po st-s hot plans and evaluations › ark: › 67531 › metadc...nvo -61 $2- \ project po st-s hot...

NVO -61 $2- \

PROJECT PO ST-S HOT

PLANS AND EVALUATIONS -

D E C E M B E R , 1969

THIS DOCUMENT CONflRMED AS UNCLASSIFIED

DlVlSlON OF CLASSIFICATION BY q, If , /CLAL.,-,~ DATE 1 t '7 7, / y , z

UNITED STATES ATOMIC ENERGY COMMISSION

N E V A D A O P E R A T I O N S OFFICE

L A S V E G A S , NEVADA ORDER FROM CFSTI AS- i:l

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

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NVO -61

PROJECT RULISON PO ST-S HOT

PLANS AND EVALUATIONS

D E C E M B E R , 1 9 6 9

UNITED STATES ATOMIC ENERGY COMMISSION

NEVADA OPERATIONS OFFICE

7 0 This document is LAS V E G A S , NEVADA

Au-thdEing Oficial Date: @6//9/2@?7

e

. . . . . . . . , ! ) ,. , ,

. . ... . . . .

. . .:;:...L . . . . . . . . . . - . . .

POST-SHOT PLANS A N D EVALUATIONS - PROJECT RULISON ,. BACKGROUND -

Project RULISON is a joint experiment sponsored by Austral Oil Company, Incorporated, of Houston, Texas; the U. S. Atomic Energy Commission; and the Department of the Interior. management is provided by CER Geonuclear Corporation of Las Vegas, Nevada, under contract to Austral . study the economic and technical feasibility of using an underground nuclear explosion to stimulate production of natural gas f rom the low productivity gas-bearing Mesa Verde formation in the RULISON Field of western Colorado. ship 7 South, Range 95 West, of Garfield County, about 6 miles SE of the town of Grand Valley. is 8, 154 feet above sea level.

Program

The purpose is to

The project s i te is in Section 25, Town-

Elevation at the surface ground zero

The RULISON experimental program is divided into three phases. Phase I included drilling a pre-shot exploratory well, performing pre-shot gas production tes t s , and geological, hydrological and other studies for technical and safety confirmation. The emplace - ment hole was drilled as a part of Phase I.

Phase II included surface construction, emplacement of the explosive, detonation and measurements of immediate detonation effects. The second phase of the RULISON experiment was completed with the detonation of a 40-kiloton yield nuclear explosive on September 10, 1969. The explosive had been emplaced at a depth of 8,431 feet through a 10-3/4 inch steel casing that was filled to the surface with stemming mater ia ls to contain the energy of the explosion and resulting radioactivity under ground.

A delay of a t least six months is scheduled before reentry. this t ime, the radioactivity in the underground cavity ‘created by the explosion will decay to l e s s than a thousandth of that present twelve hours after the detonation.

During

, *

Phase III’of the experiment involves controlled drillback into the cavity and flow testing to determine the cavity volume and the r a t e at which natural .gas flows from the low permeability reservoi r .

iii

PROJECT RULISON POST-SHOT PLANS AND EVALUATIONS

TABLE O F CONTENTS

Page No.

RULISON SITE PHOTOGRAPH . BACKGROUND. . . . . . . . INTRODUCTION . . . . . . .

. . . . . . . . . . . . ii iii . . . . . . . . . . . .

. . . . . . . . . . . . V BACKGROUND. . . . . . . . INTRODUCTION . . . . . . . PHYSICAL CHARACTERISTICS O F THE RULISON CAVITY . . . . . . . . . . . . . . . . . . . . . . . 1 PRESSURE AND TEMPERATURE EXPECTED IN THE CAVITY. 1 . . . . . . . . . . . . . . . . . . . . . . AMOUNT, NATURE AND DISTRIBUTION O F RADIO- ACTIVITYaIN THE CAVITY . , REENTRY PLAN. . . . . . . RADIOACTIVE SPECIES WHICH DURING REENTRY. . . . . .

_ . . . . . . . . . . . . . 2

2 . . . . . . . . . . . . M A Y ,BE ENCOUNTERED

16 . . . . . . . . . . . . PUBLIC SAFETY CONSIDERATIONS ARISING FROM RELEASE O F RADIOACTIVITY . . . . . . . . . . . . PROCEDURES TO ASSURE PUBLIC SAFETY . . . . . .

18

19

RADIOLOGICAL SAFETY PLAN 19 . . . . . . . . . . . .

APPENDICES

. . . . . . A. MAXIMUM HYPOTHETICAL ACCIDENT A-1 . . . . . . . . . B. ECOLOGICAL CONSIDERATIONS B-1

iv

c- .- / l a i-I

INTRODUCTION /

Project RULISON post-shot plans and evaluations have been made in accordance with the policy prescr ibed in Section 012 of AEC Manual; Chapter 0524, "Standards for Radiation Protection, which states that:

"AEC and AEC contractor operations shall be conducted in such a manner as to a s su re that radiation exposures to individuals and population groups are limited to ' the lowest levels technically and economically practical. "

The planned experimental program to determine the resu l t s of the explosion will include the following:

Reentry into the RULISON cavity, commencing not ea r l i e r than 180 days af ter the shot. r a di oa c t i w i t y -ma-y==b e.-r,e 1 ea s,eAd %--*"

- ~

During-thi.s-p'eriod*a-.few a m i e s *of-ga.seous I

c

t

.RI

/ v o 71

Short- term, high-rate flow tes t s under various meteorological conditions to a s s u r e operational readiness of monitoring systems. The-max-i.mu.m-xolume,of -ga set 0-b e*fYa-d-diir 5flg"the s e-@e sst-s-w-ial.ll-x p cobab 1 y-b e -1 e s s-than- 2 0- M-MS 6 E ,.(mi 1 1 ion,&a.nda r d ,cub i c, , f e-e t ) .. Short- term, high-rate flow testing to evaluate the cavity volume. Du-ring this t ime, 570 to 4070 of the gaseous ~ ~ ~ J i x i t 7 y ~ - m a y - - b e r e - l e a s h F 4 o w ra tes of natural -e gas*a6sGhigh as 20 MMSCF per day may occur. The ankic-ipsted total volume to be flared in these tes t s will be 100,---*20'0 MMSCF. Time dur,ation including shut-in t ime for buifdup between flows, is expected to be abouL2 weeks.

*.*-- 1

-.-- u. .&+@+" --L*

Intermediate t e r m , lower ra te flow tes t s to evaluate dimensions and flow character is t ics of the fracture zone. h-r-i-ng-thi.ss&me, 5Ojo0_~o-3 O y o - o f - t l g a s eo anticipate d--t otalJ.xol~uw.-e 100 - 200 MMSCF. M S C F per day may \

During long-term production testing anddparflal buildup, 5% to 40% of the total>aseous radioactivity,may-be released. Maximum flow

"4, rates of 5 MMSCF\Eer day.may-occur, with the total volume of gas f lared to be 300 - 6O-O-P;iTqSCF. 6 - 8 months.

'1, ,.A ~ Time duration is estimated to be /-

V

These plans should be understood to be subject to changes ar is ing f rom the actual conditions encountered during reentry and testing.

The radiological safety criteria for the RULISON Project were provided in a teletype from the Director, Division of Peaceful Nuclear Explosives, AEC Headquarters to the Manager of the AEC Nevada Operations Office, dated April 11, 1969, the pertinent par t of which is quoted below:

"Post event activities for Project RULISON will be conducted under AEC MC 0524, Appendix 0524, Section I-A - individuals in controlled a r e a s , and Section IIA - individuals and population groups in uncontrolled areas. I '

Radiation exposures to the population around the RULISON site during and following the flaring operations are predicted t o be negligible. Even under the condition of the postulated "maximum hypothetical" accident, operations will be conducted so as to keep the radiation exposure to the nearby population well below the Radiation Protection Guides and still further below the levels of the Protective Action Guides recommended by the Federal Radiation Council.

J

vi

1. PHYSICAL'CHARACTERISTICS O F THE RULISON CAVITY

Diagnostic data obtained at the t ime of detonation, as well as preliminary reports on measurement of ground motion by USC&GS and Sandia Corporation, indicate that the RULISON device behaved about as expected, i. e . , a nominal yield of 40 kilotons.

The geophones near surface ground zero showed a burs t of noise commencing at 48 seconds after detonation and lasting until about 150 seconds. This is consistent with prompt collapse of the cavity t o form a chimney a s might be expected where the cavity p re s su re arises mostly f rom vaporized rock with low water content.

Environmental Research Corporation predictions of cavity dimensions for nominal yield, together with the chimney volume and the void space in the chimney (i. e. calculated from their predictions, a r e

TABLE 1-1

Maximum -

Cavity Radius 108

Cracking Radius 580

Chimney Height 45 I

Cavity Volume 5 .28 x lo6 (or Chimney Void Space)

Chimney Volume 16.5 x 10 6

, the cavity volume), given in TABLE 1- 1.

Mean

90

485

376

--

3 . 0 5 x l o 6

9 .57 x 106

Minimum Units

72 feet

390 feet

301 feet

1.56 x l o6 ft3

4.90 x lo6 f t3

2. PRESSURE AND -- TEMPERATURE EXPECTED IN THE CAVITY The p res su re in the cavity six months after the detonation, based upon wellhead p res su res observed subsequent to detonation, is expected to be within 50 psi of the initial reservoi r p re s su re (2940 psi).

The ambient temperature of the g a s in the cavity six months a f te r the detonation is estimated to be 375O - t 25O F.

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3 . AMOUNT, NATURE AND DISTRIBUTION O F RADIOACTIVITY I N THE CAVXTY

Radioactive nuclei a r e created in the course of a nuclear detonation by fission and neutron activation. at the temperature of molten rock (1500O - 2000° C) a r e entrained in the melt. falls through' the gas . peratures or a r i s e by radioactive decay of normally gaseous elements, especially the noble gases Xe and K r . Some fraction of these species a r e widely distributed throughout the rubble. Fission product chains giving r i s e to such species a r e shown in TABLE 3-1.

Species which a r e not gaseous

Most of the r e s t plate out on the cool rubble as it A few species a r e gaseous at normal tem-

Computer calculations were made to determine the fission products remaining in the cavity 180 days after the detonation. Additional calculations were made of radioactive species ar is ing f rom neutron activation of device components and the surrounding rock. The result of these calculations is shown in TABLE 3-2 . The tri t ium will be distributed among several chemical species which include hydrogen gas , water, tr i t iated methane and other tr i t iated hydrocarbons; the exact partitioning of the t r i t ium among these species will be a function of the thermodynamics of chemical reactions occurring in the cavity, and will vary over a period of time.

4. REENTRY PLAN

0 b j e c tive

It is intended that the reentry into the chimney, which was formed in the R-E Well by the detonation of the nuclear device on September 10, 1969, be made through the R-EX Well which is located on the surface approximately 3 11 ' southeast of the R-E Well (emplacement hole). State of Colorado Oil & Gas Conservation Commission rules and

All mater ia ls and procedures used will be in compliance with

regulations and al l work will be accomplished in a workmanlike and prudent manner.

P r io r to the commencement of the reentry drilling operations in R-EX; preliminary operations involving R-E (Emplacement Well) will be undertaken to determine the ability of the Emplacement Well to produce natural gas and to collect and analyze samples of

and hydrocarbon components contained in the gas . I the g a s produced to determine the nature of the radioactive species

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Nuclide

8 5 K r

8 9 ~ r

9 0 ~ r

1 311

137cs

Half L i fe

10.4 y.

50.4 d.

2 8 y.

8. 05 d.

30 y.

TABLE 3- 1 SELECTED FISSION PRODUCT CHAINS Radiation

(Including Daughters) (d' .> I , ..

10070 8 - 1.46 MeV

100% P- 0. 54 MeV B- 2.27 (d)

. 0270 y 1. 739 (d)

p - 0.61 MeV 8770 0. 25

0. 81

y 0 . 3 6 82%

0 . 6 3 9%

Others

Chain of Formation

85 .o s Se +

B r + 85

3 . 0 m 4.4 h 85Krm 4

1.4 y 85Kr + stable 85Rb

1.2 m 8 9 ~ r -,

5.4 m 89Rb -+

10.4 d 89Sr - stable 89Y

. 6 s 90Br

;3 s 9 0 ~ r

:. 7 m 90Rb + 18 y 9 0 ~ r 4

)4. 3 h 9 0 Y stable 90Zr

Sn + i.4 m I

:3.1 m I3lSb 29h Te (.15)

131

131 m

131

131 Sb 24. 8m Te (. 85)

131

: 9 h I3lTem --L 8. 05d I (.8)

131 I3lTem + 24.8m T e ( . 2 ) 1311 131Te + 8.05d:

1 311 4 12d Xe .-) stable 131Xe(.008) 131

131 m

I + stable 131Xe (0. 992)

137 24.2 s . I 3.9 m 137xe 4

137 m 30 Y 137Cs + 2.57m Ba (.092)

137Cs +

2.57 m137Bam -, stable 137Ba stable 137Ba (0. 08)

-3 - I -

I .

TABLE 3-2

FISSION-PRODUC T AND NEUTRON-INDUCED ACTIVITY IN CAVITY - 180 DAYS AFTER DETONATION

Nuclide

85Kr

8 9 ~ r

9 0 ~ r

9 1Y

9 5 ~ r

95Nb

Half Life Cur ies

10.76 y 0.96 103

50.6 d 0.91 lo5

28i8 y 0 . 5 9 ~ 104

59 d 1.01 lo5

65 d 1.82 l o 5

35 d 0 . 3 2 ~ lo6

lo3Ru 40 d 0.41 lo5

lo3Rh 57 min 0.41 105 I . . . . 5 106RU 1.0 y 1.52 x 10

06Rh 30 sec 1.52 l o 5

13 11 8.05 d 1. 13

133xe 5.27 d 0.86 x

1376s

137Ba

140Ba

30 Y

2.6 min

12.8 d

0.75 x l o 4

0.69 lo4

0 . 3 4 ~ 103

1 4 0 ~ a 40 h 0 .40 103

141ce 32.5 d 0.52 105

1 4 3 ~ r 13.7 d 0.63 lo3

I -4- . . 1 , . .

I

. - .. L . .?.. ' . , , , . _ . ' . . . . . . . . . .. . . . . . . . . . . - .> .

~

I -4- . . 1 , . .

I

. - .. L . .?.. ' . , , , . _ . ' . . . . . . . . . .. . . . . . . . . . . - .> .

~

TABLE 3-2 (Cont'd)

Nuclide

144ce

144Pr

147Pm

3H

7A

9A

14c

Half Life Cur ies

285 d 1.47 x 10 5

5 17.3 min. 1.47 x 10

2 .6 y 0.28 l o 5

1 2 . 2 6 ~ 10 t o 10 3 4:::

34.3

260

5770

::Produced by neutron activation.

p

. - , .. I

-5-

History - R-EX Well

After production testing from the R-EX Well, and pr ior to the detonation of the nuclear device in the R-E Well, the R-EX Well was placed in a state of temporary abandonment through means of filling the casing with cement and water.

The R-EX Well has 7-5/8" casing set to a depth of 6367' and a 5-1/2" casing l iner se t in the interval 5860' to TD 8516'. The abandonment process employed in this hole consisted of setting a competent cement plug in the interval 5465 - 6663'. Water was placed inside the 7-5/8" casing from a depth of 5465' up to 1500' at which point a conventional bridge plug was set . F rom a depth of 1500' to a depth of 300' from the surface, a competent cement plug was placed and, from 300' to the surface, water was placed in the hole.

(Figure 4- 1.) '

The Xmas t ree , consisting of a 10-3/4" x 7-5/8" casinghead placed on the 10-3/4" casing, was used to suspend the 7-5/8" casing. This piece of equipment a lso includes a positive seal assembly between the 10-3/4" surface casing and the 7 - 5 / 8 " protection casing. tubing head with two 2' ' outlets was installed above the casinghead. The 2" outlets on the tubing head a r e presently blanked off. upper portion of the tubing head has a blind flange with a 1/2" opening in which a valve and pressure gage have been installed, the purpose of which is simply to record or measure pressure , if any, and allow removal of pressure prior t o reinstallation of additional X m a s t r e e equipment.

A

The

General EauiDment Test Data

The tested pressure of equipment will be approximately twice the designed working pressure . p ressure at which the equipment may be operated at all t imes and at which it is believed there is no chance of failure because of pres sure .

The designed working pressure is the

The minimum designed working pressure of all equipment (which could be exposed to the wellhead shut-in pressure) that is utilized in connection with the reentry drilling and/or completion and testing of the well, will be 3,000 psi. The minimum factory tested pressure of all this equipment is 6 ,000 psi. In each case, the manufacturer either has or will advise Austral of the designed working pressure and tested pressure of the equipment in accordance with the standards established by the American Petroleum Institute.

-6-

I O 3/4 c

TOP 51/2" L I N E R 5 8 6 0 '

7 5/8" CASING 6367 '

SAND

x

, .

CEMENT PLUG TOP

'b

CEMENT PLUG 5 0 /50 LITE POZ No. 3

AT 3 0 0 '

GUI BERSON BRIDGE PLUG AT 1500 '

CEMENT PLUG TOP AT 5465 '

CEMENT PLUG 5 0 / 5 0 L I T E PO2 No. 3

PERFORATIONS 6 1 4 5 - 4 8 ' 8 6155-6! CEMENT SQUEEZED W/D65 SKS

BOTTOM OF CEMENT PLUG 6 6 6 3 '

M0DEL"N"BRIDGE PLUG AT 7 2 5 0 '

. MODEL "0" PACKER AT 8100 '

MODEL " N " BRIDGE PLUG AT 8 1 9 0 '

I

5 1/2 "CASING AT 8516'TD

OBSTRUCTIONS LEFT IN H A Y W A R D 25-95 (R-EX)- F I G U R E 4-11

- 7 -

The American Petroleum Institute has established cer-tain rules and regulations governing the methods by which these standards a r e achieved. Generally speaking, the largest factor in determining the working or tested p res su re of equipment is the thickness of the s teel utilized; however, with high pressure equipment the type of s teel utilized becomes important. The general procedure followed in the petroleum industry is for the designed working pressure to be equal to or exceed the wellhead shut-in pressure .

0

It has previously been established through the pre-shot reservoir testing of R-EX that the static reservoi r pressure is approximately 2930 psi, thus the maximum shut-in surface pressure will be no greater than 2600, psi. The minimum designed working pressure of the equipment that will be utilized in the various operations is 3000 psi. surface pressure or flowing surface pressure can exceed the designed working pressure . Every piece of equipment which has or will be utilized which could possibly be exposed to such pressure in the various procedures concerned with the original completion and/or the future work, has a designed working pressure of 3000 psi and has actually been tested by the manufacturer. ventional gas well equipment and has been used many t imes suc-

There is no situation under which the maximum shut-in

This equipment is con-

c e s s fully.

Reentry Drilling Control Equipment

The drilling control equipment (Figure 4-2 ) which will be placed on the existing tubing head will meet the standards set by the American Petroleum Institute and will consist of the following:

, . ' J1$

Valve assemblies will be reinstalled on the tubing head which is presently blanked off. Immediately above the tubing head will be installed a hydraulically controlled BOP in which blind r a m s will be installed, 'the purpose of which is to have positive shut-off control of the 7 - 5 / 8 " casing below that point.

Above the blind r a m BOP will be located a casing pool (with comparable working pressure and tes t p ressure) which will have two outlets on which valves will be installed for positive control. valve which can be operated remotely. hydraulically controlled valve will be installed a choke manifold which will allow complete control of the flow of liquids (mud returns) under pressure , i f necessary. liquids will be directed through a separation system or directly to the shale shaker or mud tanks. equipment will be described la ter . )

One of these will be a hydraulically controlled Downstream of the

The

(Separator

. , I - I .

+ SECONDARY I CONTROL UNIT

REMOTE CONTROL i i t ACCUMULATOR R I G FLOOR I

@

I

MUD FLOWLINE

-e--

*.

. . - .

, .

TO SH, KER a 'ANK

I CHOKE MANIFOLD

I CASING t

I , 12" FE SPOOL

i - I I I 4" t y; I I I I !

1 1 I

I I 1 TOTANK i L E G E N D L------.------J

~ C A SINGI I HEAD I R REMOTE CONTROL FE FLANGE0 END r I

I I

SE SCREWED E'ND

2" SE

. I BOP BLOW OUT PREVENTER I

F I G U R E 4 - 2 D R I L L I N G CONTROL ASSEMBLY - 9 -

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

* ' -

Above the casing spool will be installed an,addi in which appropriate pipe rams will be installed which will be of the proper size to positively packoff around the dril l pipe if desired. A dual-ram type will be employed in this position during the use of the inatidn dr i l l pipe s t r ing with the r ams sized to packoff around both, s izes , 3-1/2" and 2-3/4".

tely above this prevent0 Hydril preventor- which also can be pos dr i l l pipe o r , i f necessary, can be completely closed when the dril l pipe is withdrawn from the hole, under which circumstance it acts as a valve.

ff around the I Above the Hydril will be located a flowline spool through which the mud returns can be directed to the shale shaker and mud tanks. remove the cement o r shale cuttings from the mud system.

Above the flowline spool will be located a rotating head which will control the flow of fluids while drilling such that there will be no escape to the drilling r i g floor of either liquid o r gas above this point. so that at all t imes there is a seal exerted around the dr i l l pipe o r kelly which circulates drilling fluids down the dril l pipe and up the annular space through the conventional mud circulation sys tem.

A l l preventor equipment and the hydraulic valves will be , controlled by remote control and a hydraulic accumulator, the purpose of which is to allow the positive control of each of these pieces of equipment f rom either the drilling r ig floor or a remote spot located a safe distance away f rom the r i g location.

All valves and preventor equipment as well as the accumulator and remote control system will be tested to their working pressure (to a s su re continued reliability) as circumstances indicate that it would be desirable.

The purpose of the shale shaker is to

The rotating head is designed

D r i l l String Assembly

The dr i l l str ing assembly from the bottom of the s t r ing through the top will consist of the following and is outlined in general bec'ause each operational phase will require cer ta in pieces of equipment unlike that which will be required for other phases'. described herein will meet A P I standards and will be properly

A l l equipment .J - 10-

selected to meet drilling c r i te r ia . A l l equipment will be that which is conventional and similar to that which has been used many t imes before. No equipment used will be experimental in nature. All mater ia l used and procedures followed will be in compliance with the State of Colorado Oil and G a s Conservation Commission rules and regulations.

Appropriate drilling bit which may, as circumstances require, be cer ta in portion of the casing l iner , 2) conventional rock bit for drilling cement or formation, o r for drilling cement or formation.

1) a tungsten carbide mill for removal of a

3) a diamond bit

D r i l l collars as circumstances require - the s ize of these will be dependent upon the hole s ize being drilled at any given time. The range of s izes will be f rom 3-1/2" to 4 - 3 / , , I . Two dril l pipe floats which will allow fluid to be circulated down through the dr i l l pipe but will not allow fluid to reenter f rom the opposite direction.

An l 'S ' ' nipple - the purpose of which is to allow a positive plug to be se t in the dril l pipe i f such is desired o r required during drilling operations.

A 3- 1 / , I 1 internal, flush modified, dri l l pipe (or a comparable type during the removal of cement f rom the 7 - 5 / 8 " casing and milling of 5- 1 / 2 I f l iner) , and a combination dr i l l s t r ing consisting of the above described dr i l l pipe together with a bottom section of dril l pipe consisting of smaller dr i l l pipe, i. e . , 2 - 3 / 4 " flush joint (during the remainder of drilling in the lower-most portion of the hole after setting the 5- 1 / 2 " l iner in the sidetracked hole). .

A safety valve to be located immediately below the kelly and at the uppermost portion of the dr i l l pipe such that the kelly can be removed af ter closing.the valve, i f such is required.

Above the safety valve will be located the kelly, a hexagonal joint of pipe necessary for the rotation of the dr i l l pipe. A t the upper portion of the .kelly will be a kelly cock. The purpose of the kelly cock is to allow a v a l v e to be closed at the uppermost portion of the kelly s o that the swivel-and hook portion of the drilling equipment can be removed i f it is desirable to do s o while the kelly remains closed in.

-11-

Arrangements will a lso be made such that each of the valves and/or kelly cocks mentioned above can be pressure tested as often as circumstances require.

Reentry Procedure -

After the installation of all the equipment has been made at the surface and all equipment has been amply tested .in accordance with predetermined tes t requirements, the dril l str ing assembly as described above will be inserted into the wellhead control equipment and drilling will commence in the cement at a depth of approximately 300'. The cement plug will be dril led from inside the 7-5/8" casing to a depth of 1500' and, subsequently, the bridge plug at 1500' will be drilled. The water in the interval 1500' - 5465' will become a part of the drilling fluid system. The cement in the interval 5465' to 5860' will then be drilled, after which the cement f rom the inside of the 5-1/2" casing l iner will be drilled to a depth of approximately 6500'. 5-'1/2" casing, the casing l iner hanger will be removed from the hole and- the 5- 1/2" casing will be milled out through the use of a pilot mill to a depth of approximately 6500'.

After having removed the cement f rom the inside of the

P r io r to drilling the cement below the top of the 5- 1 / Z " l iner, the 7-5/8 ' casing will be calipered and pressure tested to determine i t s competency. below the 7-5/8" casing, the 7-5/8" casing seat will be p re s su re tested to determine its integrity.

After milling the 5- 1 /2" casing l iner to a depth of approximately 6500', a conventional whipstock (permanent) will be placed at the uppermost portion of the 5- 1 /2" casing l iner at a depth of approximately 6500'. At this point, the whipstock will be oriented such that the hole to be drilled below that depth can be deviated in such a manner that it will eventually intersect the chimney of the R-E Well (emplacement hole) near the top. location of both the R-E Well and the R-EX Weill is known f rom instrumentation used when the two wells were originally drilled. This data will be used in determining the exact direction and deviation required for the sidetrack operations. A hole, 6-3/4" in diameter, will be drilled below the whipstock point to a,depth of approximately 7600' and a 5-1/2" casing l iner will be se t before

. drilling ahead. The casing point of 7600' is the objective depth; however, drilling conditions may require setting -of the 5- 1 / 2 " l iner at a shallower depth. After setting and cementing of the 5-1/2" cas'ing l iner , a portion of the previous dril l s t r ing will be laid down and a smaller string of dr i l l pipe as a stinger will be picked up and used in the inside of the 5- 1 /2" casing and for drilling below that depth.

After milling the 5-1/2" casing to a point just

The exact bottom hole

0-

- 12-

Drilling below the 5- 1 / 2 " protection l iner will proceed to the point where ample and adequate communic chimney, and there is a i s u r high flow ra tes .

A conventional mud circulation s>stem will be used. consists of pumping drilling fluid'down the dril l pipe and up the annular space between the dril l pipe and casing or open hole. During the la ter course of this drilling i t is anticipated that the mud drilling system will l i terally be lost in the cavity when adequate and complete communication has been attained. Thus, if any of the mud which has been used for drilling purposes has been contaminatedwith radioactive mater ia l , this radioactive mud will be permanently injected into the cavity.

ion has been made with the ce of the ability to flow the well at

This system

It is anticipated that when final and adequate communication has been made by drilling into the chimney, the dril l pipe will be removed from the well under pressure controls which would allow no leakage of gas and/or drilling mud above the surface, and that a production tubing string and production packer would be installed in the well using s imilar procedures. Producti'on tubing would be placed in such a manner that the casing annulus would be adequately sealed off. (Figure 4-3). The wellhead preventor hookup would then be removed and the permanent Xmas t ree , a combination of flanges and valves and choke assemblies, placed on the wellhead for future production testing.

Additional Control and Safetv Features

Flow Control - During early stages and for the greater par t of the drilling operations, the mud discharge from the hole will pass through the flowline, over the shaker screen, and into the tank. It is expected; however, that during the la ter drilling, as gas cutting of the mud will reach an abnormally high level, provisions will be made for the controlled release of the gas-cut mud through the use of a flow control unit. as Figure 4-4.

A schematic diagram of this unit is shown

The flow from the well is diverted'through the appropriate manifold valve, shown on Figure 4-2, to the flow control unit. The s t r eam first passes through an adjustable choke, where the back pressure is automatically controlled, and thence into a separator . The gas separates from the liquid phase and passes on to the flare stack. The fluid and cuttings a r e dumped back to the settling tank, where, re la - tively f ree of gas, the cuttings a r e removed by the shale shaker screen.

The inlet side of the flow control unit, f rom the choke manifold through the adjustable choke, will consist of equipment with a minimum working pressure of 3000 psi. the routine testing of the wellhead drilling control assembly and

I ts integrity can be tested during

' choke manifold.

Y

V

t- v) W

U

-J

LL

0

l- a

a

FIG

UR

E 4

-4

- 15

-

.” . . I, .. . . . -I , . . . ... . . . .,

Ventilation System - The wellhead drilling control assembly will be enclosed and equipped with an air vent system (Figure 4-4). enclosure will be sized to permit working room around the wellhead equipment and will have the air intakes sized to provide at least 100 l inear ft /min. air velocity. shaker will be equipped with a hood and s imilar ly ventilated. (Figure 4-5). f lare stack.

0 This In addition, the settling tank and shale

I

The discharge from this sytem will a l so be made through the

Provisions will be made to place contaminated dril l cuttings, i f any, into suitable closed containers for appropriate disposal.

5. RADIOACTIVE SPECIES WHICH M A Y BE ENCOUNTERED DURING REENTRY

During reentry drilling, radioactivity may be encountered when the dril l enters the cracked zone about the cavity. No particulate material is expected to reach the surface, a s mud circulation will a lso be lost when cracks a r e encountered, and the particulate mater ia l will be flushed into the cavity with the lost drilling mud. Drilling will proceed from this point with lubrication provided by addition of drilling mud to replace that lost to the cavity. While drilling mud is circulating, it will be monitored at frequent intervals. possible that tr i t ium contamination may appear in the mud before circulation is lost .

It is

A s the cavity is approached, the well will be pressurized by the reservoi r gas . dr i l l str ing. Any gas leaking from the drilling equipment will be drawn off with a shroud, and released through a’stack to protect the drilling crew. The gas coming from the well is expected to contain radioactivity in the concentrations given in TABLE 5- 1.

Drilling will continue with containment around the

TABLE 5-1

CONCENTRATION O F RADIOACTIVITY IN THE GAS (Calculated on basis of 1.29 x lo7 M3 gas volume at 10.8 psi, Oo C)

3 Isotope Expected Concentration Ci/cm )

3H 8 x

8 5 ~ r 8 x lom5

146 4 x 10-l0

- 16-

\

a 3

m

w 0

-1

0

I-

d T // za

a

3

w

// o

n

coo--<

ax

-a

a+

z

-

n

a

3 0

S

v)

n

a

w I

-1

-1

,w

B

FIG

UR

E 4-5

- 17-

, .% . -. . . . . , . x l .,..,.., ~ - . . ~ - . . . _. , .. . , .

6 . PUBLIC SAFETY CONSIDERATIONS ARISING FROM RELEASE O F RADIOACTIVITY

Possible Routes to Public Exposure

Radioactive mater ia ls released ,from the RULISON cavity may contribute to public, exposure through three routes. These a r e by 1) exposure to air containing radioactivity, 2) ingestion of radioactively contaminated water or 3) ingestion of radioactively contaminated foods.

Air

Entrapment of particulate mater ia l within the molten rock and rubble produced during the detonation and radiological decay since the detonation have reduced the amount of radioactivity in the RULISON cavity that could be released to a small fraction of that produced. to be those which a r e in gaseous form at the temperature of the cavity. xenon and argon.

Water

The isotopes associated with the gas a r e expected

14C, and the iner t gases - krypton, These are tri t ium,

Radioactivity may be transported through the air with ultimate deposition on surrounding surface water supplies. The radioisotopes to be expected a re : t r i t ium in the fo rm of water vapor, 85Kr, 133Xe, 37A, 39A, and 14C. be incorporated into surface waters as a result of direct diffusion from the air o r as a resul t of scrubbing of the radioactivity f rom a n air mass by precipitation.

Some of this radioactivity may

Food

The mechanisms which transpo’rt radioactivity directly to man can also serve to bring it into his environment where i t becomes indirectly available through secondary routes.

’ common indirect pathway is through milk. Deposition of radioactivity on pasture or feed, and to a l e s se r extent by direct inhalation, may result in the secretion of a percentage of that radioactivity in milk. in the t issue in the same manner.

The deposition of radioactivity on agricultural food crops provides another indirect pathway for the potential exposure of man.

Perhaps the most

Meat animals may accumulate radioactivity

0- 8

” . F

- 18-

Deposition on soil may make radioactive mater ia ls available for later uptake by plants during the growing season.

7. PROCEDURES TO ASSURE PUBLIC SAFETY

Operational procedures to a s su re compliance with established safety c r i te r ia a r e summarized as follows:

a. Trit ium and krypton concentrations will be measured in the gas at the time of flaring. isotopes i f present will be documented by appropriate sampling and analysis.

The types and amounts of other

b. Meteorological support will be available to provide predictions of t ra jector ies and concentrations of effluent. Director of Nuclear Operations will use this information to determine that the operation may continue within established safety c r i te r ia .

The

c . Samples of air, water and food will be collected in populated a r e a s and analyzed. F rom these analyses, radiation dose to the public will be calculated and action will be initiated, if necessary, to maintain compliance with the established safety cr i ter ia . (See p. vi).

Par t icular emphasis will be placed on surveillance of Battlement Creek water to a s su re the safety of the families using it. Creek water u s e r s and TABLE 7-1 indicates the water use.

Figure 7-1 indicates the location of Battlement

d. Instruments and procedures to be used in assuring public safety a r e detailed in the following section.

? ? .

8. RADIOLOGICAL SAFETY PLAN

This plan is intended to extend the Project RULISON Safety Plan issued for Project RULISON on August 15, 1969. Radiological control and m'onitoring into the RULISON chimney and during the subsequent production

'- testing by contractors and affiliated agencies will be as'outlined j ' below.

rocedures to be observed during reentry

- 19-

I Ib 0 1

v v

MONUMENT GULCH

I 13 CIRCLED NUMBERS INDICATE INDIVIDUAL RESIDENCES.

3 MILES

LOCATION OF B A T T L E M E N T CREEK WATER USERS

TABLE 7 - 1

..

MAP NO.

1.

2 .

3 .

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

BATTLEMENT CREEK WATER USERS

HOUSEHOLD GARDEN ORCHARD ALFALFA

X X

X X (Some truck garden sold)

X X

X

X

X

X

X X

X X

X X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

-21-

TABLE '2- 1 ,(.Cont'd)

BATTLEMENT CREEK WATER-USERS

21.

22.

23.

24.

25.

26.

27.

28.

29.

30.

HOUSEHOLD

X

X

X

X

X

X

X

X

GARDEN, ORCHARD

X

X

X

X

X

X

- x

ALFALFA

X

X

X

X

X

-22-

RADIOLOGICAL SAFETY (WORK AREA)

Responsibilities

Radiological safety responsibility within the work area will be delegated to the Operations Director (OD) by the Director of Nuclear Operations (DONO) during the reentry and initial flaring. When the'OD assumes responsibility for radiological safety, he i s responsible to the DONO to a s s u r e that the radiological safety program is conducted within c r i te r ia established for the work a r e a .

Support

The Eberline Instrument Corporation (EIC) will provide radiological safety support services for the DONO and to the OD as required. Sufficient personnel will be provided to periodically monitor the dril l r i g as well a s to operate a n on-line gas monitoring system.

Personnel Monitoring

Personnel monitoring will be conducted as necessary by the use of individual personnel dosimeters and bioassays.

Sampling and Analysis

To ensure complete control of the situation in the work a rea , sampling and analysis to establish environmental factors will be conducted as directed by the OD. will not necessarily be limited to the following:

Such sampling will include, but

A i r samples will be collected and analyzed for appropriate contaminants (e. g. , particulates, vapors).

Surface' swipes will be taken routinely in all work areas to determine i f contamination is present. . \

Control of Radioactive Sources and Contaminated Materials and Equipment:

The OD will establish procedures to ensure that all radioactive mater ia ls brought into the work a r e a will be regis tered. . .

Control of radioactive mater ia ls entails surveillance 'of the mater ia l during receipt, possession, transportation, u se and storage.

- 2 3 -

The user scientific laboratory, agency or organization is ' responsible for notifying the EIC when receipt, movement o r t ransfer of any radioactive mater ia l i s to be initiated.

Materials o r equipment which a r e to be removed from '

be monitored, packaged and labeled in ith requirements of the Department of

Transportation (DOT). contaminated and/or radioactive mater ia l 'from. the a r e a will be established by the DON0 to ensu re compliance with all pertinent regulations and rulings.

Procedures for the remobal of

Facil i t ies and Equipment

r, Basic facilities yhich will be used in the working a r e a to provide radiation monitoring services for the Project RULISON drillback

escribed below. The Access Control and Radiological rements facilities will be outfitted, moved to ir operating

location and put into a condition of operational readiness pr ior to initiation of d r illback.

The Access, Control Facility will be positioned a t the entrance of the work a r e a and will: . f

Provide a control point for access into the work a r e a .

Provide a personnel monitoring and decontamination station' for persons leaving the work a rea .

Serve as a facility for the issuance and return of personnel dosimetric devices , anti - contamination (Anti - C) clothing, and portable instruments for detecting radioactive mater ia l , explosive mixtures, and toxic gases.

Serve a s a headquarters for radiation monitoring personnel.

The Radiological Measurements Facility will be equipped for analysis of air samples; for maintenance, calibration and tes t of monitoring equipment; for special process measurements (STALLKAT); and for a limited bioassay capability.

Decontamination - A steam-cleaning capability for equipment decontamination will be provided. laundered by a commercial decontamination laundry.

Contaminated clothing will be

-24- *

Control and M.onitoring of Radioactivity Release to the Atmosphere

Drilling - C irculated Mud S y s tem

During this operation, the drilling control and containment gear , the shale shaker and settling tanks will be shrouded by suitable fixtures. to ensure in-flow of controlling air cur ren ts , i. e . , a minimum of 100 l inear feet per minute a i r velocity into all openings. Suffici- ent in-flow will be provided to keep the atmosphere in the enclosures below the lower explosive l imits of the gas leaking from the containment system on off-gassing from recirculated mud. Enclosed places will be monitored by probes for explosive gas mixtures . a l a rm system.

The enclosures will be exhaust-ventilated at a rate

Probes will be connected to a centrally located readout and

The exhaust air will be vented to the atmosphere through a single stack. the following manner:

Monitoring of the exhaust stack will be accomplished in

The System to Analyze Low Levels of Krypton and Trit ium (STALLKAT), and/or the U . S. Bureau of Mines type detection system, will be employed to continuously monitor this exhaust air s t r eam for krypton and t r i t ium. the air s t r eam will be obtained to provide correcting factors for particulate and condensate fractions of the gas system.

Grab samples of

The exhaust s t r eam will be sampled continuously for particulate mat ter , gases and water vapor. A minimum of one sample per 8-hour shift will be collected and analyzed. More frequent sampling will be accomplished as experience indicates.

A sensitive gamma monitoring instrument will be utilized t o record gross gamma radiation levels associated with the effluent passing through the stack.

Production Testing

Gas produced by the well in the production tes t period will be processed’by a separator into three product s t r eams , i. e . , 1) gas s t r eam, 2) water , and 3) condensate (hydrocarbon liquid comparable to a low-grade gasoline). - A l l product s t r eams will be discharged through a seventy-foot-high flare stack. The natural g a s s t r eam will be discharged directly through the stack; the water will be converted to s team and injected a t the f lare; and the condensate will be discharged into the stack. The various process

-25 -

s t r eams will be monitored to determine the amount of radioactivity re leased to the atmosphere per unit time, as follows: 0

, I Main Gas Stream

The System to Analyze Low Levels of Krypton and Tritium (STALLKAT), and/or the U. S. Bureau of Mines type detection system, ,will obtain a sample of the main gas s t r eam just before the s t r eam enters the flaring stack. Samples will be analyzed a t a minimum ra te of one per hour.

Continuous sampling of the stack for particulates, gases and water vapor will be accomplished. Frequency of sample analysis will be dictated by experience and flow- through ra te of the production gas , but will be no l e s s than once each 8-hour shift.

L t

Water Fraction

A representative sample of the water from the separator will be collected pr ior to discharging any volume increment of the water to the f lare stack. The water will be analyzed for tr i t ium and subjected to a gamma pulse height analysis. Suspended and dissolved solids in the water will be beta counted and subjected to gamma pulse height analysis.

Condensate Fraction

The condensate fraction will be oxidized and analyzed by the procedures outlined above for the water fraction.

RADIOLOGICAL SAFETY (PUBLIC)

Re spans ibilitie s

The Southwestern Radiological Health Laboratory (SWRHL), U. S. Public Health Service, is responsible to the Atomic Energy Commission for providing the Public Radiological Safety Program for Project RULISON, under the general direction of the Director of Nuclear Operations. The operational procedures which will be followed for the Public Radiological Safety Program during the reentry (drillback) and production'testing or flaring phases of the project aLre outlined below.

SWRHL is responsible to the Director of Nuclear Operations for radiological services including the following:

- 2 6 -

Determine by fixed station and mobile monitoring and, i f necessary, by aer ia l surveys, the extent of any contamination resulting from the operations.

Maintain a comprehensive record of public radiation monitoring data associated with the operation.

Ensure continuing protection of the public health, which will include the sampling of various types of environmental media such a s air, water, milk, soil, vegetation and animal t issue, as required.

c

A.s requested by the Director of Nuclear Operations, investi- gate incidents that might possibly be attributed to the operation.

P rogram planning and field activities will be performed by the SWRHL Environmental Surveillance Program personnel. Colorado Depart- ment of Health officials have been consulted on the planning and will participate in the execution phases of the surveillance program. Field and support personnel will consist pr imari ly of personnel f rom SWRHL, supplemented when possible by personnel f rom the Colorado Department of Health.

Siirveillance Plan

The environmental surveillance plan for the drillback and flaring programs will consist of surface monitoring, supplemented with ae r i a l monitoring as required. The intensity of the surveillance program during various phases will depend on such parameters as the initial surveillance resul ts , flaring and radioactivity re lease r a t e s , meteorological conditions, and productivity of foodstuffs in the area of concern during the t ime of the operations.

Surface monitoring will involve reestablishing SWRHL environmental surveil lance networks operated in the RULISON a r e a for the detonation period in 1969, and the operation of special-purpose manned sampling stations. The field personnel will be furnished with two- way radio equipped vehicles. tracking and sampling of gaseous re leases with specially equipped SWRHL,aircraft. samples pr ior to any re lease of 'radioactivity. These samples will include food and water used by selected wildlife, domestic livestock and humans. ' The emphasis will be on t r i t ium levels, although levels of other fission and activation products will a l so be documented

Aerial monitoring may include

The program will include collection of background

Throughout the first few days of flaring, an intensive special-purpose monitoring program will be conducted. This will entail manning

-27 -

monitoring stations and possibly aer ia l sampling systems positioned in accorklance with meteorological guidance for both daytime lapse and nighttime drainage conditions. 0 . < Direct reading monitoring systems will be employed during cer ta in periods in the drillback and flaring programs to a s s i s t in the timely assessment of radiological situations. These devices will include portable sarvey instruments to measure external radiation levels , and tri t ium and krypton measuring devices capable of detecting a t l eas t 10 microcuries of tr i t ium per cubic meter of a i r .

. I

Other monitoring activities a r e described below. (See TABLE 8-1. ) I A i r Sampling

The fifteen a i r sampling stations originally established for Project RULISON will be reactivated pr ior to initiation of the drillback procedure and operated through the initial ,flaring and as long a s the radiological situation warrants . samplers a r e equipped to collect continuous particulate filter and charcoal cartridge samples, and will be located a t the populated locations and communities shown in Figure 8- 1.

Approximately five of these stations, located in the predominantly downwind directions from the s i te , will a lso be equipped to collect atmospheric moisture samples for analysis for t r i t ium.

These

. Particulate samples will be collected beginning one week pr ior to initiation of reentry. Charcoal car t r idge sample collection will begin pr ior to the beginning of reentry and continue as r e - quired to document any releases of radioactivity. moisture samples will be collected during the drillback and flaring phases of the program.

Four Air Surveillance Network stations from the 103-station SWRHL network in the western s ta tes a r e located at Durango, Grand Junction, Denver and Pueblo, Colorado. Data from ' these stations will be available in support of the drillback and flaring of Project RULISON. Samples from this network a r e collected daily.

Monitoring personnel will c a r r y portable a i r samplers during drillback and flaring operations to supplement the fixed stations. These monitors will be equipped to collect particu- la te , gaseous and atmospheric moisture samples. Molecular sieves, si l ica gel, and/or cryogenic samplers will be used to collect samples for analysis of tr i t ium, 14G and 85Kr.

Atmospheric

-28-

TABLE 8 - 1

ANALYTICAL PROCEDURES - TECHNICAL SERVICES - SWRHL

Sample, Type

A. i r F i l te r

a) Glass-Fiber

I N 9 I

b) Charcoal

Milk

.B

I-

T

T

Count Analysis Instrumentation Length

3H

Low Background 2 min. Wide Beta I

Gamma Spectro- 10 min. meter

* I

' . meter

Gamma Spectro- 20-40 me te r min.

Detectable Analytical Procedures Limits Notes

Gross activity at t ime of count. Repeated ceed 4 t imes counts for extrapolation 2-Sigma count- t o estimate activity at end of collection time.

Net counts ex-

ing e r r o r .

8x8 Matrix solution. 0 . 1 p ~ i / m 3 50-100 pCi total Selected isotopes speci- f ied in equations' solution.

in sample /isotope

Gross count with warn- 0. 1 pCi/m3 50-100 pCi total ing limit se t at 300CPM Single isotope in sample/isotope above background over 0-2 MEV energy range. Isotopic analysis by 8x8 Matrix solution.

Isotopic analysis by 8x8 Matrix solution.

20 pCi/m3 1311

20 pCi/l 137Cs isotopes) detect- 20 pCi/ l 140Ba- able limit will La

If masking occurs (presence of other

vary.

Liquid Scint. 100 min. Collect water distilled f rom Milk 0 . 4 pCi /mlH20 Based on minimum

of 5 ml

TABLE 8 - 1 (Cont'd)

ANALYTICAL PROCEDURES - TECHNICAL SERVICES - SWRHL '

Sample, Type - Analysis Instrumentation

8 9 ~ r

9 0 ~ r

Water

I w 0 I

Low Background Wide Beta 11

Low Background Wide Beta Il

Gamma Spectro- meter

Wide Beta 11

Wide Beta 11

Wide Beta Il

Wide~Beta 11 . . ,

3H lator

, * Liquid Scintil-

0 I.

Count Length

50 min.

50 min.

20-40 min.

50 min.

50 min.

50 min.

50 min.

100 min.

Detectable Not e s Analytical Procedures Limits. I-.

Chemical separation by 5 pCi/ l 89sr 90Sr analysis ion-exchange method. dicta)ted by p res - Separated sample counted successively; activity 2 pCi/ l 40Ba -La calculated by simultaneous equation solution.

ence of 1311, o r

Isotopic analysis by 20 pCi/1 8x8 Matrix solution.

Sample dried, gross 2 pCi/ l activity calculated.

2 pCi/ l

Chemical s.eparationby 5 pCi/ l 8 9 ~ r , 90sr analysis ion- exchange. Separated dictated by presence sample counted succes- 2 pCi/ l of 1311 o r 140Ba-La sively; activity calculated by solution of simultaneous equations.

Sample prepared by . 400 pCi/l distillation. Counted in liquid scintillation counter.

TABLE 8-1 (Cont'd)


C ount Length

10-20 min.

10 min.

100 min.

30 min.

100 min.

100 min.

Detectable Limits Sample, Type Analysis Instrumentation Analytical Procedures Notes

Feed (Cow) Y

Vegetation 3'

Gamma Spectro- me te r

Isotopic analysis by 8x8 Matrix solution.

50 pCi/kgm

Quantitation only within order of magnitude for select isotopes.

Gamma Spectro- me te r

Gross activity calcu- 1 a t e d. analysis.

Qual it ative

3H ' Liquid Scint. Separate water f rom ve get at i on.

0 . 4 pCi/ml water

Based on a minimum of 5 mls of moisture .

A i r I w a ) Grab X e & K r I t@ w

Glass envelope Geiger counter

0 . 3 m 3 usual

sample size. Inert gases separated from air sample and beta counted. Xe & K r activity concentration is calculated.

100 pCi total s amp1 e

b) Molecular Sieve

1. Ambient H & 4C 3H 0.4pCi/ml>:: Based on a mini- H 2 0 mum of 5 mls -' 14C 6 pCi/m3 moisture .

air

Water and GO2 removed from sieve and collected. Water analyzed for 3H and CO2 for 14C by liquid scint. counting.

Water, C02 and noble gases removed from sieve, separated and col- 1 e c t e d. Water analyzed for 3H and C 0 2 for 14C by liquid scintillation.

Liquid s cintil- lation counter

3 3H 0 .4 pCi/ml:k 1. 5-4.0 m H O sample s ize 12C 6 pCi/rn3 air

usual 2. Cryogenic 3 H & 14C Liquid Scint .

:::I- 8x10 3 pCi /m 3 a i r depending on relative humidity in anticipated range.

' I . : '- TABLE 8-1 (Cont'd)


Sample, Type Analy si s

Air 2.Cryogenic X e & K r

(Cont 'd)

c) Freezeout 3H

Natural G a s Rn

Animal, W i l d l i f e , Vegetation & Soil

Animal & Wildlife

I

c

3H & I4C

Xe & Kr

3H

CT 8 9 ~ r

9 0 ~ r

De t ec tabl e Count Instrumentation Length Analytical - Procedures Limits Notes

Glass envelope Xe & K r fract ions beta Geiger counter counted in glass enve1.- total sample

ope Geiger counter.

Xe & K r 100 pCi

Liquid Scintil- 100 min. Air passed over cold 3H 0.4 pCi/ml::: 3-6 l i t e r s per lation counter t rap to f reeze out mois - H20 minute sampling

ture. W a t e r analyzed rate. Sample for tritium. s ize varies.

Rn-Alpha Scint- 60 min. Rn-direct t ransfer to Rn-0.04 pCi/ l 100 ml Alpha illation counting Alpha scintillation scintillation

cell and counting. cell.

Liquid Scintil- 100min. Gas is combusted and 20 pCi/ l (14C) About 4-1 burned lation counting noble gases, water and 1 pCi/ l (3H)

CO2 are separated.

Glass envelope 30 min. 100 pCi Total Sample About 12-1 Geiger counter 100 pCi Total Sample Burned.

Liquid Scintil- 100min. Prepared by distillation . 4 pCi /ml of De t ec tabl e l imits la tor of H20 f rom sample H20 based on minimum

of 5 ml of H20

Gamma 20-40 Isotopic analysis by 50 pCi/Kg Spectrometer min. 8 x 8 matrix solution '

Low Background 50min. Chemical separation 5 pCi/sample Wide Beta I1 by ion-exchange

Low Background 50 min. Chemical separation 2 pCi/sample Wide Beta I1 by ion-exchange

I

Various animal organs- analyzed separately Usually only done on bone sample

Usually' only done on bone sample

TABLE 8-1 (Cont'd)

ANALYTICAL PROCEDURES - TECHNICAL SERVICES - SWRHL '- 0 .L

Count De t e c tab1 e Sample, Type Analysis Instrumentation Length Analytical Procedures Limits Notes -

r Soil

8 9 ~ r

9 O ~ r I w w

Gamma 10-40 Qualitative Analysis Quantitative anal- Spec t r omet e r min. ys i s not usually

performed because of U and Th in soil.

Low Background 50 min. Leach S r from soil. 5 pCi/sample Wide Beta 11 Chemical separation

by ion- exchange.

Low Background 50 min. Leach Sr from soil. 2 pCi/sample Wide Beta 11 Chemical separation

by ion-exchange. I -

Descriptions can be found in Document NVO-28, USAEC Publication, Revised 1968.

Detailed procedures a r e presented in "SWRHL Analytical Procedures Manual" SWRHL.

Instrumentation Description: a) Gamma Spectrometer; 4" x 4l' NaI(T1) detector, 200 channels calibrated at 10 kev (channel detector enclosed in a steel box with 6"-thick walls, with lead, cadmium and copper lining).

b) Wide Beta I, pure methane gas flow, 4" hemispherical detector with anti- coincidence guard ring and automatic sample changer with 60 sample capacity.

c ) Wide Beta 11, pure methane gas flow, 2" hemispherical detector with anti- coincidence guard ring and automatic sample changer with 80 sample capacity.

d) Liquid Scintillation Counter. Ambient temperature.

3 3 pCi/m :! 1-8 x 10 NOTE: Detectable limit for 14C in air (Air b) based on assumption of 0. 03% CO2 in A i r .

air depending on relative humidity in anticipated range.

Dosimetry

Eight thermoluminescent dosimeter (TLD) stations will be established pr ior to drillback in a five -mile circular a r r a y around the si te. located at the air sampling locations l isted below and shown in Figure 8-1. the immediate a r e a of the site.

Twelve additional TLD stations will be

Additional TLD stations will be established in

De B eque Grand Valley Rulison Rifle Silt Glenwood Springs

C ollb r a n C arbondal e Paonia Silt Mesa Mesa Grand Junction

Each thermoluminescent dosimeter station will be equipped with three EG&G TL- 12 thermoluminescent CaF2:Mn dosimeters with a sensitivity range f rom 5mR to 5, 000 R. will be placed a t the respective stations one week preceding the beginning of drillback and exchanged and read at monthly in te r - vals until the operation is completed.

These devices

During drillback and flaring, monitors will c a r r y additional TLD's for issue to residents and for supplemental u ses . These TLD's will be collected at intervals and returned to Las Vegas for reading.

Milk Sampling

The SWRHL Standby Milk Surveillance stations in Colorado and other western states will be sampled a s necessary. Standby stations in Colorado are located at:

Craig Colorado Springs F o r t' C ol lins Durango Glenwood Springs Monte V i s t a G rand Junction Alamosa Delta Rocky Ford Salida

The SWRHL Rulison Milk Surveillance Network consists of five Grade A dair ies and ten family milk cow locations shown in Figure 8-2. The Grade A dair ies a re :

- 3 5 -

I J

0

0-

Alex Urguhart Dairy, Rifle Rockin Pines Dairy, Molina Cecil Young Dairy, Collbran Rupert Wasson Dairy, Mesa Glen Taylor Dairy, Molina

Milk samples will be collected at all stations during the week preceding drillback operations, Samples will continue to be collected at regular intervals throughout the drillback and flaring operations as necessary. Information on location of all family milk cows within 10 miles will be updated and selected locations sampled pr ior to and during the operation as necessary. Selected samples, pr imari ly those nearest the s i te , will be analyzed for t r i t ium in addition to gamma emit- t ing radionuclides and radiostrontium.

Water Sampling

The SWRHL Rulison Water Surveillance Network will be r e - activated for the post-event operations. consist of:

The network stations

Twelve municipal supplies within 25 miles of the RULISON si te , plus municipal supplies a t Glenwood Springs, Carbondale, Paonia, Cedaredge and Redstone.

Five private wells in the a r e a immediately surrounding the s i te , and a special well on Battlement Creek near the USGS gauging station above Morrisania Mesa.

Three springs in the a r e a immediately surrounding the s i te .

Four Reservoirs -

Vega Reservoi r , near Collbran Harvey Gap Reservoir , 6 mi les north of Silt Two representative reservoi rs in the Grand Mesa area

Nine S t reams -

Battlement Creek - daily samples just below the s i te

Plateau Creek - 1 mile south of Collbran Wallace Creek - Wallace Creek School Cache Creek - intersection with Holmes Mesa Road Parachute Creek - Grand Valley

and on Morrisania Mesa

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i

Buzzard Creek - 6-1/4 miles east , 1 /2 mile north

Mamm Creek - Rifle Airport W e s t ,Divide Creek - Fairview Colorado River - DeBeque'

of Collbran

Water samples will be collected during the week preceding drillback and periodically throughout the flaring procedure as necessary. ling stations.

Figure 8 - 3 shows the location of water samp-

In addition to the network described, a detailed survey of springs, s t reams, ' reservoi rs and water supplies within 10 miles of the tes t well will be conducted, and selected stations will be established for sampling through the post- event operation, as required.

Snow samples from various locations in the RULISON a r e a will be collected to document background and post-event radioactivity 'concentrations. Portable precipitation samplers will be deployed to collect samples of precipitation that may occur during drillback and flaring operations.

Animal and Wil'dlife Sampling

Specimens will be taken from deer in the RULISON a r e a pr ior t o drillback, and at intervals during and after operational activities at the RULISON si te . analyzed for mixed fission products and tri t ium. If necessary, as determined from other surveillance resul ts , special samples of domestic animals an-d wildlife will be obtained.

Selected organs will be

Vegetation and Soil Sampling

Vegetation samples will be collected from stations around the RULISON site. Collections will be made pr ior to drillback, during' flaring, and after testing is complete. Seasonal var i - ation will be considered in selecting vegetation species, and special samples of appropriate fruits and vegetables will be c 011 ec t ed.

Soil samples will be collected from representative vegetation sampling s i tes .

_.

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Gas Sampling

Grab samples ofdnatural gas will be collected from the RULISON reentry dril l hole as soon as gas begins to flow. These samples will be collected in evacuated high-pressure s teel bottles at the wellhead, using line pressure to f i l l the bottles. constituents. After initial collection, grab samples will be collected at the wellhead whenever the line monitor indicates a significant change in radioactivity concentrations in the natural gas. and moisture separated from the gas.

Filled bottles will be analyzed for radioactive

Samples will a lso be taken of the condensate

The initial samples will se rve to determine the re lease ra te of the radioactive nuclides, and will aid in establishing the calibration accuracy of the line monitor. be analyzed for tr i t ium, 14C, 85Kr, Xe and other radioactive mater ia ls .

The samples will

If it is determined that aer ia l monitoring is necessary, a SWRHL aircraf t will be used to provide aerial sampling of effluent plumes. mation on plume r i s e , direction of t ransport , ra te of movement, and the extent of diffusion. The a i rc raf t may a l so be used to supplement ground surveillance by collecting low altitude samples in a reas inaccessible to mobile monitors. Samples will be collected to determine particulate and radioactive gas activities. 85Kr, 14C, and tri t ium analysis, The aircraf t will a lso provide a means for rapid transportation of samples to SWRHL for analysis.

The aircraf t may be used to provide infor-

Cryogenic samples will be taken for

METEOROLOGICAL SUPPORT PLAN

Responsibilities -

The A i r Resources Laboratory, Las Vegas, Nevada, (ARL-LV) is responsible to the Atomic Energy Commission for providing f o r e - . cas t s of meteorological conditions and predictions of radiation movement and dispersion, under the general direction of the Director of Nuclear Operations.

The principal meteorological problem anticipated during the drilling reentry of the RULISON chimney and the flaring of the natural gas consists of knowing at all t imes the atmospheric t ra jectory and dilution and the forecasted deposition patterns of any radioactive gas

a

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. - - . . , . . .. 1 . ., _I _” . ... .. . . . , . , . , . . , . . . . . . ... ..

re leased into the air . Director of Nuclear Operations (DONO) to position radiation moni- t o r s , take environmental samples, and to exercise controls.

This information will be used by the

Objectives . The objectives are:

.

Design and emplace a meterological data acquisition network in tKe 1&a1 a r e a .

Provide weather data and weather forecasting service in supporrt’of the Director of Nuclear Operations safety programs.

Provide predictions of the dispersion of radioactive effluent that might result f rom Project RULISON actiyities.

To accomplish these objectives, ARL-LV will provide 24-hour weather forecasting and observing service as required by the Director of Nuclear Operations (DONO). forward a r e a forecasting and observing complex near Surface Ground Zero ( S G Z ) .

ARL-LV will establish a

Instrumentation

The ARL-LV inflation van will be used as the pr imary observation point. casting office at the si te.

Additional t ra i le r space will be’used for a weather fore- Both of these facilities will be near SGZ.

Maximum use will be made of the data from the National Weather Network available to the meteorologist in Grand Junction. provide mesoscale forecasts for the RULISON a r e a , the instrumentation required is as follows-

Sur fac e Wind

The SYSTRAC radio-telemetered system will be used to obtain surface wind speed and direction.at: Tower No. 1, 3 . 7 miles northwest of GZ; Tower No. 2, 1.. 6 miles northwest of GZ; and Tower No. 3 , near GZ. (See Figure 8-4). Data f rom these stations will be telemetered into a mas te r station in the inflation van. at the-wellhead’as backup for Tower No. 3 . The readout will be on an analog recorder located in the inflation van.

To

A p electromechanical surface wind system will be installed

,. . : ..i ., . . - . . . . , . . .

'

RUL l SON WIN D TOWER S FIGURE 8 - 4

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Wind data f rom these towers will be continuously recorded and will provide the meteorologist a means of determining the local wind regime in the vicinity of the RULISON si te . a r e a l so required t o recommend placement of manned sampling stations.

These data

Temperature and Humidity

Surface temperatures and relative humidities will be available f rom a hygrothermograph exposed in a standard instrument shelter located near the inflation van.

Upper Level Winds

b

The upper level winds will be obtained near the C P by pilot balloon observations (pibals) using a single theodolite. mobile pilot balloon units will be available f rom NTS if the need a r i s e s .

Additional

The data will give an indication of the initial la teral dispersion of the effluent and, i f required, will give indication where aerial sampling should begin.

V e r t ical Soundings

ARL-LV Ground Meteorological Device (GMD) will be used to obtain vertical temperature , humidity and wind soundings. GMD will be located approximately 4 miles northwest of S G Z near Battlement Creek.

The

Vertical temperature soundings will be required to determine the on-site current atmospheric stability profile, estimates of plume r i s e height and can be used to obtain upper level wind observations during inclement weather (low ceilings). soundings will a l so be available f rom the Grand Junction Weather Bureau Station.

Upper-air

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APPENDIX A

MAXIMUM HYPOTHETICAL ACCIDENT

. 1. Postulation of the Maximum Hypothetical Accident In order t o a s s e s s the potential hazard ( i f any) that may result f rom an accidental loss of control over the gas flow during reentry or production testing, a maximum hypothetical accident was postulated though it is extremely unlikely that such a hypothetical accident could occur, The chance of a sudden and complete discharge of essentially all gaseous radionuclides f rom the chimney is regarded by the petroleum engineers who have examined the reentry plan as not only improbable but practically impossible. Nevertheless, t o complete the analysis of radiological hazards , a study has been made to determine the effect of such an event.

2. Airborne Radioactivity Estimates

F o r the maximum hypothetical accident, it is assumed that an uncontrolled blowout occurs through an open dr i l l hole, releasing 94% of the gaseous radioactive nuclides present at 180 days from detonation, over a 24-hour period. ( l ) (It should be noted that, based on the GASBUGGY experience, one would expect that only 10% of the gaseous radionuclides would be released. The initial sample analysis will indicate whether the available fraction for re lease is nearer 9470 or 10%. ) The total inventory of gaseous radionuclides present at 180 days after detonation is as follows:(')

Nuclide

85Kr

1 3 3 ~ e

Curies

9 .6 x 10 2

8 .6 x

3 9 A

4c

, L3H

1 2 x 10

l x 10-1

4 l x 10

The released methane gas will be burned and the plume r i s e , due to its momentum and buoyancy, will be significant. Calculations indicate that the effective release height, as used in the diffusion

A- 1

APPENDIX A

0 calculations, will be 300 meters or more. (2) Estimates have been prepared for a 100 meter , a 300 meter , and a 600 meter daytime effective release height to demonstrate the effect ,of this parameter . A 600 meter height is not used for the nighttime case since this height is normally above the nocturnal surface inversion. would be transported by the winds above the inversion and would not diffuse to ground level until the nocturnal surface inv.ersion had been destroyed by solar heating.

Climatological wind data from the RULISON site indicate that air drains down-canyon during the nighttime and predominantly blows in a different direction during the daytime. Therefore, trajectories of airborne radioactivity re leased during the daytime and nighttime a r e expected to be different. Fo r this reason the total re lease has been divided into a 12-hour daytime release and a 12-hour nighttime re lease with half of the total inventory being released during each period. stant and the plume would have little meander, daytime period, considerable meandering of the plume is likely to occur. Therefore, estimates of total integrated exposure (TIC) for the daytime period a r e considered conservative, since it has been assumed the plume travels along a constant t ra jectory during the entire period.

For the diffusion calculations, daytime atmospheric conditions were assumed to correspond to the P a ~ q u i l l ( ~ ) stability category C (slightly unstable) with a mean wind speed of 5 mps. Nighttime conditions were assumed to correspond to the Pasquill stability category E (stable) with a mean wind speed of 3 mps.

The plume *

The t ra jectory of air motion a t night would be rather con- During the 12-hour

3 . Environmental Pathways of Radionuclides to Man

Radionuclides released to the surrounding ecosystem in the event of a hypothetical accident as described above may be t ransfer red to humans by various environmental pathways. quite direct , e. g . , external exposure and inhalation exposure to airborne radioactivity o r ingestion of drinking water which has absorbed radionuclides. l e s s direct and, in fact, may involve multiple steps. Knowledge of the general character of the environment and land use patterns in the RULISON site a r e a affords a basis for selecting those pathways that could be most significant in t ransferr ing radionuclides to man; three particular routes appear to mer i t discussion. Consider that during the hypothetical accident a quantity of the radionuclides

Some of these may be

Other environmental pathways a r e somewhat

A - 2

APPENDIX A

enumerated above is released to the atmosphere and dispersed according to the prevailing meteorological regime. A fraction of the airborne radionuclides will be intercepted by, and retained on, vegetation- -cultivated and natural. vegetables, fruit) may in turn be consumed by humans. plant mater ia l (hay, pasture grass or native forage) may be eaten by herbivores such as cattle, deer or elk, which in turn a r e consumed by humans. Or , finally, humans may consume milk produced by milk cows feeding on vegetation that has intercepted airborne radionuclides. These three modes a r e believed to be the most significant ones for transporting airborne radionuclides through food chains to man in the particular environmental setting of Project RULISON.

This vegetable mat te r (leafy Other

More elaborate environmental t ransfer modes can be visualized. However, taking into account the local ecology and reasonable assumptions concerning the kinds of radionuclides that may be released, there is no reason to believe that such more complex pathways would lead to higher internal doses to man than the three routes specified above.

Near the RULISON site, the local human population utilizes locally grown garden vegetables and fruits, consumes meat f rom local range livestock and native herbivores (principally deer , plus a few elk), and uses milk from local cows. Therefore, considera- tion has been given to the potential internal radiation dose to man that might result f rom consumption of plant products that have intercepted airborne radionuclides accidentally re leased to the environment. Similarly, doses to man that might resul t from consumption of milk o r meat products f rom primary herbivores feeding on such plant material are considered.

Estimation of Dose to Man From Radionuclides in A i r

The applicable radiation protection guides for RULISON for an average annual dose or dose commitment to a suitable sample of the exposed population is 0. 17 rem. The estimated dose resulting f rom the maximum hypothetical accident case, based on concentration of each nuclide, has been calculated a-s a function of downwind distance and the total dose is obtained by a summation of these individual contributions. of the 0. 17 rem. It is apparent f rom this figure that, even using the 100 meter effective re lease height, the total dose which could resul t f rom the calculated air concentration is a small fraction of the 0. 17 r e m guide, for both the daytime and nighttime conditions.

4.

It is expressed in Figure A-1 as a fraction

A-3

APPENDIX A

5. Estimation of Dose V i a Drinking Water

Two pos'sibilities have been considered for estimating concentrations of radioactivity in drinking water resulting from reentry drilling:

a.

b.

If the leakage into the aquifer is in the form of radioactive gas , the radioactivity is expected to be confined in the immediate vicinity of the explosion site. If the leakage is in the form of radioactive water and confined to Mesa Verde formation rock, dril l s tem pressure tes t s show that there is no significant upward or downward potential for flow, but ra ther flow in these rocks will be lateral . Ground water in the Mesa Verde formation will flow in the fracture and pr i - m a r y pore spaces resulting in extremely low average water velocity. Therefore, radionuclide transport is expected to be very limited and the concentration of any nuclide in water is expected to be below 1 RCG beyond a thousand me te r s f rom the explosion site.

If leakage in the form of radioactive water is into shallow water-bearing rock, water flow ra te will be higher than in Mesa Verde formation. However, concentrations of radionuclides will be less than 1 RCG by the t ime these nuclides have traveled a few thousand me te r s and before they reach locations where the water might be used for domestic purposes.

F o r case two, radioactivity in surface water resulting f rom rainout of re leased radioactive gases could, i f the gas were vented during rainfall and that rainwater subsequently used to fill c is terns , result in concentrations above those specified by A E C MC 0524(4) for continuous drinking water consumption. Although such an occurrence appears exceed- ingly remote, the planned water sampling program would lead to appropriate steps being taken to a l e r t against such use of this water.

6 . Estimating Radiation Dose V i a Foods

a. The estimation of potential internal radiation dose to man via food chains is based on a general model which, given the radioisotopes source t e r m and atmospheric dispersion predictions,

/ can be used to estimate:

(1) The interception and retention of airborne radionuclides by vegetation,

.

A. -4

of radionuclides in the organs and t issues of animals feeding on vegetation that has intercepted airborne radionuclides,

(3) The internal radiation doses to man that would resul t f rom his consumption of given quantities of t issue from such animals o r vegetation o r milk f rom cows feeding on the vegetation.

b. Not all of the biological and ecological constants required for application of the general model a r e available; as a consequence, certain of these have been inferred on the basis of the best data available. estimates a r e as follows:

The assumptions used in making the present

(1) Est imates of internal radiation doses to man a r e based on tri t ium only. the quantity and kind of other radioisotopes expected to be released would not contribute significantly to internal doses. )

(Pre l iminary calculations show that

(2) Tritium re lease to the environment will be in the form of tritiated water vapor, i. e . , the gas re leased will be burned.

( 3 ) Two cases of foliar deposition of tr i t iated water vapor a r e considered:

(a) "dry" deposition (i. e . , when no precipitation i s occurring)

(b) deposition during a 12-hour period of rain a t the r a t e of 0. 5 mm per hour. (5)

(4) . F o r estimating deposition and retention of tr i t ium on vegetation, the following assumptions a r e used:

(a) a deposition velocity of 1 c m / s e c

(b) the fraction, of radioactivity intercepted by vegetation is 0 .1 '

A - 5

APPENDIX A

(c) the effective half-time on vegetation is 28 days for the dry deposition case and the effective half-time on vegeta.tion is estimated to be about 2 days for the rainfall case.

(5) Transpiration and uptake from the soil (where the other 90 percent of the tr i t ium is deposited) a r e considered for the rainfall case. The transpiration ra te is taken to be 0 . 0 5 cm per day.

( 6 ) For estimating the f i r s t year internal radiation dose to humans from consumption of vegetables and fruits that have intercepted airborne tri t ium, the following assumptions a r e used:

(a) 50 percent of the t r i t ium is removed by washing or during preparation of the plant mater ia l for eating.

(b) 50 percent of the individual adult 's caloric intake is derived from locally grown vegetables and fruits (this approximates 770 gm per day) over the entire period of one year.

h

(7) For estimating the first year internal radiation dose to human adults from consuming flesh of herbivores which have fed on vegetation that has intercepted airborne tri t ium, the following assumptions a r e used:

(a) the deposition and retention of tr i t ium on vegetation is estimated on the basis of assumptions (1) - (4), para. 6 . b . , 'above.

(b) the animal derives i ts entire caloric intake from this vegetation; a 75 kg animal is assumed to consume 15 kg per day.

(c ) the animal 's effective bio-elimination half- time is 5 days.

(d) the animal is butchered at the t ime when the tr i t ium content in i ts t issues reaches a maximum.

A,-6

APPENDIX A 0

(e) man consumes 2 kg/week of the herbivore flesh throughout the year .

(8) For estimating the internal radiation dose to a human adult or child from consumption of milk from a cow feeding on vegetation that has intercepted airborne tri t ium, the following assumptions a r e used:

The deposition and retention of t r i t ium on vegetation is estimated on the basis of assumptions (1) - (4), para. 6. b . , above.

the cow's forage intake is about 40 kg/day for a 450 kg cow.

the cow's bio-elimination half-time is approximately 3 days.

the adult or child consumes 1000 gm/day of milk, at a tr i t ium concentration assumed to be equal t o that of the body water of the cow.

the weight of the adult is 70 kg; that of the child is 10 kg.

the bio-elimination half-time for adult and child is proportional to body weight to the 0. 25 power; the half-t ime is 12 days for the adult and 7 . 4 days for the child.

c. Using the above assumptions, estimated doses to man from food lead to values from about 4 mil l i rem for the dry deposition case to an extreme upper value of about 100 mi l l i rem pe r year for the rainout case. This upper value would only occur f rom the highly improbable simultaneous occurrence of an uncontrolled venting and rainout.

7. Summary

The foregoing discussion indicates that potential radiation doses to the neares t residents resulting from concentrations of radioactivity from air on locally produced foods, even in the postulated maximum hypothetical accident case, would be small compared to 0. 17 r e m / y r .

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APPENDIX A

Control of exposure from drinking water supplies, which may be replenished during a simultaneous occurrence of the maximum hypothetical accident and rainfall, requires monitoring, sampling, and preventive action to a s su re that c is terns a r e not filled during such a t ime.

Remedial action capability will as su re that the post-shot program can be car r ied out within the constraints of AEC MC 0524.

REFERENCES

Aamodt, R. L., Prel iminary Outline of Document, October 25, 1969.

RULISON Re-entry

Briggs, G. A . , Prediction of Plume Rise Heights, to be published in proceedings of 8th annual Environmental and Water Resources Eng. Conf. , Vanderbilt Univ. School of Engineering, Nashville, Tennes see, June 1969.

Pasquill, F. , The Estimation of the Dispersion of Windborne Material , Meteorological Magazine, Vol 90, 196 1 .

A EC Manual, Chapter 0524, Standards for Radiation Protection.

Chamberlain, A . C. , and A . Eggleton, Washout of Trit iated Water Vapor by Rain, Int. J. Air Water Pol l . , 1964, Vol 8, 135- 149.

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