor implements EPIP 5.7.6, Notification.

. 3. The Shift Superviser directs the Control Room Operator to activate

- f. s the Emergency Alarm for 10 seconds and make the following emergency

, announcement: " SITE AREA EMERGENCY, SITE AREA EMERGENCY. There is a (what) in/at (where). Emergency personnel report to assigned emergency stations. All other personnel, contractors, and visitors evacuate to the CNS Security Building. All personnel stay clear cf the affected-area".

a. . Repeat the alarm and announcement.

b. -Sound alarm for 1 minute.

• 4. . The Division Manager of . Nuclear Operations or his designee may

. relieve.the Shift Sup cvisor of the duties of Emergency Director as soon as he arrives on site.

B. Subsequent Actions.

1. The Emergency Director will perform the following:

a. Determine the need for any additional personnel. Direct the Operations Communicator to call -in additional personnel as needed by contacting the appropriate Department Managers.

Pertinent telephone numbers are contained in the Emergency l Telephone Directory.

'b. Activate the EOF per EPIP 5.7.9, Activation Of EOF.

u Proc 1 dure Number 'EPIP 5.7.4 Date [)-h3-73 Revision 2 Page 2 Of 3 Pages

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c. . Implement EPIPs as required by ccepleting the checklist con-tained D l.**;:hment "A", SITE AREA EhERCENCY Implementing Procedure Checklist.

d. Re-evaluate the emergency classification as conditions change by using EPIP 5.7.1 and provide corresponding information to the on-site emergency response facilities and appropriate governmental agencies.

e. Close out or recommend reduction in the emergency classifica-tion by briefing off-site authorities by telephone followed by a written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of close out or classification reduction.

2. TSC Activation.

a. The TSC Director will assume comtand of the TSC. If this i

emergency response facility has not been previously activated, activate it per EPIP 5.7.7.

3. OSCs Activation.

a. The Mainter ance and OSC Coordinator and the Chemistry and Health Physics Coordinator will implement EPIP 5.7.8, Activation [

Of OSCs. I

/ X . A TACRMENTS

• T A. Attachment "A", SITE AREA EMERGENCY Implementing Procedure Checklist.

L Prcesdure Number EPIP 5.7.4 Date S-2-N Revision 2 Page 3 Of 3 Pages

• '" ' COOPER NUCLEAR STATION OPERATIONS MANUAL AITACHMENT~"A" -

EMERCENCY PLAN IMPLEMENTING PROCEDURE 5.7.4 SITE AFEA EMERGENCY IMPLEMENTING PROCEDURE S I' L '".; . *;Y IMPLEMENTING PROCEDURE CHECKLIST REOUIRED COMPLETED PROCEDURE AS NUMhER PROCEDURE YES REQUIRED DATE TIME EPIP 5.7.1 Emergency Classifications X / /

EPIP 5.7.6 Notification X / /

EPIP 5.7.7 Activation Of TSC X / /

EPIP 3.7.8 Activation Of OSCs X / /

EPIP 5.7.9 Activation Of EOF X / /

EPIP 5.7.10 Personnel Assembly And Accountability X / /

EPIr 5.7.11 Evacuation Of Non-Essential Personnel _ X / /

EPIP 5.7.12 Emergency Radiation Exposure Control / /__

EPID.5.7.13 Personnel Monitoring And Decontamination X / /

EP. $.7.14 Stable Iodine Thyroid Blocking / /

EPIP 5.7.15 Rescue And Re-Entry / /_, '

EPIP 5.7.16 Release Rate Determination X / /

EPIP 5.7.17 Dose Assesreent X / /

EPIP $.7.18 Off-Site And Site Boundary Monitoring X / /

EPIP 5.7.19 On-Site Radiological Monitoring X / /

EPIP 5.7.20 Protective Action Guides X / /

EPIP 5.7.23 Media X / /

EPIP 5.7.24 Medical / / _

EPIP 5.7.25 Recovery Operations / /

EPIP 5.7.26 Long-Term Environmental Monitoring / /

EPIP 5.7.27 Early Warning System / / __

Precsdure Number EPIP 5.7.4 .Date I D - h'35 ~)f d3 Revision 2 Page 1 Of 1 Pages

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