Text

Monthly Operating Repts for Aug 1988 for Sequoyah Nuclear Plant Units 1 & 2
	ML20154H626
Person / Time
Site:	Sequoyah
Issue date:	08/31/1988
From:	Shawn Smith; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8809220074
	Download: ML20154H626 (176)
	v • d • e

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TENNESSEE VALLFY AUTHORITY s

NUCLEAR POWER CROUP 9

(FORMERLY OFFICE OF NUCLEAR POWER) i SEQUOYAH NUCLEAR PLAN?

MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY CO.'NISSION AUGUST 1938 UNIT 1 00CKET NUMBER 50-327 LICENSE NUMBER DPR-77 9

UNIT 2 DOCKET hTMBER 50-328 j

LICENSE NUMBER DPR-79 l

.A Submitted by dM#N l'

S. J. 6mith. Plant Manager i

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S809220074 SGOS31 I\\

i PDR ADOCK 05000327 R

PDC

I TABLE OF CONTENTS j

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Operational Sumary I

Performance Sumary 1

Significant Operational Events 1-2 Fuel Performance and Spent Fuel Storage Capabilities 3

Miscellaneous 3

PORVs and Safety Valves Sumary 3

Special Reports 1

Licensee Events 4-10 Systems of Sequoyah Nuclear Plant 11 Radwaste Sumary 12 Offsite Dose Calculation Manual Changes 12

!!. Operating Statistics ji A.

NRC Reports i

Unit One Statistics 13-15 2

Unit Two Statistics 16-18 B.

TVA Reports t

j Nuclear Plant Operating Statistics 1) j Unit Outage and Availability 20-21 l

1 Reactor Histogram 22-24

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!!!. Maintenance Sumary l

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Electrical Maintenance 25-26

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Instrurrent Maintenance 27 j

Mechanical Maintenance 28-33 l

l Modifications 31 37 L

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Offsite Dose Calculation Manual Changes 38 i

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i OPERATIONAL SD'?.ARY l

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PERFORMA' ICE SLStARY August 1988 i

i The following summary describes, the significant operational activities for the month of August.

In support of this sunnary, a chronological log of f

significant events is included in this report.

UNIT 1

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Unit I renained in an administrative shutdown the entire nonth because of design control review, configuration control updating, and resolution of

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significant employee concerns. Outage-related maintenance and modifications j

continue for ro tart.

Unit I has been off line 1,105 days.

Extensive testing and sarious system alignments as well as other restart activities are being

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performed.

J Another significant milestone has been accomplished for the Sequoyah Restart l

Program. On August 4, 1988, the NRC agreed to the proposed schedule for l

unit I restart. This causes great anticipatien and enthusiasm to prepare the i

unit for operational s tatus.

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Other major objectives that are being eagerly anticipated are criticality, f

power operation (generator synchronization), and full power operation I

(100 percent reactor power),

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UNIT 2 i

j Unit 2 continues to operate extraordinarily since restart.

It was entir.e the entire month with a capacity factor 92.53 percent.

Since restart, unit 2 has j

generated ever 2 million Whs (2,012.420 Wh) of electrical power and has teen i

in continueus operation for seventy (70) days.

S_I_C_N I F_I C_A'i_T_O. P_E R A. _T I_C_N A.L_EV_E N..T.5_

4 Unit 1 Date T i c-e Event l

Os/01/S3 0001E Made 5 RCS at 110 degrees F, atmospr.eric pressure.

Amtivities continue for restart.

0s/04/53 ltC0F NRC and TVA meet to discuss restart issues.

04/06/s3 2250E Venting and sweeping of the RCS begins.

03/09/53 180CE RCS venting and sweeping completed.

08/15/S3 1652E Loss of one offsite independent circuit because of thunderstorm. All four D/Gs started, IB-B tied to the system.

Entered various LCOs.

1732E All D/Gs returned to standby position.

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l SIGNIFICANT_0PERATIONAL EVENTS i

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paB Time Event l

08/21/88 0558E Bubble established in the pre;surir.er.

j 08/31/88 2400E Maintenance activities continue toward restart.

L' nit 2 Date Time Event 08/01/88 0001E Reactor at 75 percent. 865 FNe. Maintenance continues on "2A" condensate booster purrp.

08/02/8S OS35E Began power incre.ase.

1150E Holding at 90 percent. 1020 SNe for power range adjustment.

1335E Resume power increase.

1509E Reactor at 9S percent. 1117 FNe, High steam flow alarm initiates at power greater than 98 percent reactor G

power.

08/15/53 1652E Loss of one offsite independent circuit beesuse of thunde rs t o rra. All four D/Cs started. 15-B tied to the system.

Entered various 1.COs.

1732E All D/C retvrneit to standby position.

C8/25/85 1940E Began reducing load to 95 percent for the moderator coefficlent test.

2140E Reactor stabilised at 95 percent.1050 ENe.

OS/26/88 0555E Test coroplete.

0620E Began power ascension.

110SE Reactor at 9S percent. 1103 FNe, 08/31/83 2400E Reactor at 93 percent. MOS FNe, l

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TUEL PERFORMANCE 4

l Unit 1 The core average fuel exposure accumulated during August was 0 SND/MTU with i

the total accumulated core average fuel exposure of 0 FND/MTU.

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The core average fuel exposure accumulated during August was 1153.33 FND/MTU j

j with the total accumulated core average fuel exposure of 10963.67 SND/MTU.

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I SPENT FUEL P!T STORACE CAPABILIT!ES I

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The total storage espability in the SFP is 1.396.

However, there are five cell locations which are incapable of storing spent fuel (SFP).

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a locations (A10. All. A24. and A25) are unavailable due to a suction strainer i

I conflict, and one location (A16) is unavailable due to an instrumentation L

j conflict.

Presently, there is a total of 348 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1.033.

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f MISCELLANEOUS l

1 frecial Nuclear Material (SNM) Sersiannual _ System Review I

i The semiannual system review of the plant's overall SNM &nagement Program was

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conducted August 3-5, 19SS. by Nuclear Fuel. NE. Chattanooga. and representatives from the Controller Office with Coopers and Lybrands also j

present.

This specific review eensisted of all the SNM records and a complete j

videotape review of the spent fuel pit. No major discrepancies were observed in any areast however, a minor documentation discrepancy resulted in a CAQR I

(SQTSS0001P) written by Nuclear Fuel and NE regarding the noninventory of a l

f temporary storage area.

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NOTE: A physical inventory on four other storage areas containing SNM was performed on July 28, 1988. No discrepancies were observed.

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PORVs A'm SAFETY VALVES

SUMMARY

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No PORVs or safety valves were challenged in August.

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I SPFCIAL REPORTS l

The following special report revision was submitted to the NRC for the month of August.

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38-03 This revision provides the completion schedule for corrective action

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Rev. 1 concerning a fire barrier beltsg nonfunctional for greater than seven days.

LICENSEE _ EVENT REPORT (S) l The following licensee event reports (LERs) were transmitted to the Nuclear Regulatory Comrnission in August 1988.

Description of Event LER 1-88027 On July 14, 1988, during a review of RM S!s. it was discovered that an incorrect source strength evaluation date existed in SI-83 l

"Channel Calibration for Radiation Monitoring System." At the time of the discovery, unit I was in mode 5 and unit 2 in mode 1.

Upon review of SI-93 it was determined that the common fuel storage pool RMs (0-RM-90-102 and 0-RM-90-103) were affected by the incorrect j

evaluation date. This date resulted in 0-RM-90-103 being declared inoperable on July 14. 1983 until it could be verified that it was within acceptable TS setpoint limits for a high radiation trip.

l During the investigation, it was discovered that 0-RM-90-103 was out of etlibration for a 3-month period (August 6.1987, to Oct;ber 23

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1997). The immediate cause for the out of TS tolerance condition for 0-RM-90-103 (August to October 1987) is attributed to an incorrect source strength evaluation dato in SI-83.

The root cause of this l

event is considered to be an inadequate checklist in A>pendix F of I

SI-1. "Surveillance Program." Appendix F of SI-1 provides a checklist to ensure that technical and administrative concerns are i

addressed during the S! revision review process. Upon review of the L

Appendix F checklist, it was discovered that a verification did not exist to ensure that RMs soutee strength evaluation dates were correct.

For Ir rediate corrective action, on July 14. 1988. 0-RM-90-103 was verified within the present allowable TS setpoint limits by a performance of SI-83 with the correct source strength evaluation I

date. 0-RM-90-102 was also verified to be within the allowable L

setpoint limits.

For long-term corrective action, a revision has i

been instituted and is in use, to include the correct source i

strength evaluation date. A revision will be made to the S!-1

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Appendix F checklist by November 1. 1988, to provide a verification to ensure that RMs source strength evaluation dates are correct.

U 1-SS029 on July 23. 1988, with unit 1 in mode 5 and unit 2 in mode 1 at 93 percent power, the hourly fire watch patrol through the 734 foot

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elevation of the auxiliary building (refueling %1oor) was suspended from 0700E to 1500E because of an unexpected increase in the airborne l

radioactivity in that area.

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Description of Event IM 1-88028 The fire watch was required by LCO 3.7.12 as a compensatory measure i

(cont.) for three breached fire barriers.

Fire barrier breaching permits were issued part of a workpl.n to reroute a cable to poelude a i

potential "Appendix R" e M e interaction and to ensure rh6 i

availability of RCS '.esdown following a postulated fire. The r

k immediate cause of this event was the high level of airborne i

radioactivity in the auxiliary building. This condition represented l

j an overriding personnel safety concern and access to the area was I

L subsequently restrined.

The roat cause of this event was valve 1eaks that allowed nitrogen to leak into the RCS during S! system J

9 ter,t in g. The inleakage caused a rise in the indicated RCS level and prompted unit 1 operators to open the reactor vessel head vents.

l Since the head vents discharge to the pressure relief tank (PRT) and

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l the PRT safety valves had been removed for maintenance 3 there was an I

increase in he activity level of the containment almosphere. With

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l the unit 1 blast doors open, the radioactivity from the containment j

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atmosphere migrated into the auxiliary building.

At 1500E on l

July 23. following manual operation of the ABGTS. the level of i

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airborne radioactivity decreased to an acceptable level and fire protection personnel resumed the required fire watch patrols.

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Sebsequently, tLe leaking SI system valves were repaired using i

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standard work control practices.

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j 1-88029 On August A. 19S8 at 2143E with unit 1 in mode 5 and unit 2 at

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98 percent power load shedding occurred on 6.9 kV shutdown board 1B-3 during the performance of WP 7152-01.

This WP provides l

instructions for modifying the load shedding and load sequencing t

l logic to allevlete concerns regarding emergency D/G loading l

1 capabilities. Before this event. the control power fuses for the WX i

(undervoltage) relays were pulled to f aci'11 tate the modification.

l Also, handswitch 43T1. was placed in the "TEST" position to preclude inadvertent emergency D/G starts. Pulling the control fuses resulted l

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in deenergizing the WX relays and completed one half of the load l

j shedding logic. During this event, a centact of a BOX (blackout) 1 relay was to be connected in parallel with contacts of other P0X I

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relays that are part of the control circuit for the annunciation

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timing relay. The annunciation relay receives control power from the same source as the WY relays. Therefore, when a wire was 11fted to connect a contact of the BOX relay in the circuit. poser to all UW

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relays downstream from the point was interrupted.

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the WX logic relays had already been pulled and now the WY relays l

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sere deenergired load shedding then occurred, causing a loss of RHR

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cooling.

The initial investigation of the event mistakenly concluded 5

that the performance of the WP did not cause the event and a second j

load shedding event occurred.

The root cause of the first load 1

shedding event was that the WP incorrectly stated that the steps of j

the WP could be worked in any order, The cause of the second load n

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shedding event was the incorrplete assessment of the cause of the l

first event. As imnediate corrective action. Operations personnel

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3 responded to reestablish RMR flow.

To aid in the prevention of recurrence. these events will be reviewed with the cognizant l

i modifications engineer and the engineers in the Plent Reporting l

j Section. Plant Assessment Section, and Work Oversight Section by September 30. 1983.

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pescription of Event l

LER l

i 1-08030 At approximately OS11E on August 6. 1988, with unit 1 in mode 5. 4

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O train "A" CVI signal was generated by the unit 1 SSPS.

Since the CV!

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closed the containment isolation valves to the containment upper and lower compartment RMs inhibiting the air flow to each, both were j

inoperable and 1.C0 3.3.3.1 was entered.

Following verifict. tion that the CVI was not caused by an actual high radiation condition, plant

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operators initiated recovery procedures. At approximately 08228. one

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RM was restored to operable status and !.C0 3.3.3.1 was exited. At j

approximately 092SE. the CVI secovery had been completed. Following

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an investigation of the ongoing work activities at the time the CV!

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was generated, it was concluded that the CVI was the result of an IM l

technician insdvertently contacting the wrong RM terminal durjng i

functional testing of unit 2 RMs.

The root cause of this event has i

been attributed to the use of one terminal block for routing cables associated with RMs from both unit 1 and unit 2 without clearly l

1 identifying each cable and/or terminal.

To prevenc recurrence of j

this event. SQN will issue a design change to relabel the electrical i

j cables in control room panel 0-M-12 that are associated with Mts j

eapable of generating CVIs.

In the interim. SQN will review this event with IM personnel who may be required to perform maintenance on 4

l RMs before the relabeling has been corepleted.

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i 1-55032 On August 2. 198S, with unit 2 in mode 1 and uriit 1 in mode 5. the f

EGTS (common to both units) was declared inoperable because of an

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incertplete system design.

During a design review of the system, a single failure occurrence causing the discharge modulating damper in i

4 the automatic train to open prior to the initiation of the system or prior to arming of the swapover logic, could preclude the syst m from j

performing its design function.

With this condition present, tho j

initiation of EGTS operation on an accident signal could result in an t

unmodulated open path of air discharged to the environment. Design l

l calculations have shown that with this condition present, the Site toundary whole body garms dose could exceed the 10 CpR 100.11 timits 3

of 25 Rem.

The cause of this condition is attributed to a design j

oversight.

This specifte scenario was not anticipated in the initial i

design of the system.

!arnediate corrective actions were ta declare l

4 both trains inoperable until compensatory measures were incorporated

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l into procedures to take eunual control of both trains of ECTS.

They were returned to operable status at approximately 2215E on j

August 2. 1988.

l.ong-term corrective actions are to modify the present pressure switch logic to preclude any single failure i

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occurrence on the discharge damper arrangement. To prevent recurrence, present design procedures that were not it. place during l

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the initial design of EGT3 require encorpassing plural reviews and l

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established technical checkpoints to be evaluated on new design l

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1-85007 This revision changes the date in which a supplemental report will be Rev. 1 submitted. Because the corrective actions necessary to resolve this issue have not been finalised. IVA must delay the submittal of a

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supplemental report untti November 1. 1988.

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Desegr.iption of_Evgnt

!1R 2-68031

'uly 5. 1988, unit 2 in mode 1. Operations personnel noticed ic performance of the MCR hydraulic pressure indicator for N-87-21 and initiated a WR to investigate and repair the 4cator. On July 8, 1988, at 1430E, the repairs =vre completed.

. that time, it was noted that the hydraulic pressure in the accumulator for 2-FCV-37-21 was low (2647 psig).

It was recharged to 3034 psig. At approximately 1630E on July 8, 1938, a meeting was 1

held to discuss the ramification of the low hydraulic pressure.

Systems Engineering and hintenance were directed to develop an action plen to perform a nitrogen precharge check. Nnagement j

stressed that the plan was to address contingencies in the event i

equipment was required to be replaced. At 1231E, on July 10, 1988, 4

LCO 3.5.1.2 was entered to perform the nitrogen precharge check.

The nitrogen pressure was found to be 1164.5 psig. A leaking Schrader 4

j valve on the nitrogen side of the accumulator was repaired and the 1

nitrogen was recharged. At 1555E the LCO was exited. After discovering the low nitrogen pressure in the accumulator, Westinghouse was requested to evaluate the "as-found" affects of the nitrogen pressure on the response titte of 2-FCV-$7-21 and the applicable accident analyses. Westinghouse concluded tht.t an additional 170 cubic feet of water would be injected into the rea: tor I

vessel.

The Ud! accumulator level switch is currently set to actuate l

at 1000 cubic feet of injected water.

The SQN safety analysis for the JRI delivered water volume assured 1180.5 ctbic feet would J

injest. Thus, the 1170 cut ie feet assured so inject as a result of i

the low nitrog*n pressure is within the latest accident analysis.

The root cause of this event was that SI-744, "Monitoring of CHI l

!soiation Vsive Accumulator Pressure," did not contain sufficient i

informat'on to perform an adequate assessraent of valve operability.

i; In order to prevent this event from recurring, SI-744 will be revised i

to clarify the actions to be taken af ter aa accumulator cha ge.

i 2-88033 On July 29, 198S, it was suspected that an inadequate SI used for the i

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calibration of the CHI system accumulator tar.k level switches may have resulted in the SQN unit 2 being in noncompliance with the TS.

At this time, unit 2 was in mode 1 unit 1 in mode !.

During the 1

perforeunce of a demonstrated accuracy calculation by DNE, it was l

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discovered that incorrect level switch seth> int values existed in

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S!-196, "Periodic Calibration of Upper Head Injection System Instrumentation." This SI is used to calibrate the UHI system accumalator level switches to ensure compliance with TS and accident analysis for delivered water volume to the P.CS.

Upon verification

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that a noncompliance condition existed, unit 2 eTtered TS

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ICO J.5.1.2, "Emergency Core Cooling Systems (ECCS) Coper Head Injection Accumulators," at 0000E on July 30, 1999.

Since unit I was

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in mode 5, the subject LCO was not applicable.

For imediate 4

corrective action on July 30, 1989, S!-196 was revised to incorporate the correc level switch setpoints and subsequently perforced to recalibrate all unit 2 level switches. Upon coupletion, the unit 2 UHI system was declared operable and the LCO was exited.

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G 2-88033 tong-term corrective action, correct level switch differential (cont.) pressure values for unit I have been incorporated into SI-196. Also, the switches have been replaced by DCN 060. TVA will reverify that the vendor worksng line is marked at the correct elevation on both I

units, clearly identifiable, and preserved by placing signs on the j

tanks beside the turked working line.

i 2-83097 This revision updates information on the planned corrective actions Rev. 3 f or the containtnent sump level transmitters.

-88026 This revision provides additional information regarding the Rev. I corrective action SQN is taking to prevent recurrence of this event.

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ABBREVIATIONS Page 1 of 2 1.

ABCTS

- Auxiliary Building Cas Treatment S9 stem 2.

ABSCE

- Auxiliary Euildir.g Secondary Containment Enclosure 3.

ABI

- Auxiliary Building Isolation 4

AFW

- Aux!!!ary Teedwater 5.

A0!

- Abnornal Operating Instruction 6.

ASOS

- Assistant Shift Operation Sepervisor 7

AUO

- Assistant l' nit Operator 9.

BAT

- Borie Aeld Storage Tank 9.

B!i

- Soron Injection Tank

10. CAQR

- Condition Adverse To Quality Report

11. CCF

- Centrifugal Charging Pump

12. CCW

- Component Cooling Water

13. CRI

- Costrol Room Isolation

14. CREVS

- Control Room Emergency Ventilation System

15. CSS (CS) - Containment spray System 1

16.

CVI

- Containment Ventilation Isolation

17. D/C(s)

- Diesel Generator (s)

18. DCN

- Design thange Notice 19.

DCR

- Design Change Request 20.

ECCS

'ergency Core Cooling System 21.

ECN ineering Change Notice 22.

ECTS

- -rgoney Cas Treatment System 23.

EMI

- Electromagnetic Interf erence 24 EQ

- Environmentally Qualified / Environmental Qualification 9

25. ERCW

- Essential Raw Cooling Water 26.

ESf(A)

- Engineered Safety Teature (Actuation) 27.

TCV

- Flow Control Valve

28. TSAR

- Tinal Safety Analysis Report 29.

FV!

- Teedwater Isolation

30. C0!

- General Operating Instruction

31. CPM

- C411ons Per Minute

32. H0

- Hold Order

33. IM

- Instrument Mechanie 34 IMI

- Instrument Maintenance Instruction

35. LCV

- Level control Valve 36.

LCO

- Limiting Conditien for Operation 37 LOCA

- Loss of Coolant Accident

38. MAST

- Maximra Allowable Stroke Time

39. MFI

- Main Teedwater Isolation 40.

MFP

- Main Teedwater Purp i

41.

MOV

- Motor Operated Valve 42.

MS!

- Main Steam Isolation

43. MSIV

- Main Steam Isolation Valve 44 MCR

- thin Control Room

45. NE

- Nuclear Engineering (formerly Division of Nuclear j

Engineering)

46. NSS

- Puclear Security Service 47.

NSSS

- Nuclear Steam Supply System 48.

PORC

- Plant Operation Review Committee 49.

PRO

- Potential Reportable Occurrence 9

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ABBREVIATIONS Page 2 of 2 49.

RCS

- Reactor Coolant System 50.

RHR

- Residual Heat Removal 51.

RM

- Radiation Monitor (RAD Monitor / RAD MON) i 52.

RWST

- Refueling Water Storage Tank 53.

SCR

- Significant Condition Report 54 SFP

- Spent Fuel Pit 55.

S/G(s)

- Steam Generator (s) 56.

SI

- Surveillance Instruction /or Safety Injection 57.

SMI

- Special Maintenance Instruction 58.

S0I

- System Operating Instruction 59.

SQN

- Sequoyah Nuclear Plant 60.

SR

- Surveillance Requirement 61.

SSPS

- Solid State Protection System 62.

TACF

- Temporary Alteration Control Form 63.

TI

- Technical Instruction 64.

TS(s)

- Technical Specification (s) 65.

UHI

9per Head Injection 66.

UO/(S)RO - Unit Operator /(Senior) Reactor Operator 67.

VLV

- Valve 68.

WP

- Workplan 69.

WR

- Work Regenst O

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SYSTEMS OF SEQUOYAH NUCLEAR P1 ANT

/S SYSTEM kv)

CODE SYSTEM TITLE 1

Main Stearc System (Turbine) (MSR) 2 Condensate System (FW Heaters) 3 Main and Auxiliary Feedwater System 5

Extraction Steam System 6

Heater Drains and Vents System 14 Condensate Demineralizer 15 Steam Generator Blowdown System 24 Raw Cooling Water System 27 Condenser Circulating Water System 35 Generator Cooling Systems 36 Feedwater/ Secondary Treatment System 37 Gland Seal Water System 42 Main / Auxiliary Feedwater Control System 47 Turbogenerator Control System 54 Injection Water System 58 Generator Bus Cooling System 61 Ice Condenser System 62 Chemical and Volume Control System 63 Safety Injection System 64 Ice Condenser Containment System 65 Emergency Cas Treatment System 67 Essential Raw Cooling Water System 68 Reactor Coolant System (Steam Cenerator) 70 Component Cooling System b

72 Residual Heat Removal System 82 Standby Diesel Generator System 87 Upper Head Injection System 90 Radiation Monitoring System O -

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

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

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RADWASTE SDNARY l

i August 1988 1.

Total volume of solid waste shipped offsite:

A.

Dry active waste:

1764 ft.3 Activity:

21.3308 curies j

B.

Spent resins, sludges, bottoms: 0 j

Activity: N/A curies i

Shipped: August 4, 1988 Barnwell, Inc.

l August 26, 1988 Barnwell. Inc.

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Radwaste onsite and awaiting shipment:

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Resin in storage.:

109 ft.8 1

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Estimate resin that will be generated:

28 ft.3 f

C.

Dry active waste awaiting shipment:

379 ft.3 0FFSITE LOSE CAI.CULATION MA.WAL CHANCES 1

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j No changes were made to the SQN offsite Dose Calculation Manual (ODCM) in l

i August 1988.

Correction: A change was made to the SQN Offsite Dose Calculation Manual (ODCM) in July 1988. This revision (Rev. 20) is found in Appendix IV.

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i OPERATING STATISTICS (NRC REPORTS) i I

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_PERATING STATUS i

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. UNIT NAME: CEGUOYAH f:UCLEAR PLANT, UNIT i

NOTES:

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TMPORT PERIGD: AUGU"lT ' 'W D i

3.

L;CENGED THCRMAL POWER (MNT 4 3411.0 4.

N41EPLATE P ATING (CROSS Mub).

1320.6 3.

i'ESIGN ELECTRICAL RATIUG (NET MWE):

1140.0 I

6.

%XIMUM DEPENDAGLE CAPACIn (GROSS MWE):

1103.0 y

7 MAXIMUM DEPEND /,3LE CAPACITY (NET MLE):

1148.0 3.

U CHANGES OCCUR IN CAPACITY PATINGS(ITEMS NUMDERG

"' THROUGH 7)SINCE LAST PJ.PCRT, GIVE REA90N3'

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.'CWEH LEVEL TO WHTCH RESTRICTED.IF ANY(NET MWE):

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+

10.

30ASONS FOR RESTRICTIC;r1 (P ANY:

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THIG MCNTH YR. - TO-DA TE CUNULATIVE

'45 IN REPC9 7 IiG >> iis ( C ~.;

744.00 33 5J'. 00 42856.OC i

'MER OF h0URS M~ AC TON :.AS CNI TIC /aL 0.00 0.00 24444.91

.Ac7CR 'iESEFVE el-UiDCWN H OUR t.

O.00 G.00 C. 00 O.LUNTGCNERATCR C71.lNE 0.00 0.00 23701.13 JT 4ESERVE SHU FDLWN HOUW-0.00 0.00 O.00 i

1; d2 THERMAL.!4E R G,

.dNERAlED (MWH) 0.00 0.00 77050971.91 L7, 103S ELLIC TR IC AL P.1:0 Gv CCl!.

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0.00

0. GO 2'W7 6386. 00 f

la.

T ELECTR IC AL ENEPOY GENEHATCD (MUH)

~S147.00

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9

't7 EERVICE FACTCM 0.00 0.00 37.83 N.

,Ir AVAILA0ILITY rJ.C CR 0.00 0.00

37. 63 l 71.

il1 CAPACITY FACTC3(USING MDC NEl) 0,00 C. 00 34.39

7. 3.

ult CAPACITY FACTO 9(i. MING t:'IM N.IT )

0.00 0.00 34.39 l l

3.

11T FORCED OUTAGE dATE 100.00 100.00 33.89

4.

'iUTDOWNS SCHEDULED CVER NF.TIMATED DATE OF STARTUP:

'9 PESYART OF VNIT-1 IG Eh!:rtLED FOR GEPTEMDER 1990.

G T E.
~ HAT TWi TWE YR.-TO-DAl'E AND
{
GUR.:t.ATIVE VALUES HAVE DEEN UPDATED.
O -
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=
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i SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL 1
.t I
DOCKET.NO. : 50-327 i
UNIT : ONE DATE SEPTEMBER 07,1988 COMPLETED BY : D.C.DUPREE TELEPHONE : (615)870-6722 l
i 4
i f
i MONTH: AUGUST 1988 j
1 t
i AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l
DAY (MWe Net)
DAY (MWe Net)
[
01
-6 17
-6 I
l 02
-6 18
-5 i
l
]
03
-9 19
-8 i
04
-5 20
-6 l
05
-6 21
-6 t
i 06
-6 22
-5 l
{
07
-8 23
-10 08
-4 24
~5 09
-d 25
-8 i
10
-8 26
-6 j
11
-6 27
-9 j
l 12
-8 28
-6 v
i 13
-7 29
-6 1
l l
14
-9 30
-8 J
f 15
-10 31
-6 i
i 16
-8 l
l i
i
\\
l I
t i
1 I
1
, _ _ _ _. _ _ _ _ _ _._.. _ _ _ _ _ __ _ _ _.~ _ _ _,. _,_
UNIT SIIUTDOWS AND POWER REDUCTIONS DOCKET NO.
50-327 UNIT NAME sequoyah one DATE scorenber 7, 1988 COMPLErED BY C.
Dupree REPORT !!0NTil AUGUST 1988 TELEP110NE (t,15) 870-6722 ll g
E E
Cause & Corrective cg yg Licensee go, g n, e+
9 g
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Report #
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$$5 R
1 880101 F
744 F
4 Design Control, Configuration Updating, and Employee Concerns.
l 3
4 2 Reason:
fiethod:
Exhibit C-Instructions 1F: Forced S: Scheduled A-Eejuipment Failure (Explain) 1-!!anual for Preparation of Data B-!!aintenance or Test.
2-;ianual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report-(LER) File-D-Regulatory Restriction 4-Cont. of Existing (1:UREC-0161)
E-Operator Training F. License Examination Outage F-Administrative 5-Reduction SExhibit I-Saroe Source' C-Occrational Errer (Explain) 9-Other Il-Other (Explain) li
==
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DOCUET >:3.
GO '.i20 vATE SEPTEMUER 07, 1900 Cui1PLl!TED 3Y D. C. CUPD:+
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.L AR PLANT. UNIT NOTES:
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. ; 43. 0 ai1 MUM DEPEND AULE C AP A "
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1100.0 7.
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O SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL i
1 DOCKET NO. : 50-328 t
UNIT : TWO I
DATE : SEPTEMBER 07,1988 j
COMPLETED BY : D.C.DUPREE t
TELEPHONE : (615)870-6722 4
t
]
MONTH: AUGUST 1988 4
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l
DAY (MWe Not)
DAY (MWe Net) i 01 824 17 1066 1
l l
02 959 18 1065 t
l 4
)
03 1073 19 1061 t
l 04 1079 20 1065 i
05 1078 21 1065 t
06 1066 22 1065 i
07 1064 23 1065 i
08 1066 24 1064 l
09 1072 25 1061 l
1 i
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10 1081 26 1055 I
11 1052 27 1064 i
l 12 1063 28 106T f
j 13 1061 29 1063 l
14 1063 30 1062 t
15 1069 31 1068 i
16 1067 l
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1 1
1 i
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d.-_.._-
_,_.._...._,__,.~._ - _. _,_,.._. _ _ _,_.-,_ _ _.
m i
UNIT SIIUTDOWS AND POWER REDUCTIONS DOCKET NO.
50-328 UNIT NA!!E Sequoyah Two DATE september 7,
1988 COMPLETED BY D. C. Dupree REPORT 110NTil AUGUST 1988 TELEPHONE (615) 870-6722 u
cg "c
oah L'icensee go, fg Cause & Corrective gg ygg Event ug g]
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No events for the month of August 1988.
8F: Forced 2 Reason:
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4 3
Exhibit C-Instructions S: Scheduled A-Equipment Failure (Explain) 1-!!anual for Preparation of Data B-!!aintenance or Test 2-flanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161) 3 E-Oper.itor Training & Li, cense Examination Outage o
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NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Pla nt t
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v 744 Monih AUGUST 19 88 Period Hours t t em rio Umt No.
UNIT ONE UNIT TWO PLANT 1
Ave, age Hoos ly Gross t 03ci. LW 0
. 1,094 624 1,094,624 a
M3. morn unn. N..e Gener at.oi. Mwn 0
1 088 1,_C 88 t
2 0
102.4338 L 2.433F 1
cor, T heinia.i E ne cy Gen. Gwn (11 2
sican, G n rne,mai t remv Gcn. Gwn p)2 0
102.8399 102.8399 j
5 G,oss Eicc ti, cal Gen., Nhyn 0
814.3400, 814,400 i
e, station use. MW h 5,147 34,638 39,785 7
Not r tr c tocal Ge n.. f.h'/h
-5,147 779 762 774,615 3
0 8
stat.on use. Percent N/A 4.25 4.89 9
Accom. Core Avo. E mo7sure. f.hVDiTonT 0
10,964 i0,964 j o_
c TEG This Month.100 0TU 0
8,390,5 Q 8.390,553 11 sGTrc Thg Mnrith 106HTU 0
8,423,825 8,423,825 1'
13 i40urs Hractn, was cr<t,cai 0.0 774.0 774.0 ta unit us. naars-M.n.
0:00 744:00 774:00 m
rwacy i acto, re, cent 0.4 92.53 46.26
)
im Tu.n ne n.a.i.> xint a cn<ot 0.0 100.0 50.0 l _I7 G e m W ri w & m m m ;;g 0.0 100.0 50.0 o
in To.,n.3 nsao & n to..ro. cent 0.0 100.0 50.0 i
P..
" n, c ' a b u t ' h E ;sent 0.0 100._0 50._0 2
to or. A
.r. i x te,c e.,t 0.0 100.0 50.0 J _.
Tom rr 93.t ms 0
0 0
k 0
0 0
p
.3w c+L3tuw 2.2 0,
s s.., s t o ' s. n*, s an N/A 10,300 11,910 a
t c.rt o it o m, ne,...r N/A 10,760 12.525 j
x Gross Heat Rate Btu /kWh(w/o oil) 10,300
,7 Net Heat Rate Stu/kWh(w/o oil) 10.830
.9 T rinina re ess s.
csq N/A 839,7 819,7 C
t r, n t e.3 T n tr, a tyad_
N/A 525.7 525.7 y
w 30 r. n v,,1 P, esso,c. m m.m s N/A 3.61 3.61 c.
E u
intu..,ter r e m o_.._ _ _ _ _ _ __ _
_ _N/A _ _ _
~r 78.8 78.8 31 a nn i cea, vater. M e h N/A 14.5 14,5
/
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C anar it v. I 6 ef) 404.db J6).05
/ 0 6._) l__.
u A c o.n c g e sou po c.i>a,s.r; en 0.0 265.7.703 285.4_70) y l'1 Gil I ned f or Gene.ition, Ganons 9dh7 2
m o.' "Nlin23 N Uby,ai Uf,365-
_.1L _DsitLGerrlicL31? h 144 i
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43 1,088 0200E 8-5-88 ' 26,120 8-10-88 95.69 3
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=
3 a 1 l 3 p .n.
O O O i REACTOR HISTOGRAM SEQUOYAH UNIT ONE i 100 90 - 80 - g Zw 70 - 1 o } [ l y 60 - h 50 - i
==o 40 - t o. 30 - i S 20 - wz 10 - O ""i"**'" l I i i i i i i i i i i i i i 1 5 9 13 17 21 25 29 AUGUST 1988
l 1 l O N i i n \\ _D l M W f f-< l s% i MO ~R \\ I O& r O O f ~ i, b b~ l f -I [. '_b l N O W..J l ~ ~ H s l ~I i (n l
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s i I UNIT TWO REACTOR HISTOGRAM ANALYSIS i I l 1. Maintenance on 2A condensate booster pump. 2. Iloiding for reactor power adjustment. 3. Reactor @ 98 percent, high steam flow alarm initiates at power greater than 98 percent. j 4 Reduced load to perform moderator coefficient test. I l i l 4 i i l l O 24-l
I l t i i I
)
l l l i l i 1 I i l i SGD!ARY OF MAINTENANCE ACTIVITIES I i (NPRDS MAINTENANCE ITEMS) l i k O l l l l i i l f j G l 1 I I l l l i w
f r k i i 1 i i l i l. l MAlhTENANCE SUDIARY (ELECTRICAL) l e O l O \\
,a.c.aL neunit. u, a..;. u w.nx t u -J CC'.P MR2. J '"1C SYS nwiL%. anvr. DESCRIPTICN. CCPRECTIVE 6CTICl. ) 0?10%f 2 r.1;P 067 0063 C3/16/os i-nK.5-05f-0068-AJfMi7tz 1P20,taTUR/LP THE QLY,RIER-TLRN GEAR 11N (Ef.R$ WERE EIATCH It WOT CLG3I.4 ',lV f(C THE USY. l.AD, POSSIltY DCE T3 FnitL KEf.h FLEASE PirAIR CR PEFLf,CE. Cot!!ING THE PIN T3 3HEff! fd'D UALVE TO ) (:D*D. EXCIANGED GUARTER-ilNN GEf.R I:0X WITH GEf.R F3X FL9 2-WW-Of7 0064. q FETERnD'.dTED WIRDiG AND DlIN!TfLLED j DPERATCR. EEPLf,(!D "C-Cin."J'" WITH A n"RE 3 EFFICIENT TYPE GT CL A"P OH VN.VE $fE!1 I u l i l i-4 i t l I 4 4 i \\ i i !h i i i 1 i l l J I i s i i J l i!9 i I I 25-l
. a ntne umu u.ett u tits iu:.w Y d-u-58 CCllP \\ .7.. O % ;f3 ACORi13. C ATE. r, ESC 9f PTI;;;. .... (0?J2ECTIkT ACTIC1. E2P269 2 CEni: 082 "C Ow med 2 CEFl: 062-000:t i:,C01;Dd],D/C (AILED TIT.C DEltiY RELAY (ID3A) 1 A3 OETECTIVE 10 START WHEA LDCAL START FUTH fiTriCH FOSSI[tY DUE TO FURMAL LEAR. TERMINAL [] WAS PUSHED. CCLAYS TD3A AKD 7D3D LUG OH UEXCCR WIRING WAS PARTIALLY ( ) AFFEARS TO FAD.ED TO CFERATE. IRCKEN, (UT DID Pili t.PPEAR TO (( THE IhUESTICATE AD PEPAIR. DN-1 STEP 6.2.4 CAUSE CF THE RELAY FAILURE. RETERMIKATED I d.2.5 $1 102 Eiti. WILI #31. FELUGGED AND LAID WIRE CACK DOWN. REPLACED fl.ECTTOMCRETIC TIfE CELAY RELAY (fD3A). LIRITIED PRCFER GPERATICH Gr DICIEL CENERATCR U$1MG $1-10;E/3A. WR f:2392Bi. 02/1'07 I inn 070 C087 (9/19/881 EKRA-070 c?87-P,EcFIDu,rP2s],SrJNT PUXILItRY EONTACT 52A, CN THE $ HUNT TRIP MEAIER M4 CDtiACIS 52A f AILED TO CLOSE IREfKER, FAILED TU CL0ft CUE TO FCRfAL PRCitEn IDUWD OURIXG PEETOEMIEC WEAR CF THE EREAKIR CCHIACTS. REPLACED FLHCTICMAL TEff FCR VAltE 1-TCV-70 87 Et ThE 15 AnP 3HUHf TRIP IREArER LCCATED IN CEnPT.15El n3fCR CPERATED L*Ltt 10ARD. LIRIFIED PhCPER GrERATICH CF BREAIER U11XG 31-258.1 (WR i:273107). l'ii322 1 ~0TO c47' c;33 08/2U t3 1-(C10 067-c;83 A:Cx/FF:s],P3T02 PUxILItAY CONTACTS WEtt STICK!KG CUE TO CC8TACTC1 CCC! HOT MrE-L? EACH TI':I DElRIS MD HCIMAL WEAR CH CudiACTS. VoltE II SIECKED. CLEt'.A COMIACTCR PER REPLACED SOTH FRCif /30 310E EDUNTED n! 10.W. FEEDS CFT P.C'J [0 1Al A-Lui. eUXILI/AY RELAY CCMTACT ASSE."BLIES. M 073L52). by h i I l i I 'l -26= 1
u _am mMm we ammm_ m-- -m- --- .meu-.mam --A.h5_- l l i t I O l l l l I HAINTENANCE SDD!ARY (INSTRDtENTATION) l O h l I. i l i t O 1 l
A n mwn.st,aimta.wt ;.alati sunt:af v1-v /~'n i Gr> ..P2... 4 Fl%C SYS ADORESS. DATE.. DESCRIPTION.,.... CCCRECTIVE ACf!D:1. i 02370C3 2 !M (?1 0003L 08/04/83 2-FM-001-0003L-D,CWFDw3,HICH STEAM FLCW1:I-STAltCPICRUP. @ 024'4133 2 iR C01 0090 08/01/3a 2-FR-003-0090,CHGEDm],ttDE PEH TEMSIC'i ADJUSTMENT F01 NCMING PRDFERLY ( REPAIR /EEPLACE AS FECES!ARY l i:789961 1 fi 061 00911: 08/02/E31-fi-063-00911:,CWRDs],UENT AND OH REFAIR flCW TRANSMITTER-kHEN 1-fCV-7tr-33 i L'AS STR0 RED TLCW FAILED 10 CCM [$CK TO NCFMAL. AIR IS SUSPECTED IN TRANSMIffER 1 I i l i 'i l i l i I t l l l l 1, t 1 I i ) l@ 1 i 27-4 .-....-,-,-_,,._n,,,,, ._,-nr,------n_ .-.,,.,g v.---.,
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r Hl :5 Ctrf G2. 3 il2C !YS A M FESS DATE.. CESCRIPTIDN. ....... CUEECTIVE OCTIO. I:20 W 1 1 fLV Citi Cold 03/10/S31-fCV-074-0014,ERP24,:kPRDn3,uC-ZCNEuVA EDF.ML LTAR CN PACKIHC-REPnctED t'.UE LLE STEM LEAKIHG t.ND RETURNED TO SERVICE. ')121E^%1iCVC61 0191 C?/07/231-fCV 061-0191,[hKFP0m,xP283,UAlti RORML WEAR Cf VAltE PARTS-FEBUILT g/ CLOSES IN REGUIRED TITE [1JT IT Tftts THE VALUE, REPLACED 0-RINGS AED DIA?HEAG5. VAL 4T 310 3 MIN TU CIEN EACK UP. FETURHED VALVE TO SERVICE. 02%D1 1 ULV 0($ 0513 07/10/831-ULV-063-0515-5,TFE t?LVE 13 LEIriN!' pdKIEG 1:AD ITEN ADJUSTED CCW, >EECED SCR::N AT THE STEM. IWP REQUIRED r.3RE NCKING. ADCED UP.E P6CKING RING exD WIrfR WING. EETL'PMID TO SERVICE. GRI 02W301) IITS552 1 t1V 0(3 0549 C3/13/081-VLV-053-0%8-P,CiXPFDn],FEPAIR tlAltT XORML HCAR UN PACKING REPLACED PACKING !EAL LCf.C USING APPRDVED TVA PROCEDURES MD REWRNED VAltt 10 SERVICE. As LECES!ARY. I74 Mil 2 ICV 001 0013 03/09/83 2-fCV-001-0013 B, PLEA!E ADJUST PACKING PACKIFG EAS ricuN cui CR CUT EEY::FD CH 2 f CV-1-18. I1CWIFC PRETTY GiID. REPAIR, PihDVED CLD PACKING TO LAW 1EFN RING, CC'JLD NOI GET LMi[RN RI% CUT. PUT EIGHT RINGS (T NEW PACKIFG IN VALLI AND RETURNED TO SERVICE. Mt B768.99) '781163 1 i'? 07) CCA6 c?/03/331 Pr/-070-0046,ChxPRDn],PIR CAVID TEtPORARY LDSS CT CCCLINC knTER, CAUSE EUS$[LLS REGUEST; TEPACK 1 A CtaPGNENT Cr L353 !! TEr.PCTARf UkXWCW, PJS$IttE CCCLING SYSTEM Plt.P P ACKING CUE 10 M IHADVERTrdl ISOLAi!ON CT A l' Alt 7 \\ J O
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L MECHANICAL MAINTENANCE MONTHLY REPORT FOR AUGUST 1988 O Common 1. Completed repair on RAD MON pump 0-RM-90-12%. l 2. Completed SI-191.1 "Fire Hose Inspection." 3. Completed repair on "B" service air compressor. i Unit 1 l 1. Completed work on ERCW "A" and "B" MIC header. j 2. Completed diesel generator monthly inspection on 1A-A and 1B-B D/G. 3. Completed sweep and vent work on RCS. l 4 Completed glycol outage. i j 5. Installed new UHI rupture disc. 6. Completed work on condensate booster pumps. r 1 i 7. . Completed work on ice condenser. ] S. Completed repair on CCW traveling screens. ] 9. Completed repair on main steam check valves. i
10. Working on containment spray outage.
11. Completed work on RWST outage (freeze plug). ] 12. Completed work on heater drain pumps. [ j 13. Repacked ERCW pumps. i 14 Repaired several reach rod indicators. I 15. Cor;pleted work on several snubbers. I 16. Completed repairs on lower ot.cer airlock door. l 17. Repaired are strike on 1-FE.'4-12.
18. Completed repair on IB-B containment spray pump coupling.
19. Rebuilt emergency bearing tube water pump. 20. Installed row hydrogen analyzer pumps. 21. Repaired high point vent valve 1-VLV-3-352B. i 22. Completed repair on feedwater long cycle valve 1-MV0?-3-67. 23. Installed No. 5 hatch plug. 24. Completed repair on main turbine oil tank vapor extractor. ( 4 25. Roplaced several sight glasses on pumps of various systems. 26. Completed repair on 1-VLV-78-24.
27. Completed repair on 1-FCV-72-39.
l 28. Completed repair on feedwater regulator valves. 29. Rebuilt two glycol chillers. t 30. Installed No. 3 RCP plug. j 31. Rebuilt 1B-B boric acid transfer pump. ) Unit 2 1. Completed repair on condensato booster pump, i 2. Replaced ERCW traveling screen couplings. 3. Completed diesel generator monthly inspection on D/G 28-B. j 4. Completed work on condenser vacuum pump. i i Other i 2 j 1. Continued closure of various CAQRs, CARS. DRs. etc. l j l9 30-t i
'"""Aw---mmmmmnewm-mA m gg--.. mm__. m m. m.__, O I ? StAINTENANCE SUSNARY (MODIFICATIONS) l l t i O l 6 l O
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SUMMARY
OF WORK CCHPl.ETED l HODIFICATIONS - CURRENT STATUS I i l bOGUST 1988 O 9 I f I I 1 l l 9 I
l l i Major __ Capital Projects: pN7102: ECH 5938 - Replaco Foodwater Heators 3 and 4 No work in progress at this timo, pN7105: ECN 5009 - Essential Raw Coolinr. Water (RRCW) Piping Chanr,cout From Carbon Steel to Stainless Steel i No additional pipe replacement is scheduled in the near futuro. pH7108: ECU 6720 - Crano Consistency program a Unit 1 polar crano blocks and limit switch weights remain to be painted. Unit 2 polar crano post modification testing by Electrical Maintenance is not complete. Auxiliary Building crano (WP 12569) has completed review cycle. Turbino Building 200-ton crancs (Unit 1/6720-04, Unit 2/6720-03) WPs are approved. Turbino Building 15-ton crano Wps (Unit 1/6720-06, Unit 2/6720-05) and i [ \\ 5-ton Servico Building crano WP (6102-02) has been j k _, approved. s Modification of Turbino Building unit 2, 200-ton crano has begun. i pH7115: ECN 6719 - Volumetric Intrusion Detection Sysi s; ECN 6719 is in work. Design continues to work to make r j the system functional. Lighting is complete except for [ j a decision to be made on output of light on ono 50-foot l mast. Field Chango Roquest (FCH) 6645 for Nuclear Engineering (NE) changes 10 approved. Work is proceeding. l pN7122: DCR 1373 Secondary Side l i j No work in progress at this tino, i [NJJ30: DCR 1156 - post Accident Monitoring i This work to now scheduled by unit 1 cycle 4 (U1CA) and J. unit 2 by unit 2 cycle 4 (U2CA). i 1
i, U Major Capital projects (cont.): [N7132: DCN 0026 - Sowste Treatment Facility and Civil Upgrado l Work is nearing completion. Connections at the lift station and electrical supply to ti.o pumps is in J process now. pH7136: ECN 6259 - MSR Tubo Bundlo Replacosent ECN is completo execpt for postmodification testing (pHT) and incorvice leak test on unit 1. Leak checks will be performed during system heatup. Unit 2 leak checks are comploto. 4 4 pH7161: ECN 5855 - Replacement of Doors A56 and A57 j Wp 09679 renains on hold and is partially completo. i pH71bt: DcR 1898 - ECNs 6832 and 6596 - Dry Active Waste (DAW 1 Building Elcetrical interfaco work is complete. Workplan l closure hold for Elcetrical Maintenanco (WP 12478). [ ] checks and updato of Sois by Cperations, and Operations (Wp 12477) pending a revision for packing i dry active wasto. i l Significant Items: 1 1 l ) PN7199: Hiscellaneous Activities Under $100.000 a \\ l This was for various work orders prepared for work ~! under $100.000 total sito cost. This work was done as { i manpower resources were availablo, r 1 1 i 1 i 1 l l l I 1 1 ! r
) l f\\s I 06her Itogsi ECN 51,'l - Provido permanent Power to !;anholog 42-46 A t Four WPs remain in work. ,ECN 5503,- Evacuation Alarms O&pS/Firo Detection O&PS Work stopped for lack of funding. ECN 5552 - Condensato Dcmineralizer Modifications and High Crud Filter Upgrade to higher range instrumentation for condensato domineralizer system neutralization and nonreclaimabao wasto pumps. [ WP 5552 Fieldwork is completo. ECN 5609 - Evacuation Alarm /Firo Detection Valvo 26-290 KP 12387 is 90 percent complete and has been hold duo to manpower probicas. ,ECN 5609 - Alteratlon to the Makeup Water Treatment Plant s WP 12576 - Work is approximately 75 percent complete and is on hold for E1cetrical Maintenanco to perform breaker tests. Need resolution of instrument tab deceription from NE. WP 12633 - Work in approximately 80 percent complete. Hold for instrument tab (47B601-928) setpoint revisions. i WP 12731 - WP is approximately 80 percent complete. Hold for [ instrument tab (4 7B601-928) setpoints. Need connection diagram revisions from HE. WP 12684 - WP is approximately 80 percent complete. Hold for instrument tab ;47B601-928) setpoints. Need connection diagram revision fecm NE. WP 12665 - WP is on hold for outage and is 95 percant completo. WP 12682 - WP is on hold for outage and is 80 percent complete. i ECN 5626 - Containment Ladders. Unit 1 i Modifications needs additional design information to complete. NE l needs to issue all drawings listed on this ECN. Work has not begun because of this holdup.
l l i D] Other Items (cont.): ECN 5841 - Ilot Shop Firo Protection / Evacuation Alarm - WP 12360 is complete and in closure cycle. Need drawing deviation completed. WP 12637 - All fieldwork for evacuation alarm is completo. Awaiting W rk Request (VR) B240406 to be worked to restart fans to do functional test on firo protection. ECN 5935 - Correct Power Block Lighting Deficiencies ' WP 12437 is complete and in final review. WP 12275 is in work. Need WP revision for FCR 7706 to add approximately 40 more lights. WP 5935-01 is field complete. ECN 6196 - Pressurizer Hangers and Valves PMT is scheduled for unit i restart. Remaining unit 2 work is scheduled for U2C3 refueling outage. ,ECN 6357 - Essential Raw Cooling Water (ERCW) Roof Access and Rails for Security Equipment Original design for WP 12238 was rejected by Operations. NE to rework design to comply with Operations' needs and attempt to salvago existing work. ECN 6388 - Itydrogen Monitors in Switchyard WP 12223 - Work has been stopped due to a lack of funding. ECN 6429 - Component Cooling Ilcat Exchanger B Replacement Plate head exchanger and framo is complete. Hansces and pipe which can be installed prior to outage !s in work. WP to remove old heat exchanger is in review cycle. NE procuring the remaining necded piping material. Estimated completion dato for nonoutngo work is dur'ns the month of October 1988. ECN 6455 - Upgrado CU-3 Box Battery Packs WP 12295 is field complete. ECN 6543 - Install Public Safety Access Portals and Modify Entrance Road Work is being held pending the release of drawings from NJ. N Other Items (cont.): 1 ECN 6601 - Removal of Unit 1 Emergency Cas Treatment System (EGTS) Baekdraft Dampors l PMT remains to be completed by the Mechanical Test Section. Fieldwork is complete. ECN 6689 - Relocation of Main Steam Power Operated Relief Valves (PORV) I All work is complete for unit 2. Work on unit 1 in calibration rtage. WP 12172 (tubing reroutc) is 99 percent comploto and holding tor materlat consisting of tube fittings and clamps (PR 08-2768). ECN 6706 14 Support Enhancement / Lost Calculations Repairs continuo on unit 1. This project has been combined with the calculation regeneration project for unit 1. Unit 2 work is completo 4 i and workplans are closed. All fioldwork is completo. Document clocuro for unit I restart 13 in progress. j ECN 6739 - Alternato Analysis I All unit 1 modification work has been completed. Review and closuro is in progress for unit I restat t. ] ECN 6161 - East Valve Room (EVR) Blowout Pancis j ] i i Unit I work is complete. Unit 2 work is completo. l i ECN 6784 - Documentation to Show Pipo Class Breaks Final closuro is awaiting a revision to the plant modification j procedure for deleting requiremen.s to mark shift supervisor drawings. a i I ECN 6815 - 500-kV Switchyard Addition ) i Install 500-kV power circuit breaker and associated equipment for j bay 1. Retire 161-kV PCB and associated equipment. A total of 10 r 1 workplans will be required. Foundations and conduit installation (WP 12654) are complete. WP 12740 for lighting, drain pipe, and l + i surface ground mat is 95 percent complete. WP 12739 for the j structural stool installation is 95 percent complete. WP 6815-02 is i 90 porcent coeplete. WPs 6815-01 and -03 are 90 percent complete. l WPs 6815-04 and -05 for the electrical control board, main relay boards, and the comnunications room are 95 percent complete. WP 1 6815-06 for the addition of the Franklin solid state relay cabincts is i field complete. The Watts Bar No. 1 ilne was energized by bay 1 on ] June 21, 1988. Energitation of the Franklin line has been delayed i i because of prob 1 cms with an existing power circuit breaker (PCB 5028), and incorrect supply voltage for the static relay carrier sets. 1 3 1 4 35-i i J
p) tV Other Items (cont.): Ecti 6860 - Control Room Bullet Resistivity - DCR 2268 - Ecti 6860 WPs 12602 and 12604 aro field complete. WP 12603 is hold for disposition of CAQR 880183. WP 6860-01 is hold for material on Contract 14014A. Essentially all work is comploto except for pull handles, replacement of door closures, and rework of one lockcot. Estimated dato of completion is September 30, 1988. WP 12605 is in closure cycle. ECW 7078 - Install llangers - Main Steam Piping f Complete. I DCtl X00006A - Remove Hydrogen Analyzors Tubing The workplan lacks PMT. ECt1 7091 - Replacement of Feedwater Pipo Work is in progress and is 98 percent complete. Remaining work is hold for D/C testing. I Q DCt1200018B - Install tiecolo Valve for Hydrogen Analyzers The workplan lacks PHT. DCtl 70 - Ilydrogen Analyzer Check Valves I 1 The workplan lacks PMT. l f DCt1 341 - Pressurizer Drain Pipc/ttangers i j Work is in progress. j Instrtmentation Verification Program 1 For unit 2, the have been 953 discrepancies issued to MODS to date with 476 not t aqaired for restart. All dlierepancies required for l restart have been completed; 69 nonrestar, 'tscrepancios are open. For unit 1, there have been 532 discreponeles issued to MODS to date with 218 not required for restart. The 314 required for restart are { completo. 1 O IC
Other Items (cont.): DCN 224 - RHR Slopo Rcwork Train A completo, Train B needn outage. ECM 7241 - Replaco Valvo Room Inculation Work in continuing in both valvo rooms. DCN 27 - Doubio Isolation Valvos In work. ECJ 7345 - Valve Shims Work cosploto, workplan in closuro cycle. pCN 373 - Flex nono Rowork In work, pCN 214 - AFW Tap Rotation Completo. Instrument Maintenance to test. pCN 2dl - Sence Lino Hangers in work. ] DCU 19% - Ice Condensato Expancion Boitows Ucrk is in procoso. kqua 229 and 231 - H2 Analyzer Hodification Work is in progress on unit 1. j pCN 300 - ERCW Hodification for Microbiological 1y Induced corrosion (MIC) A Train is Completo, B Train in Work Unit I work is couploto. EQl 6'sti - Dry Active Waste Piping Interface WP 12402 - Workplan is closed. WP 12612 - Completo. Closure in process. SOIs are complete. The procedure for the fire detection system of cho Dry Active Waste Building is in thJ process of being updated by Electrical Maintenance. l i i - -.. - -.
O I 0FFSITE D1SE CALCULATION MANUAL ClfANGES I l \\ 1 1 i REVISION NO. 20 i \\ O l 0.
_ =. -.. _. - - - _ _ - 1 i f 1 i ) SXQUOYAH NUCLEA!! PLANT ~- QEDITfdSE. CAL"EATION FR{UAL I EITECTIVE PAGE LIRKING j REVISION 20 l t l EaM Revision I All Pages I Revision 20 1 I l t I h I I i J l I l l i l i EPL-1 i 1 t
SEOUOYAH NUCLL PLANT f-s OFFSITE DOSE CALCULATION MANUAL l\\s_-} IABLE OF CONTEMS Revision 20 page 1.0 Caseous Effluents 1.1 Alarn/ Trip Setpoints 1 1.1.1 Release Rate Limit Methodology - pCi/s 1 Noble Gases - Dose Rates 1 l Total Body Dese Rate 2 Skin Dose Rate 2 Iodinet and Particulates - D>se Rates 2 Initial Setpoints 2 i Release Mix Specific Setpoints 3 ] Satpoints 4 } Initial Setpoints 4 %) Release Mix Specific Setpoints 4 i 1.2 Monthly Dost Calculations 6 i 1.2.1 Montiily Noble Gas Dose (Conservative Model) 6 h j 1.2.2 Monthly Dose fram Iodines, Particulates and Tritium (Censervatise. Model) 9 i i l 1.2.3 Mor.thly Noble Gas Dose (Realictic Model) 12 1.2.4 Iodines. Particulates and Tritium (Realistic Model) 13 i 1.2.5 Cumulative Quarterly and Annual Doses 13 i 1.2 Quartarly Dose Calculations 14 [ i l TOC - 1 I 1 F 2...... 1 l ^ .~.
I' i ) EQUOYAH NUCLEAR PLAHI l OFFSITE D9JE CALCULATION MANUAL TABLE OF CONTEffrS (CONTINUEDM i I Revision 20 s page I f 1.4 Gaseous Radvaste Treatment System Operation 16 1.4.1 System Description 16 ) 1.4.2 Dose Projections 16 b 1.5 Gaseous Releases - Dose Calculation Equations 17 f j 1.5.1 Noble Gas - Gamma air Dose 17 I l 1.5.2 Noble Gas - Beta air Dose 17 [ q 1.5.3 Radioiodine, Particulates and Tritium - Maximum Organ Dose 18 l l 1.6 Caseous Releases - Dose Factors 20 i l 1.7 Dispersion Methodology 33 1.7.1 Air Concentration 33 l i j 1.7.2 Relative Coo",netration 34 { 4 1.7.3 RelatEve Deposition 35 l l i, f j 2.0 L' quid Effluents i l J 2.1 Concentration 1 i 1 1 i 2.1.1 RETS Requirement 36 l 4, i 2.1.2 Prerelease Analysis 36 l t 2.1.3 MPC - Sum of the Ratios 37 i t { 2.2 Instrument Setpoints 38 1 1 2.2.1 Setpoint Determination 38 4 i 2.2.2 Post-Release Analysis 38 l l j TOC - 2 l 4 i il 4 g..... j! 1 ~ '
SEOUOYAH FTUCLEAR PLANT OFFSITE DOSE CALCULATION MAf(WLI, IABLE OF CONTENTS (C0JRil(UEDJ - Revision 20 Ptge 2.3 Dose 2.3.1 RETS Requirement 39 2.3.2 Monthly Analysis 39 2.3.2.1 Water Ingestion 40 2.3.2.2 Fish Ingestion 41 2.3.2.3 Recreaticn 42 2.3.2.4 Monthly Sum ary 43 2.3.2.5 Dose Projections 44 2.3.3 Quarterly and Annual Analysis 44 2.3.3.1 Individual Doses 44 2.3.3.2 Population Doses 47 2.4 Operability of Liquid Radvaste Equipment 48 3.0 Radiological Environmental Monitoring 3.1 Monitoring Program 49 3.2 Detection Capabilities 49 3.3 Interlaboratory Cc=parison Program 49 3.4 Land Use Census 50 I l 4.0 Annual Maximu= Individual Doses - Total 51 1 i TOC - 3 O l a....
1 SIQUDIAM NUCLEAR.PLAlfI QTFSITE DOSI.f,.ALGULATION MANUAL" LIST OF TABLFJ REVISION 20 page 1.1 SQN - OTTSITE RECEPT 0R LOCATION DATA 52 1.2 EXPECTED ANNUAL ROUTINE GASEOUS RELEASES TROM OMt UNIT AT SEQUOYAN NUCLEAR PLANT $3 1.3 JOINT PERCENTAGE TREQUENCIES OF WIND DIRECTION AND WIh3 SPEED TOR DITTERENT STABILITY CLASSES 54 i 1.4 DOSE TACTORS FOR SUBMERST.0N IN NOBLE CASES 62 1.5 SECTOR ELEMENTS FOR POPULATION DOSES 63 [ 1.6 POPULATION WITHIN EACH SECTOR ELEMEMT 64 ) 1.7 INGESTION DOSE TACTORS 65 [ 1.8 RADIONUCLIDE DECAY AND TRANSTER CATA 73 1.9 DOSE CALCULATION TACTORS 75 1.10 IUllALATION DOSE TACTORS 77 k 1.11 EXTERNAL DOSE TACTORS FOR STANDING ON CONTAMINATE 9 CEOUND 85 i 5 2.1 INGESTION DOSE TACTORS I 47 i i 2.2 FISH CONCENTRATION TACTORS f 91 j Ps3 RECREATION DOSE TACTORS 93 i 5 2.4 FUBLIC VATER SUPPLY INFORMATION [ 97 { 2.5 FISH HARVEST DATA 98 2.6 RECREAft0N USACE DATA 99 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORNG FROGRAM 100 I t 3.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROCRAM SAMPLING 104 [ t 3.3 SEQUOYAH NUCLEAR PLANT THERMOLUM!NESCENT DOS! METER 106 l LOCATIONS 3.4 MAXIMUM VALUES FOR THE LOWER LINITS OF DETECTION (LLD) 108 l t I TOC - 4 1 l } 1 w :--.- -.~~
^ \\ SEQUDIAH.MLCLEAR P1ANI i 0FFSITE DOSLQALQUI,AUQJif,aFUAL" sq klil AEllir2Efd REVISION 20 page 4 1.1 SQN LAND SITE EOUNDARY 110 l 1.2 GASEOUS RADWASTE TREATMENT UYSTEM 111 y 1.3 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 112 t 1.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 113 4 1.5 RELATIVE DEPOSITION FOR GR00(D LEVEL RELEASES 114 3.1 RADI0 LOGICAL EfNIR0!iME? CAL SAMPLING LOCATIONS - WITHIN i 1 MILE OF PLAliT 115 3.2 RADIOLOGICAL EtNIRONME CAL SAMPLING LOCATIONS - WIT!!!N I 1 TO 5 MILES OF PLAtc 116 3.3 RADIOLOGICAL E!NIR0!&,NTAL S A;'lPLING LOCATIONS - GREATER TilAN 5 HILES OF PLANT 117 i ) i i I J l l l I j 1 j i ) l J TOC - 5 I i C i \\ i j i g*-... i ~ ~ =_= 'l
SQN ODCM Page 1 of 117 ~ ' Revision 20 m ) 1.0 G31cs.gs "ffluenta 1.i alArmLIrip_Sitralnia Specification 3.11.2.1 requires that the dose rate at or beyond the site boundary (Figure 1.1) due to gaseous effluents from the site shall te limited at all times to the following values: 1, 500 mres/y to the total body and 3,000 mrem /y to the skin from noble gases. 2. 1,500 mrem /y to any organ from radiotodines and particulates. Specification 3.3.3.10 requires gaseous effluent monitors to have alarm / trip setpoints to ensure that the above dose rates are not exceeded. Th!s section of the ODCM describes the methodology that will be used to determine these setroints. The methodology for determining alarm / trip setpoints is divided into two major parts. The first consists of backcalculating from a dose rate to a release rate limit, in pC1/s, for each nuclide and relesse point. The recond consists of using the release rate limits to deternine the physical settings on the conitors. l 1.1.1 Reltase Ratel imit Methodolsty - uqiZn Relent _ bit _LiniL11tihedolery - Desclitra First, a dose rate is calculated based on the design objective source term mix used in the licensing of the plant. Dose rates are determined for (1) noble gases and (2) todines and particulates. Etitue Rate Limit Mtthndaloav - Dese Rates - Noble Cas I Dose rates are calculated for total body and skin, due to submersion within a cloud of noble gases, using a semi-infinite cloud model. The dose rates are evaluated at the offsite locations with the highest j expected concentrations, i.e., the nearest land site boundary points in l each sector (from Table 1.1). The noble gas radionuelide mix used in this calculation is based on the o sign objective source tern given in Table 1.2. Dispersion of the released radioactivity is handled as described in Section 1.7 using historical annual average meteorological data given in Table 1.3. l Ne credit is taken for shielding by residence. 'D
Entire page changed 1157c T - -~ ~
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_. _ _ _. ~ l l 3 SQN ODCM f Page 2 of 117 i 3 - Revision 20 1 I i To calculate the dose rate for any one of the 16 potential } maximum-exposure points, the following equations are used. i i i Il Total Body Dese Rate l 1 j DTB = I Xg DFBt (1.1) f where I j DTB = total body dose rate, mrem /y. 3 Xg = air concentration of radionuclide 1, pC1/m8 Air j concentrations are calculated as described by Equation 1.16. f i ] DFBt = total body dose factor due to gamma radiation, mrem /y per [ pC1/m3 (Table 1.4). I ,I L ] 51rin Dese R at., 1 { Ds = I Xg (DTSg + 1.11 DP g) (1.2) y j i i i vhere l i Ds = skin dose rate, mrem /y. } Xg = air concentration of radionuclide 1, pCL/a8 Air { concentrations are calculated as described by Equation 1.16. f l ) DTSg = skin dose factor due to beta radiation, area /y per pC1/m3 (Table 1.4). I 1.11 = the average ratio of tissue to air energy absorption coefficients, urem/arad. ] Dryg = gama-to-air dose factor for radionuclide 1, arad/y per { 4 i pC1/m3 (Table 1.4). 3 I Release Rate Limit Methodolony - Iodine and Particulate Dese Rates ( Inittai Setroints For initial setpoints, the iodine and particulate dose rates are i i calculated for the design objective source tern given in Table 1.2. Dose i j
Entire page changed 1157c
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SQN ODCM q page 3 of 117 Revision 20 l rates are esiculated for the critical organ, thyroid, of the critical age 1 i group, infant. Pathways considered are inhalation, gro'and contamination and milk ingestion. The dose rated are evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest land site boundary points in each of the 16 sectors (from Table 1.1). This calculation assumes that a (hypothetical) cov is at each of these locations. These cows are assumed, conservatively, to obtain 100 percent of their food from pasture grass. The inhalation, ground cor,tamination, and milk ingestion dose rates (in mrem / year) for the selected organ (thyroid) and age group (infant) are calculated using Iquation 1.15 as described in Section 1.5.3. For determining the total thyroid dose rate from iodines and particulates DTit = DTill + DTBG + D }m (1.3) 7 where D }{ = total thyroid dose rater, mres/yr. 7 DTl!I thyroid dose rate due to inhalation, mrem /yr. = DIBG = totti body dose rate due to ground contamination, crem/yr. i The thyroid dose rate is assumed to be equal to the total body dose rate for this pathway. Dr}m = thyroid dose rate due to pasture grass-cow-milk ingestion. { mres/yr. i E.timtJilx_Itttific Stipaint l I l i Tor release mix specific setroints, the todine and particulate dose rates 1 j are calculated for a known source term. Dose rates for each particular l nuclide are calculated for the critical organ (bone, liver, thyroid, i lung, kidney or lung) of the critical age group (adult, teen, child or infant). Pathways considered are inhalation, ground contamination, pasture grass-cov-milk ingestion, stored feed-cov-milk ingestion, pasture grass-beef ingestion, stored feed-beef ingestion, fresh leafy vegetable l l ingestion and stored vegetable ingestion. The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest land site boundary points in each of the 16 sectors (from Table 1.1). This calculation assumes that hypothetical milk and beef I cows are at each of these locations. The dose rate (in mrem / year) for the selected organ and age group are 1 calculated usint Equation 1.15 as described in Section 1.5.3. Meteorological dispersion is handled as described in Section 1.7, using historical annual average meteorological data given in Table 1.3. All pathsays are evaluated for each nuclide.
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7 SQN ODCM Page 4 of 117 1 Revision 20 1 5' j Feleut_Rait.htmlt Methodolotv - Setpolnia 4 l hil1}Al $ e t SQit112 Tha dose rate limits of interest (Specification 3.11.2.1) are: l Total Body = 500 ares /yr i Skin = 3000 ares /yr Maximum organ = 1500 arem/yr 4 i For the determination of. initial setpoints, the above limits are divided I by the appropriate calculated dose rate ) { Dose rate limit =R Calculated dose rate 1 The ratio, R, represents how far above or below the guidelines the dose rate calculation vas. Multiplying the original source term (in i l Table 1.2) by R will give release rates that should correspond to the dose rate limits given abeve. i l i Appropriate release rate limits in pC1/s for each nuclide and release 2 point will be provided to plant personnel for use in estabitshing monitor l setpoints. The setpoint for each gaseous effluent monitor vill be established using plant instructions, The geaeral equation used by plant personnel in establishing setroints in i tem from release rate limits in pCi/s is as follows: C= 0 * " 6(_ y 28320 (1*4) vheret ( C = monitor setpoint, cpm. 1 Q = release rate limit, pC1/s. e = detector efficiency, cps /pci/ce. l a = safety factor! 0.2 for systems without automatic isolationt ] 0.5 for systems with automatie isolation. 60 = s/ min. 3 28320 = cc/ft. V = flow rate out the vent, cfm. 1 I
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i SQti CDCM i Page 5 of 117 I Revision 20 I l Relnaedale Limit Methodelsrv - Settpolnia EtteatrJitx_ Specific Seteointa When release mixes are knovn, setpoints are calculated using the dose rate methodology given above, based on the known mix rather than the ( design source term mix. Using a normalized source term (qt) for each nuclide, nuclide specific dose rates (Dg) are determined for each i nuclide using the dose rate methodology described above. Dividing the I appitcable dose rate limit by the nuclide specifte dose rate, Dg, j yieldst ( l Dose Rate limit = ri Di This ratio, ri represents how far above or below the guidelines the I nuclide specific dose rate (D ) is. Multiplying the normalized source 1 ] term (qt) by rg vill give the maximum allovable release rate R l j nuclide 1. t for I I ,1 I t l The eaximum allovable release rate, R, for each nuclide is also t i calculated by an alternate methodology based on the reporting requirements of 10 CFR 50.73 (2 times the 10 CFR 20 Appendix B. Table II air concentrations). Release rate limits Rt in pCi/s, for each nuclide are calculated using this methodology as given below: i i l i R t = (5.12x10-8)(10-8) (1.5) = 3.91x1011 MPCt 1 i vhere i MPCi = the 10 CFR 20, Appendix B. Table II, air concentration, pCi/ce. 1 l 5.12x10-'= vorst land site boundary X/Q, s/m3 (Table 1.1), i 5 1 ) 10-' = conversion factor, m3/cc. 1 i The release rate limit, Ri in pC1/s, for each nuclide vill be the cost restrictive one calculated using both eethodologico. 2 l 1 Tor a knwn mixture of n nuclides the release rates, Qg, must be auch + hat: n q l I < 1 I i=1 Rt 4 J
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SQN ODCM page 6 of 117 Revision 20 The appropriate release rate limits R. in pCi/s for each nuclide t and release point will be provided to plant personnel for use in establishing monitor setpoints. The setpoint in counts per minute for each gaseous effluent monitor vill be established using plant instructions. The general equation used by plant personnel in establishing setpoints in eps from release rate limits in pC1/s is l Equation 1.4 1.2 Mq1ghly.Dese Ca.11n1Rient 1 t Dose calculations vill be performed once per 31 days to determine i compliance with Specifications 3.11.2.2 and 3.11.2.3. These specifications require that the dose at or beyond the site boundary due to gaseous effluents from each reactor at the site shall be limited to the followingt i Tor noble gases, 1. During any calendar quarter, 5 mrad per unit to air for gamma radiation and 10 mrad per unit to air for beta radiation. O 2. During any calendar year,10 mrad per unit to air for gar.ma radiation and 20 mrad per unit to air for beta radiation. i For 1-131. I-133, tritiu,, and particulates with half lives greater than l 8 days, i ~ j 1. During any calendar quarter, 7.5 mres per unit to any organ. 2. During any calendar year, 15 mrem per unit to any organ. d 1 This section of the ODCM describes the methodology that vill be used to 1 perform these monthly calculations. 1 l Doses vill be calculaced using the conservative model described in i Sections 1.2.1 and 1.2.2. If 50 percent of the conthly fraction of the 2 t unit annual Technical Specification Limit is exceeded, a realistic model, ] described in Sections 1.2.3 and 1.2.4, vill be used. I 1 1.2.1 Monthly Noble Gas Dost (Conservative Model) 1 i l Doses to be calculated are gamma and beta air doses oue to exposure to a semi-infinite cloud of noble gases. Releases of Ar-41. Kr-85m Kr-55, Kr-37, Kr-88, Xe-131m. Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 are i considered. Because only these nuclides are considered, the dose is divided by 0.9, to account for a possible 10 percent contribution of dose from other nuclides. l
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SQN ODCM Page 7 of 117 -- Reviaton 20 l 2 The dispersion factor used vill be the highest annual-average x/Q based on 1972-1975 eeteorological data (Table 1.3) for land-site boundary locations. Dispersion factors are calculated using the methodology described by EquaNion 1.17. l No credit As taken for radioactive decay, i tienthly_CfDiervat ive _ Madel - Ga?.ma dtge to__ alt 08 y = (X Q) I Qi DTyt (1.6) D l 0.9 3.15x107 i ? a j vhere Dy = gamma dose to air, trad. s f X/Q = highest land-site boundary annual-average relative l concentration, 5.12x10-6 s/m3 (from Table 1.1). 1 0.9 = fraction of total ga==a dose expected to be contributed by the 3 assumed nuclides. 1 i 106 = pC1/Ci conversion factor. Y I ~/ 3.15x107 = s/yr conversion factor. Qi = conthly release of radionuellde 1, C1, j Dryg = gamma-to-air dose factor for radionuelide 1, mrad /yr per pC1/m3 (Table 1.4). For Kr-88 end Xe-138, the dose i factors for Kr-SS+D and Xe-133+D are used to account for daughter buildup. i l f 4 I i l I ( i 1 1 r l l l L
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SQN ODCM i Page 8 of 117 l - Revision 20 (D Month 1.Y 19n3.tr.YAtht.E0Ae1..B(IA_A0se to aII l (x Q) 108 Da = I Qi Drgt (1.7) 0.9 3.15x108 g wheret l DD = beta dose to air, mrad. l X/Q = highest land-site boundary annual-average relative concentration, 5.12x10-8 s/m3 (from Table 1.1). 0.9 = fraction of total beta dose expected to be contributed by the assu.-ed nuclides. 108 = pCi/Ci conversion factor. 3.15x10' = s/yr cenversion factor. Qi = monthly release of radionuclide 1. C1. Dr g = beta-to-air dose factor for radionuclide 1. mead /yr per a pC1/m3 (Table 1.4). For Kr-88 and Xe-1J8, the dose factors for Kr-88+D and Xe-135+D are used to account for i daughter buildup. r i l i I I l
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i SQN ODCM Page 9 of 117 Revision 20 g 1.2.2 Month 111 oat _frem redinu,_httinlatuanutitha (Conservative v Model) 1 Doses are to be calculated for the infant thyroid from milk ingestien and for the child bone and teen gastrointestinal tract (CIT) from vegetable ingestion. Releanes of !!-3, I-131, and 1-133 are considered for the milk i pa' htsy. !!-3, 3r-89, Sr-90, Cs-134, and Cs-137 releases are considered for the vegetable pathway to the child bone. H-3, Co-58, and Co-60 l releases are considered for the vegetable pathvay to the taen GIT. The most critical real cov location is considered for the milk pathway and the most critical location with a home-use garden is considered for the vegetable pathways (see Table 1.1). The cow As assu ed to graze on i l pasture grass for the whole year. The highest annual-average X/Q and D/Q based on 1972-1975 meteorological data (Table 1.3) vill be used for ingestion pathway locations. Dispersion valu:s are calculated as described by Equations 4 1.17 and 1.18. i No credit is taken for radioactive decay. l Doses are divided by 0.9 to account for a possible 10 percent j eentribution from other nuclides, l tienihlylon4 e rlat.ir& del - In bnt_Thynlun t_f tenJiLi k_ Int.n t_isn 1 The monthly thyroid dose frem.nilk ingestion is calculated using the following equations 1 Drn = -1(Q1 Rcpg) D/Q lot + (Qr RCPT) X/Q I j (1.3) i 0.9 x 3.15x107 j vhere 1 l Qt = monthly release of todine nuclide 1. C1. QT = renthly release of H-3, Ct. 1 RCP1 = I-131 or I-133 pasture grass-cov-milk ingestion dose factor for infant thyrold, cr m/yr per pC1/m8-s. Dose factors j are calculated as described in Section 1.6.1. 1 Repy = H-3 pasture grass-cov-milk ingestion dose (tetor for infant j thyroid, mres/yr per pC1/ce. The dose factor is calculated j as described in Section 1.6.7. i D/Q = highest relative deposition rate for a location with an j identified milk cov 1.10x10-' m-a (frem Table 1.1). l
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1 SQN ODCM Page 10 of 117 Revision 20 l V X/Q = highest relative air concentration for a location with an identified milk cow, 6.18x10-s s/m8 (from Table 1.1). 2 0.9 = fraction of dose expected to be contributed by I-131, I-133 and H-3. 3.15x107 = s/yr. 10' = pC1/C1. a i tignthly Conservative Model - Child Bene Dese from Ventahlt_Innatinn The monthly bone dose from vegetable ingestion is calculated using the following equation I i DBC = -1 (Qg DF ) D/Q 10' + QT DFT X/Q (1.9) ] 0.9 x 3.15x107 s where i Qt = monthly release of Sr or Cs nuclide i, C1. 4 l j Qy = monthly release of H-3, C1. Drg - Total vegetable ingestion dose factor to child bone for Sr-89, St-90, Cs-134 or Cs-137, trem/yr per pC1/m -s. i a ] = Ryyt + RVS1, where Ryyg is the dose factor for frc=h leafy j vegetables (as calculated in Section 1.6.5) and Ryst is the dose factor for a u ted vegetables (as calculated in Section 1.6.6). DTT = Total vegetable ingestion dose factor for child bone for !!-3 mres/yr per pC1/ce. l l = Ryy7 + RVST, where Rypt is the trittu:n dose factor for fresh r i leafy vegetables (as calculated in Section 1.6.11) and RVST ta the tritium dose factor for stored vegetables (as calculated in Section 1.6.12). l D/Q = highest relative deposition rate for a location with an identified heme use garden. 6.38x10-' m-a (from Table 1.1). 1 x/Q = highest relative air concentration for a location with an identified hcme use garden, 3.42x10-6 s/m3 (from Table 1.1). t 3.15x107 = s/yr. j 1 1 10' = pCi/C1. j m l 0.9 = fraction of total child bone dose expected to be contributed by i B-3, Sr-39, Sr-90, Cs-134, and Cs-137. l t
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SQN ODCM Page 11 of 117 Revision 20 4 b Monthly ConurntlitJigul - Teen cutnintu11nal Tract (gin _Dut_ firm Y.cf.e t abl e. IDS RM12D i The monthly teen G1T dose from vegetable ingestion is calculated using the following equations I ) DGT = -1 (Qt DTg) D/Q 10' + Qt DTy X/Q (1.10) 0.9 x 3.15x107 l vhere Qi , = monthly release of cobalt nuclide 1, C1. j Qt = monthly telease of H-3, C1. DTg = Total vegetable ingestion dose factor to the teen G1T for Co-58 or Co-60, mrem /yr per pC1/m -a. a = Ryyt + Ryst, where Ryrg is the dose factor for fresh leafy vegetables (as calculated in Section 1.6.5) and Pyst is the dose factor for stored vegetables (as calculated in Section 1.6.6). DTy = Total vegetable ingestion dose factor to the teen G1T for H-3, mrem /yr per pC1/ce. I = Rypt + Rys7, where Rypt is the tritium dose factor for fresh leafy vegetables (as calculated in Section 1.6.11) and i Ryst is the tritium dose factor fo stored vegetables (as calculated in Section 1.6.12). D/Q = highest relative deposition rate for a location with an identified home use garden 6.38x10-' a-a (from Table 1.1). 4 i x/Q = highest relative air concentration for a location with an i [ identified home use garden, 3.42x10-8 s/m3 (from i Table 1.1). j l t ] 3.15x107 = s/yr. I l ) 106 = pC1/C1, l l ) 0.9 = fraction of total teen G1T dose expected to be contributed by l 1 H-3, Co-58, and Co-60. ] i i Lotal Menthly Dose - Ceepn h gn_to Li~its a { 1 The calcultiid ga.m a-air and beta air doses are co: pared to the monthly ] fraction ot the aanual 2-unit Technical Specification limits for these j b V l
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i SQN ODCM Page 12 of 117 l Revision 20 i i doses, i.e.,1.67 mrem for gama-air and 3.33 mrem for beta-air. The maximum monthly organ dose is the highest of the three doses calculated; l it is compared to the monthly fraction of its annual limit, i.e., 2.50 l i e em. If any of the doses calculated by the conservative monthly dose l } el exceed 50 percent of the monthly fraction of the 2 unit annual n. i Te sical Specification limits, a more comprehensive dose assessment vill l be,arformed as described below. For doses calculated to be less than 50 1 percent of these limits, the reeults of the conservative monthly model l r vill be used to determine cumulative quarterly and annual doses as described in Section 1.2.5. J l 1.2.3 tienthlyJkb1L9as DosL(Realistic Model) ] In the realistic model, all measured radionuclides are used to calculate g, ma and beta air doses. The dose is evaluated at the nearest land site boundary point in each sector using a semi-infinite cloud model, i i I 1 Historical onsite meteorological data from the period 1972-1975 ) (Table 1.3) vill be used to calculate dispersion factors as described in Seetion 1.7. i i Radioactive decay is considered in this calculation. } The monthly release is averaged over one year to obtain an average i i release rate. l l Ef 411R1AfadR1 - GCLduc_1Lalt i f q i Dp=tm I Yni DIy1 (1.11) 1 1 i j vhere: 1 } D = gamma dose to air for sector n, mrad. f p L t j Xni = air concentration of radionuclide i in sector n, i J pC1/m3 Air concentrations are calculated as described by Equ tion 1.16. i Dr g = gana-to-air dose factor for radionuclide 1, mrad /yr per i 4 y i pC1/m3 (Table 1.4). 1 tm = time period over which the release is avera;;ed, yr, ( t I I i 4 f
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SQN ODCM Page 13 of 117 Revision 20 O k-s- Realistic Model - Beta dose to air } Xni DFBi (1+12) DBn " tm i where: DBn a beta dose to air for sector n, mrad. air concer.tration of radionuclide i in sector n, Xni = 3 pC1/m. Air concentrations are calculated as described .by Equat.on 1.16. DTDi = beta to air dose factor for radionuclide i, mrad /yr per 3 pCi/m. time period over which the release is averaged, yr. t = m The land site boundary locations having the highest gamma and beta doses are then used in the cumulative quarterly and annual dose determination to check compliance with Specification 3.11.2.2. 1.2.4 Iodines. Particulates and Tritium (Realistic Model) Doses for releases of iodines, particulates, and tritium will be calculated using Equation 1.15 given in Section 1.5.3. The calculation will consider all measured radionuclide releases. The dose will be evaluated for all organs and all age groups, and the maximum organ dose selected. Actual land use survey data and grazing information will be used to determine the dose for real individuals and pathways. The highest gamma-air and beta-air doses calculated will be used in the cumulative quarterly and annual dose determination to c. heck compliance with Specification 3.11.2.2. The highest organ dose for a real receptor is determined by summing the dose contribution from all real pathways including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingastion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors). The receptor having the highest organ dose is then used in the cumulative quarterly and annual dose determination to check compliance with Specification 3.11.2.3. 1.2.5 Cumulative _ quarlsriv and Annual Dosta Cumulative calendar quarter doses are estimated by summing the doses calculated for each renth in that quarter. Cumulative calendar year doses are ertimated by summing the doses calculated for each month in i +/ that year. the cumulative calendar quarter and calendar year doses are compared to their respective 2-unit Technical Specification limits to determine compliance. f.
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SQN ODCM 1 Page 14 of 117 Revision 20 0' 1.3 Ouarteriv Dose Calculations A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in Specifications 6.9.1.8 and 0.9.1.9. Methodology for this analysis is that which is described in Section 1.5, using the quarterly release values reported by the plant personnel. - All real pathways and receptor locations (as identified in Table 1.1) are considered. In addition, actual meteorological data representative of a ground level release for each corresponding calendar quarter will be used. The highest gamma-air and beta-air doses calculated will be used to check compliance with the quarterly limits of Specification 3.11.2.2. The highest organ dose for a real receptor is determined by summing the dose contribution from all real pathways including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is idettified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors). The receptor having the highest organ dose is then used to check compliance with the quarterly limits of Specification 3.11.2.3. P_qpylation Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 1.5. For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 1.5). For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally. The general equation used for calculating the population dose in a given sector element is: Dosepop = I RATI0p
POPH

AGE

0.001

DOSEp P
where RATI0p = ratio of average to maximu:n dose for pathway P. (Average ingestion rates arc obtained from Regulatory Guida 1.109, Tablo E-4.) p = 0.5 for submersion and ground exposure pa hvays, a shielding / occupancy factor. f \\
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,w= SQN ODCM Page 15 of 117 Revision 20 O = 1.0 for the inhalation pathway. = 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (tt is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.) = 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, and adult, respectively. = 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.) POPN = the population of the sector element, persons (Table 1.6). AGE fraction of the population belonging to each age group. = = 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from !WREG/CR-1004, Table 3.39). 0.001 = conversion from mrem to rem. DOSEp = the dose for pathvay P to the maximum individual at the location under consideration, mrem. For ingestion p1thvays, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as.' ADC = exp(-l t), for milk and vegetables, i where 11 = decay constant for nuclide i, seconds, i t = distribution time for food product under consideration (values from Regulatory Guide 1.109, Table D-1). i = 1.21E+06 seconds (14 days) for vegetables. = 3.46E+05 seconds (4 days) for milk. I exp(-A t) l teb i i ADC = , for meat, 1 - exp(A teb) l i where 11 = decay constant for nuclide 1, seconds. e i
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m. i SQR ODCM Page 16 of 117 Revision 20 %/ = additional distribution time for meat, over and above t the time for slaughter to consumption described in Section 1.6.3, 7 days. teb = time to consume a whole beef, as described in Section 1.6.3. For beef ingestion, the add.itional factors in the calculation of ADG negate the integration of t.he dose term over the period during which a whole beef is consumed, foe the calculation of population dose. This assumes t. hat the maximum individual freezes and eats a whole beef, but i the average. individual buys smaller portions at a time. Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population. 1.4 Gn eous Radvaste Trt:1tment System Ooeration The gaseous radvaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA. [ 1.4.1 System Desc_riplian A. flow diagram for the GRTS is given in Figure 1.2. The system consists of two vaste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Caseous vastes are received from the followingt degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header, and toren recycle process operation. i 1.4.2 Dose Projections In accordance with specification 3.11.2.4, dose projections will be performed. This vill be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month. The projected doses are compared to the limits of specification 3.11.2.4, i.e., 0.4 mrad gamma, 0.8 mrad beta, and 0.6 mrem to any organ. If the projected doses exceed any of these limita, the gaseous radvaste treatment sy. stem and the ventilation exhaust treatment system shall be I used to reduce radioactive materials in gaseous effluents to areas at or l beyond the s'te boundary. 4 a
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i n f SQN ODCM Page 17 of 117 Revision 20 h I 1.5 CASEOUS REI. EASES - Dose Calculation Equations 1.5.1 Noble nas - Gamma _ air dost i Gamma air doses due to exposure to noble gases vill be estimated with the following equation: I Dya Xim DFyi (1.13) i t r i where: e D y Gamma air dose, mrad. [ = concentration of nuclide'i at location m, pC1/m3 Air Xim = concentrations are calculated as deset! bed by Equation 1.16. y dose conversion factor for external gamma for nuclide i, Dr g = mrad / year per microcurie /m3 (Table 1.4). 1 1.5.2 Noble cas - Beta _ air dose h Beta air doses due to exposure to noble gases vill be estimated with the following equation: Da = X m Drgi (1.14) i vhere: l I Da Beta air dose, mrad. = Xim concentration of nuclide i at location m, pC1/m3 Air = concentrations are calculated as described by Equation 1.16. j tr i dose conversion factor for external beta for nuclide i, t a = i mrad / year per microcurie /m3 (Table 1.4). 1 { 1 4
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1 i i SQN ODCM Page 18 of 117 Revision 20 \\.- 1.5.3 Radiolodine. earticulate and tritium - Maximum organ dose Organ doses due to radioiodine, particulate and tritium releases are calculated using the following equation: i Dorg = 3.17E-CS ( I (X/Q I Rpi + D/Q Rai + X/Q rig) Qi + (X/Q RPT) QT) (1.15) i P where: brgandose, mrem. D c. org 3.17E-0( = conversion factor, year /second. X/Q Relative concentration for location under consideration, see/n3, = Relative concentrations are calculated as described by Equation 1.17. Rpi = ingestion dose factor for pathway P for each identified nu:liue i (except tritium), m2-mrem / year per microcurie /second. Ingestion pathways.available for consideration include: O pasture grass-cow-milk ingastion stored feed-cow-milk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetrble ingestion Equations for calculating these ingestion dose factors are given in sections 1.7.1 through 1.7.6. D/Q = Relative deposition for location under consideration, m-2, Relative deposition is ca:culated as described in Equation 1.18. Rai = Dose factor for standing on contaminated ground, m2-mrem / year per microcurie /second. The equation for calculating the ground plane dose factor is given in Section 1.6.14. J 4 RIt = Inhalation dose factor, mrem / year per microcurie /m3 The equation for calculating the inhalation dose factor is given in Section 1.6,13. i l 1 l
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SQN ODCM Page 19 of 117 Revision 20 g. \\s. Qi = adjusted release rate for nuclide i for location under consideration pC1/sec. The initial release rate is adjusted to ~ s account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release ratr decayed for an average travel time during the period. 9 = Qin I fj exp(-11 x/uj) j=1 where -Qio = initial average release rate for nuclide i over the period, 4 pCi/sec. fj = joint relative frequency of occurrence of winds in windspeed clacs j bicving toward this exposure point, expressed as a fraction. 11 = radiological decay constant for nuclide i, see-l. e x = downwind distance, meters. uj = midpoint value of wind speed class interval j, m/s. RPT = ingestion dose factor for pathway P for tritium, m2-mrem / year per microcurie /secoad. Ingestion pathways available for consideration are the same as those listed above for Rpt. Equations for calculating ingestion dose factors for tritium are given in sections 1.7.7 through 1.7.13. QT = adjusted release rate for taitium for location under consideration, pCi/sec. Calculated in the same manner as Qi above. l l i l i e 4 j
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SQN ODCM Page 20 of 117 . Revision 20 (dO) 1.6 GASEOUS RELEASES - Dose Factors 1.6.1 PASTURE GRASS-COW / GOAT-MILK itiGESTION LOSE FACTORS - R cpi i (m2-mrem / year per microcuries/second) cpi =10DFLaoUapmiQfeXP(-ltm)f{---(-?-X{-------+----pXg r 1-exp(-l tep)) Biy(1-exp(-l ti b)) } E 6 F it p R i where: 106 = conversion factor, picoeurie/ microcurie. DFL ao = ingestion dose conversion factor for nuclide i, age group a, i organ o, mrem /picoeurie (Table 1.7). Uap = milk ingestion ra.te for age group a, liters / year. Fmi = transfer factor for nuclide i from animal's feed to milk, days / liter (Table 1.8). Qf = animal's consumption rate, kg/ day. 11 = decay constant for nuclide 1, seconds-1 (Table 1.8), tru = transport time from milking to receptor, seconds. f = fraction of time animal spends on pasture, dimensionless. p = fraction of activity retained on pasture grass, dimensionless. r t XE = the effective decay constant, due to radioactive decay and r weathering, seconds-1, equal to Xi + Av. Ky = veathering decay constant for leaf and piant surfaces, seconds-1 ep = time pastere is exposed to depos!. tion, seconds, t i Y = agricultural productivity by unit area of pasture grass, kg/m, p 2 i By = transfer factor for nuclide i from soil to vegetation. I i picacuries/kg (vet weight of vegetation) per picoeuries/kg (dry soil). i i tb = time period over which accumulation on the ground is evaluated, i 4 seconds. P = effective surface density of soil, kg/m, 2 NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Tkble 1.9.
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SQN ODCM Page 21 of 117 Re. vision 20 1.6.2 STORED FEED-COW / GOAT-MILK INGESTION DOSE FACTORS - RCSi 2 (m -mrem / year per microcuries/second) 6 (1-exp(-l ti esf)) RCSi = 10 DFL ao U Fmi Qf f eXp(-l ti fm) --- g Xg i np s (_I51-!XES-h{lcafll_+_ Big ((;gxp{:hilbll_} 4 Ysf E PXi where: 106 = conversion factor, picoeurie/ microcurie. DFL ao = ingestion dose conversion factor for nuclide i, age i wroup a, organ o, mrem /picoeurie (Table 1.7). Uap = milk ingestion rate for age group a, liters / year. Fmi = transfer factor for nuclide i from aninal's feed to milk, days / liter (Table 1.8). Qg = animal's consumption rate, kg/ day. fs = fraction of time animal spends on stored feed, dimensionless. 11 = decay constant for nuclide i, seconds-1 (Table 1.8). \\ tm = t.ansport time from milking to receptor, seconds. f 'est = time betvcen harvest of stored feed and consumption by animal, ceconds. = fraction of activity retained on pasture grass, dimensionless. r AE = the effective decay conntant, due to radioactive decay and weathering, seconds-1, equal to 11 + Av. ly = veathering decay constant for leaf and plant surfaces, seconds-1 test = time stored feed is exposed to deposition, seconds. Yr = agricultural productivity by unit area of stored feed, kg/m2, 3 By = transfer factor for nuclide i from soil to vegetation, i picoeuries/kg (vet weight of vegetation) per picoeuries/kg (dry soil). tb = time period over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m, 2 i l b NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.
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i SQN ODCM Page 22 of 117 Revision 20 b) 1.6.3 PASTURE GRASS-BEEF INGESTION DOSE FACTORS - Rgpi (m2-mrem / year per microcuries/second) (1-exp(-1 t1 eb)) 6 Rgp1 = 10 DFL ao Uam Fri Qt ----- --

exp(-A ts) i t

f {_Ill-'XEI-hEinall_ + Eir$1:'XXEShilbll} p Y X p E P i where: 106 conversion factor, picoeurie/ microcurie. = DFL ao ingestion dose conversion factor for nuclide 1, age group a, i = organ o, mrem /picoeurie (Table 1.7). Uam meat ingestion rate for age group a, kg/ year. a Fri transfer factor for nuclide i from cow's feed to meat, days /kg 4 = i (Table 1.8). i Qf cow's consumption rate, kg/ day. = j li decay constant for nuclide i, seconds-1 (Table 1.8). = time for receptor to consume a whole beef, seconds. teb = ta transport time from slaughter to consumer, ceconds. = fp fraction of time cow spends on pasture, dimensionless. = fraction of activity retained on pasture grass, dimensionless. r = O ) AE the effective decay constant, due to radioactive decay and = j veathering, seconds-1, equal to 11 + Av. 1 Av = veathering decay constant for leaf and plant surfaces, seconds-1 time pasture is exposed to ceposition, seconds. tep = 4 Y = agricultural productivity by unit area of pasture grass, kg/m2, p t By = transfer factor for nuclide i from soil to vegetation, i l picoeuries/kg (vet weight of vegetation) per picoeuries/kg (dry soil). tb = time over which accumulation on the ground is evaluated, seconds. P = effective surface density of roll, kg/m, l 2 i i NOTE: Factors defined above which do not reference a table for their numarical values, are listed in Table 1.9.
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l sd R n. - v r - - - - - - - - - - - - + " - - - ~ " - - ' ~ ~ * - * - " " ' " * " - " ~ " " ~ * " ~ ~ ~ ~ ' ~ ~
SQN ODCM Page 23 of 117 Revision 20 ~- O 1.6.4 STORED FEED-BEEP INGESTION DOSE FACTOKS - Rgst 2 (m -mrem / year per microcuries/second) (1-exp(-l teb)) i 6 DFLiao U Fri Qt ---- g-- Rgst = 10 exp(-l t3) am i 51:33PIbilcsf2)_{I$1".!xp{-}5 egg}}, B[y{1-ex[{;}ilb22} rt f 11tesf S P1 af E 1 where: 106 = conversion factor, picoeurie/ microcurie. a DFL ao = ingestion dose conversion factor for nuclide i, age group a, i organ o, mrem /picoeurie (Table 1.7). U = meat ingestion rate for age group a, kg/ year. am Fri = transfer factor for nuclide i from cow's faed to meet, days /kg (Table 1.8). Qg = cow's consumption rate, kg/ day. 11 = decay constant for nuclide i, seconds-1 (Table 1.8). tb = time for receptor e.c consume a whole beef, seconde.. c y t = transport time from slaughter to consumer, seconds. 3 f = fraction of time cow spends on stored feed, dimensionless. s test = time between harvest of stored feed and consumption by cow, seconds, l = fraction of activity retained on pasture grast, dimensionless, r test = time stored feed is exposed to deposition, seconds. Yst = agricultural productivity by unit area of stored feed, kg/m2, lg = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11 + Av. .1 Av = veathering decay constant for leaf and plant surfaces, seconds-1 Biy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (vet weight of vegetation) per picocuries/kg (dry soil). i tb = time over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m2 $ bG NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.
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{ -y ,c--,---.--+r ,.+-.,.r-*.-e-.--- - - - -,. y ,,--.--.,,.g - ew-g -we-,,y,
SQN ODCM Page 24 of 117 Revision 20 (. k-1.6.5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS - Rypt 2 (m -mrem / year per microcuries/second) i FLaf{--(-g-(X----+-----pX'[-----} r 1-e XtE e)) B y(1-e(-l ti b)) i 6 DFLiao e(-l ti hc) U Rypi = 10 L t where: 106 = conversion factor, picoeurie/ microcurie. DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /picoeurie (Table 1.7). 1 At = decay constant for nuclide i, seconds-1 (Table 1.8). the = average time between harvest of vegetables and their consumption and/or storage, seconds. Upta = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/ year. ft = fraction of fresh leafy vegetables grown locally, dimensionless. = fraction of deposited activity retained on vegetables, r dimensionless. AE = the effective decay constant, due to radioactive decay and weathering, seconds-1 =Xi + Av l = decay constant for removal of activity on leaf and plant surfaces y by weathering, seconds-1 i t, = exposure time in garden for fresh leafy and/or stored vegetables, seconds. Yg = vegetation areal density for fresh leafy vegetables, kg/m2, I By = transfer factor for nuclide i from soil to vegetables, i picoeuries/kg (vet weight of vegetatien) per picoeuries/kg (dry soil), tb = time period over which accumulation on the ground is evaluated,
seconds,
'i P = effe:tive surface density of soil, kg/m2, i l NOTE: Factors defined above which do not reference a table for their l numerical values, are listed in Table 1.9.
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SQN ODCM Page 25 of 117 Revision 20 4 1.6.6 STORED VEGETABLE INGESTION DOSE TACTORS - Rysi m2-mrem / year per microcttr!.es/second) i 0 (1-e(-l ti sv)) Rysi = 10 DFL ao exp(-l the) U afg -- X-g ----- i i S {.E51'$235'tll& iY$125-hilb22} B 8 e sv IE PXi vhere: 106 = conversion factor, picoeurie/ microcurie. DFL ao = ingestion dose conversion factor for nuclide 1, age group a, i organ o, mrem /picoeurie (Table 1.7). 11 = decay constant for nuclide i, seconds-1 (Table 1.8). the = average time between harvest of vegetables and their con *:umption and/or t'torage, seconds. usa = consumption rate of stored vegetables by the receptor in age group i a, kg/ year. l f = fraction of stored vegetables grown locally, dimensionless. g time between atorage of vegetables and their consu=ption, seconds. ty = s fraction of deposited activity retained on vegecables, r = dimensionless. AE = the effective dect.) constant, due to radioactive decay and weathering, seconds-1 =X1+% 4 ly = decay constant for removal of activity on leaf and plant surfaces by veathering, seconds-1 = exposure time in garden for fresh leafy and/or stored vegetables, t e seconds. Yy = vegetation areal density for stored vegetables, kg/m2, 3 By = transfer factor for nuclide i from soil to vegetables, i picoeuries/kg (vet weight of vegetation) per picoeuries/kg (dry i soil). j tb ^ time period over which accumulation on the ground is ? valuated, j seconds. 2 P = effective surface density of soil, kg/m, V j NOTE: Factors defined above whir;h do not reference a table for their i numerical values, are listed in Table 1.9. 't
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t SQN ODCM ' Page 26 of 117 Revision 20 O .6.7 TRITIUM-PASTURE GRASS-COW / GOAT-MILE DOSE FACTOR - R 1 CTP (mrem / year per microcuries/m3) r 1 RCTP = 103 106 DFLTao ImT Qf Uap [0.75(0.5/H)] fp exp(-A tT fm) where: 103 = conversion factor, grams /kg. [ i l i 106 = conversion factor, picoeuries/microcuries. DFL ao .= ingestion dose conversion factor for tritium'for age group a, T organ o, mrem /picoeurie (Table 1.7). FmT = transfer factor for tritium from animal's feed to milk, days / liter 1 (Table 1.8). Qg = animal's consumption rste, kg/ day, d U = milk ingestion rate for age group a, liters / year. ap l 0.75 = the fraction of total feed that is water. i 0.5 = the ratio of the specific activity of the feed drass water to the j atmospheric water. H = absolute humidity of the atmosphere, s/m3 [ f = fraction of time animal spends on pasture, dimensionless. p XT = decay constant for tritium, seconda-1 (Table 1.8). t tfm = transport time from milking to receptor, seconds. I 1 .j NOTE: Factors defined above which do not reference a table for their [ numerical values, are listed in Table 1.9. I i il ] 1 i 1 l
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l j SQN ODCM Page 27 of 117 Revision 20 O 1.6.8 TRITIUM-STORED TEED-COW / GOAT-MILK DOSE FACTOR - R CTS. (mrem / year per microcuries/m3) 6 (1-exp(-X tesf)) RCTS = 103 T 10. DF1' Tao FmT Qf Uap (0.75(0.5/II)] fs --- g tg-----exp(-AtT fm) i wheret i 103 = conversion factor, grams /kg. 106 .= conversion factor, picoeuries/iaicrocuries. DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem / picocurie (Table 1.7). FmT = transfer factor for tritium from animal's feed to milk, days / liter (Table 1.8). [ a j Qg = animal's consumption rate, kg/ day. i i Uap = milk ing'estion rate for age group a, liters / year. l 0.75 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute hu.midity of the atmosphere, g/m3 1 J t = fraction of time animal spends on stored feed, dimensionicas. s t 17 = decay constant for tritium, seconds-1 (Table 1.8). t ] t e.s f = time between harvest of stored feed and cor.sumption by animal, seconds. i tgm = transport time frers milking to receptor, seconds. i NOTE: Factors defined above which do not reference a table for their i } numerical values, are listed in Table 1.9. i l { l ) i l ~ Q k l l l
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SQN ODCM Page 28 of 117 Relision 20 p (V) 1.6.9 TRITIUM-PASTURE GRAf dEu? 20SE FACTOR - RMT (mrem / year per micre ries /m3) 3 106 RMTP = 10 DFL ao PfT Qf Uam (0.75(0.5/11)] fp exp(-1 ta) T 7 _Il:25PS:hIlep22__$1:fXEI:hTIcb)2_ ET Cep ET teb where: 103 = conversion factor, grams /kg. 106 = conversion factor, picoeuries/microcuries. DFL73o = ingestion dose conversion factor for trisium for age group a, organ o, mrem /picoeurie (Table 1.7). Ff7 = transfer factor for tritium from cow's feed to meat, days /kg (Table 1.8). Qf = cow's consumption rate, kg/ day. O Uam = meat ingestion rate for age group a, kg/ year. U 0.75 = the fraction of total feed that is water. C.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. 11 = absolute hu.sidity of the atmosphere, g/m3 !p = fraction of time cov spends on pasture, dimensionless. AT = decay constant for tritiu=, seconds-1 (Table 1.8). l t = transport time from slaughter to consumer, secepds. 3 I tep = time pasture is exposed to deposition, secc.1da. teb = time for receptor to consume a whole beef, seconds. NOTE: Factort. defined above which do not reference a table for their numerical values, are listed in Table 1.9. bi v
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SQN ODCM Page 29 of 117 Revision 20 ,,[ \\ \\'/ 1.6.10 TRITIUM-STORED FEED-8EEP DOSE FACTOR - RMTS 3 (mrem / year per microcuries/m ) 3 106 ppL RMTS = 10 Tao FfT Qf Uam (0.75(0.5/11)] f exp(-A tT 3) a _IIIexp{;373ep}}_,{l:Eexp{;h73c3}}, ET t T tcb ep where: 103 = conversion factor, grams /kg-106 = conversion factor, picoeuries/microcuries. DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /picoeurie (Table 1.7). PfT = transfer factor for tritium from cov's feed to meat, days /kg (Table 1.8). Qf = cow's consumption rate, kg/ day. U = meat ingestion rate for age group a, kg/ year. am 0.75 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass Vater to the atmospheric water. H = absol,ute humidity of the atmosphere, g/m3 f = fraction of time cov spends on stored feed, dimensionless. 3 AT = decay constant for tritium, seconds-1 (Table 1.3). t = transport time from slaughter to consumer, seconds. s t = time pasture is exposed to deposition, secenas, cp teb = time for receptor to consume a whole beef, seconds. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9. O
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SQN ODCM. Page 30 of 117 Revision 20 1.6.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR - RVTF (mrem / year per microcuries/m3) 3 106 ppLTao (0.75(0.5/H)] UFLa fL exp(-A the) RVTF = 10 t where: 103 = conversion factor, grams /kg. 106 = conversion factor, picoeuries/microcuries. DFL ao = ingestion dose conversion factor for tritium for age group a, T organ o, mrem /picoeurie (Table 1.7). 0.75 = the fraction of total vegetation that is water. 0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water. H = absolute humidity of the atmosphere, g/m3 UFLa = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/ year. ft = fraction of fresh leafy vegetables grown locally, dimensionless. X7 = decay constant for tritium, seconds-1 (Table 1.8). the = time between harvest of vegetables and their consumption and/or storage, seconds. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.
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I SQN ODCM Page 31 of-117 Rovision 20 /'~ 4 1.6.12 TRITIUM-STORED VEGETABLES DOSE FACTOR - RVTS (mrem / year per microcuries/m3) i it (1-exp(-X tsv)) I T 3 106 DFITao (0.75(0.5/H)) U RVTS = 10 f Sag----X-i;y------- exp(-X tT he) t vhere: 103 = conversion factor, grams /kg. 106 .= conversion factor, picoeuries/microcuries. i DFLTao = ingestion dose conversion factor for tritium for age group a, { organ o, mrem /picoeurie (Table 1.7). 0.75 = the fraction of total vegetation that is water, i 0.5 = the ratio of the specific activity of the vegetation water to the [ atmospheric water. li = absolute humidity of the atmosphere, g/m3 t usa = consumption rate of stored vegetables by the receptor in age l group a, kg/ year. ii f = fraction of stored vegetables grown locally, dimensionless. 8 XT " decay constant for tritium, seconds-1 (Table 1.8). t = time between harvest of stored vegetables and their consumption [ sy and/or storage, seconds, i l j the = time between harvest of vegetables and their storage, seconds. 4 I i Il0TE: Factors defined above which do not reference a table for their l numerical values, are listed in Table 1.9. l I l 1 i 1 i i l i j
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_ _ ~ I 1 SQN ODCM Page 32 of 117 Revision 20 1.6.13 IN11ALATION DOSE FACTORS-RIt (mrem / year per microcuries/m3) RIt = DFA ao bra 106 l P i j wheret i DFAiao = inhalation dose conversion factor for nuclide i, age group a and organ o, mrem /picoeurie (Table 1.10). i BR = breathing rate for age group a, m3/ year (Table 1.9). a 106 = conversion factor, picoeurie/ microcurie. I. 1.6.14 GROUND PLANE DOSE FACTORS - Rgt 2 j (m -mre4/ year per microcuries/second) 1 I I ] Rat = DFGio 1/Ai 106 8760 (1 - exp(-A tt b}} l l t where: DFgio = dose conversion factor for standing on contaminated ground for ^ nuclide i and organ o (total body and skin), mrem /hr per picoeurie/m2 (Table 1.11). i i 11 = decay constant of nuclide 1, seconds-1 (Table 1.8). 106 = conversion factor, picoeurie/ microcurie. ) 8760 = conve.'sion factor, hours / year. l l tb = time period over which the ground accumulation is evaluated, seconds (Table 1.9), i i 4 Il j s l
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SQN ODCM Page 33 of 117 - Revicion 20 m (As) 1.7 Dispersion Methodolor.v Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m. A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 1.3), and building vake effects. Terrain effects on distersion are not considered. !!ourly average meteorological data are exycessed as a joint-frequency distribution of vind speed, vind direction, and atmonpheric stability. The joint-frequency distribution which represents the historical meteorological data for the period January 1972 to December 1975 is given in Table 1.3. The vind speed classes that are used are as follows: limben Range _,Irdsj tiLd MndDl_sl D 1 <0.3 0.13 2 0.3-0.6 0.45 3 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6-8.2 6.91 8 8.3-10.9 9.59 9 >10.9 10.95 The stability classes that vill be used are the standard A through G classifications. The stability classes 1-7 vill correspond to A=1, B=2,.... G=7. 3 1.7.1 Air Conctntrallon - x (pC1/m ) Air concentrations of nuclides at dovnvind locations are calculated using the following equation: '\\ 9 7 j Xi = I I (2/v)1/2 fjk Qi P exp(-Ag x/uj) (1.16) j=1 k=1 Izk uj (2trx/n)
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1 SQN ODCM Page 34 of 117 Revision 20 I e - where l f*ik = Joint relative frequency of occurrence of winds in windspeed [ class j, stability class k, blowing toward this exposure point, i erpressed as a fraction. I + Qi = average annual release rate ^of radionuclide 1, pCi/s. [ ] p = fraction of radionuclide remaining in plume (Figure 1.3). i a i 4 Izk = vertical dispersion coefficient for stability class k which l . includes a building wake adjustment, { =(o{k+cA/s)1/2, J j or = /3 o k, whichever is smaller. z ? vhere j t j ok is the vertical dispersion coefficient for stability l z class k (m) (Figure 1.4), 4 e is a building shape factor (c=0.5), l 4 A is the minimum building cross-sectional area (1800 m2), l uj = midpoint value of wind speed class interval j, m/s. x = downwind distance, m. t i i n = number of sectors, 16. 1 l f Ai = radioactive decay coefficient of radionuclide 1, s-1 i i 2rx/n = sector width at point of interest, m. g j 1.7.2 fle1411n_1onentratign_ __yj_Q (sec/m3) 4 Relative concentrations of nuclides at downwind locations are calculated j using the following equations j i i j 9 7 j 1 k=1 (2/r)1/8 (1.17) [ =I I X/Q ] Izk uj (2rx/n) i i where l l fjk = Joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction. l 1 l 2 1 i l
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a..... a .---------n -,,n----,,... _.,,, n,,,- ,,,,,,,,.--,------.-r--_,.,,
SQN ODCM Page 35 of 117 Revision 20 Izk vertical dispersion coefficient for stability class k which = includes a building vake adjustment, (olk+cA/w)1/2, = /3 o k, whichever is smaller.- or = z where ok is the vertical dispersion coefficient for stability z class k (m) (Figure 1.4), e is a building shape factor (c=0.5), A is the minimum building cross-sectional area (1800 m2), midpoint value of wind speed class interval J, m/s. uj e downvind distance, m. x = number of sectors, 16. n = 2rx/n sector vidth at point of interest, m. = 1.7.3 Felative DeDosition - D/0 (m-2) Relative deposition of nuclides at downwind locations is calculated using the following equation: 9 fjk DR D/Q=Ij=1 k=I (1,18) 1 (2rx/n) where (k = joint relative frequency of occurrence of winds in vindspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction. DR = relative deposition rate, m-1 (from Figure 1.5). x = downvind distance, m. n = number of sectors,16. 2rx/n sector vidth at point of interest, m. a
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SQH ODCM Page 56 of 117 Revision 20 /mU .0 Liq _uid Ef fluenta 2 2.1 Gsncentration 1.1.1 RETS Reautrenent Specification 3.11.1.1 of the Radiological Effluent Technical Specificaticns (RETS' requires that the concentration of radioactive material released at any time from site to unrestricted areas shall be limited to the Maximum Permissible Concentratta.. (MPC) specified in 10 CFR 20, Appendix B, Table II, Column 2 for nuclides ^ther tb dissolved or entrained noble gases. For dissolved or entrained noble gr.ses, the concentration shall be limiteo to 2x10-4 pCi/mL total activity. To ene"*e l comp) lance, the following approach will be used for each release. 2.1.2 Prereleaut_Analnin Most tanks vill be recirculated through two volume changes prior to sampling that a representative sample is obtained. Because of their size, the high c, <s, non-reclaimable vaste tank, and cask decontamination tank vill not necessarily ce recirculated through two volumes. An appropriate recirculation time for these tanks will be determined by a one tima test. The tank vill be scirculated and periodically sampled for suspended particulates during the test. The appropriate recirculation time vill be the time that the suspended particulate concentration reaches steady state. The condensate demineralizer vaste evaporator blovdown tank \\ cannot be recirculated. However the contents of the tank will be under administrative control and could be transferred to the distillate tanks prior to release. Prior to release a grab sample vill be analyzed for each release point for the concentration of each radionuclide. n Ci=1Ci (2.1) i=1 where Gj = Total concentration in the liquid effluent at release point j, pC1/mL. Ci = concentration of radionue11de 1, pCi/mL. l l 4 1 i v allumbering change only 1157c
SQN ODCM Page 37 of 117 ~" Revision 20 3 \\ 2.1.3 MPC-Sum of the Ra11.ga There are two possibic release points into the river, the turbine building sump and the cooling tower blovdown. The cooling tower blowdown is further subdivided into four separate liquid release paths as shown below. Radvaste f1 Condensate Demineralizer fa

9 Steam Generator Blowdown fa

> Cooling Tower Blovdown F Steam Generator Blowdovn f4 / v The sum of the ratior (R ) for each release point vill be calculated by J the following relationship. Ci RJ={ (2.2) MPCi g where: Rj = the sum of the ratios for release point J. ) Ci = effluent concentration of radionuclide 1, pCi/mL. For the ( turbine build.ing sump, this will be the diluted concentration determined by daily grab sampling. For releases into the cooling tower blovdown, this will be the undiluted concentration in the tank as determined in Section 2.1.2. MPCi = the MPC of radionuelide i, as specified in Section 2.1.1, pCi/mL. i For releases into the cooling tower blevdovn, the sum of 'he MPC ratios must be 1 i due to the releases from any or all of the fwu release paths shown above. The following relationship will assure this .iterion is i mets l f1R1 + f2Ra + f3R3 + f4R4 1 3,3) P where: ft,fa,fs,f4 = the effluent flow rate at the respectiie release point as determined by plant personnel, gallons / minute. R1,Ra,Ra,R4 = the sum of the ration of the respective release points as determined by Equation 2.2. J ps ( ) T = mininum dilution flow rate for prerelease analysis (cooling j U tower blevdovn) = 15,000 gallons per minute.
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I 7 SQ!i ODCM l Page 38 of 117 " Revision 20 l i t 1 2.2 Instrument Setooints i 2.2.1 Setroint Determing iqn I The setpoint for each liquid effluent c'onitor vill be established using I 3 plant instructions. Concentration, flow rate, dilution, principal gamma ) emitter, geometry, and detector efficiency are combined to give an j equivalent setpoint in counts per minute (cpm). The physical and technical description location and identification number for each liquid [ effluent radiation detector is contained in plant documentation. l The respective alare/ trip setpoints kt each release point will be set f such that the sum of the ratios (Rj) for all points, as calculated by ( Equation ~2.3, vill not exceed 1. The RJ is directly related to the i total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the respective Rj. A large increase vould cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm / trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint(s) be set above the effluent concentration (Cj). That is, i i I l j Sj = bj (Cj + B) (2.4) 4 I vhere ,i l Sj = desired alarm / trip setpoint at release point J. j 4 q bj = scaling factor to prevent alarms / trips due to variations in the effluent concentrations at release point J. I Cj = monitor response based on the total concentration in the I liquid effluent at release point j specified by Equation 2.1, l { pCi/e1. I i i j B = monitor background prior to release. f 1 1 2.2.2 Mai_Rfh11e__ Ana1Ysh i 3 i d A post-release analysis will be done using actual release data to ensure j } that the limits specified in Section 2.1.1 vere not exceeded. i 1 1 j A composite list of concentrations (C ), by isotope, will be used with t the actual liquid radvaste (f) and dilution (F) flow rates (or volumes) t during the release. The data vill be substituted into Equation 2.3 to j demonstrate compliance with the limits in Section 4.1.1. This data and i j setpoints will be recorded in auditable records by plant peraonnel. l i 1 I i S
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A SQN ODCM L Page 39 of 117 i' - " Rr /ision 20 L 2.3 Daat i } 2.3.1 RETS Recuirementa ? Specification 3.11.1.2 of the Radiological Effluent Technical i Specification (RETS) requires that the dose or dose commitment to an f j individual from radioactive materials in liquid effluents released to j 1 unrestricted areas from each reactor shall be limited: l i l 1. Dt. ring any calendar quarter to 1 1.5 mrem to the total body and i to i 5 mrem to any organ, and 2. During any calendar year to 1 3 mrem to the total body and to ) 1 10 mrem to any organ. i i To ensure compliance, cumulative dose calculations will be performed at j least once per month according to the following methodology. l E i 2.3.2 Monthly Antivsig i [ 1 Principal radionuclides vill be used to conservatively estimate the I monthly contribution to the cumulative done. If the projected dose 4 i exceeds the above limits, the methodology in Section 2.3.3 vill be } implemented. I j The 20 nuclides (listed belov) contribute more than 95 percent of the [ j dose to the total tody and the most critical organs for each pathvay. ( The critical organs considered for water and fish ingestion are the t gastrointestinal tract (GIT), bone, thyroid and liver, j f i i H-3 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 2n-65 Sr-89 I Sr-90 Zr/Nb-95 Mo/Tc-99m Ag-110m Sb-124 I-131 1-133 Cs-134 Cs-136 Cs-137 i } i / 3 { A conservative calculation of the monthly dose vill be done according to l j the following procedure. First, the monthly release data vill be { obtained and the activities released of each of the above 20 i 4 radionue11 des, if identified, will be noted. This information vill then be used in the following calculations. ) 3 i l 5 I 8 } )
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C: j l { SQN ODCM i l Page 40 of 117 i j " Revision 20 I i 2.3.2.1 Water Intestion l 4 l The dose to an individual from ingesti)n of water is descrxhed by the j i following equation. i 1 20 y i Djk = } DCF jk lik (2.5) 1 i 0.95 g,g l i where: Djk = dose for the jth organ from 20 radionuclides, rem. J j = the organ of interest (bone, GI tract, liver, thyroid and j total body). l 1 1 k = the age group being considered, adult or child. l ) j 0.95 = conservative correction factor, considering only 20 ( ) radionuclides. i } DCF jk = critical ingestion dose commitment factor for the ith l i j radionuelide for the jth organ for the kth age group, { j res/pci, (Table 2.1). i i I ik = monthly activity ingested of the ith radionuclide by the j kth age group, pC1. I j is described by i 1 Ai Yk (30) I ik " (2 0) 1 F d (7.34x10 0) 1 i vheres i I A t = activity released of the ith radionuclide during the month, pCi. i l I, l Yk = maximum individual's water consumption rate corresponding to the kth age group selected for the critical DCri k above l (Adult: 2000 mL/d, Child: 1400 mL/d Regulatory uide 1.109). i I 30 = days per month. I i l r = average river flow at Chickamauga Das for the month (cubic l feet per second). [ j d = fraction of river flow available for dilution (1/$). 1 7.34x10 0 = converts cubic feet per second to milliliters per month.
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SQN ODCM Page 41 of 117 Revision 20 Considering the conversion factor from rem to mre:r, the c'ese equation then becomest 20 2*15x10-6 Djk
2Yk DCF jk Ai (2.7) i I
i=1 2.3.2.2 Elph_innestion The dose to an indiaidual from the consumption of fish is described by Equation 2.11. In this case the activity ingested of the ith radionuclide (Iik is described by \\ At Bi Mk (2.8) F d (7.34x1010) where Ai = activity releasca of ith radionuelide during the month, pC1. I Bi = effective fish concentration fuctor for the ich radionuclide pCi/g per pCi/e1 (Table 2.2). Mk = amount of fish eaten conthly by maximum individual i correrponding to the kth age group selected for the i critical DCF jk above (Adult 1750g, Childt 575gt i Regulatory Culde 1.109). F = average river flow at Chickama'Jga Dam for month (cubie. feet i per second). l d f1 action of river flov available for dilutica (1/5). = 1 l 7.34x10 0 = converts from cubic feet per second tc, milliliters per month. I Considering the conversion factor from rem to crem, thee dose equation then becomes l 20 1 7*17x10-8 Djk
IAi Bi Mk DC,F jk (2.9) i I
i=1
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SQN ODCM i Page 42 of 117 i Revision 20 l -e Recreati4D The total body dose to an individual via the shoreline recreation pathway is described by the following equation. For this calculation, the total dose is estimated based on a calculation for Co-58, Co-60, Cs-134, and l Cs-137. These four nbc11 des are expected to contribute over 95 percer t j of the recreation dose, 1 4 0.1 RCDri (i 67 I D= I (2.10) 0.95 8760 L g,y j i where l 1 D = shoreline recreation dose to the total body from plant teleases, mrem. 4 i 1 I 0.95 = consenative correction factor, considering only 4 radionuelides. ~ 1 RDCF,' = shoreline recreation dose commitment facto't for the ith t radionuclide, mrem /yr per pCi/cma (Table 2.3). (Notet For Cs-137, the dose commitment factor for its daughter, Ba-137m, is assumed.) 67 = assumed monthly exposure time for maximum individual, h. { = 500 h/ year x 0.4 (fractional exposure for vorst quarter) l + 3 (months / quarter). f i 8760 = conversion from year to hours. t f 5 0.1 = conversion factor combining conversions for mP/cma i and mL/L. t ? f (i = concentration of ith radionuclide in shoreline sediment f i a (pci/cm ), as dr. scribed by the following equation ] (based on equation A-5 in Regulatory Guide 1.109). I = 100 RHLg Cg W (1-er.p (-Ag t)) (2.11) l 4 v i wheret 100 = transfer constanc defined in Regulatory Guide 1.109, I a L per m -day. I t RHLt = radiological half-life of the ith radioisotope, days, j from Table 2.1. 1 I W = shoreline width factor (0.3 for a lako shore, per Table l A-2 of Regulatory Guide 1.109). l' k j
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SQN ODCM Page 43 of 117 Revision 20 OV) i lt = decay constant of the ith radionuclide = 0.693/RHL.t t = buildup time in sediment, assumed 15 years, per Regulatory Guide 1.109. Ci = concentration of ith radionuclide in the Tennessee River, pC1/mL. = A /(T d 7.34x1010) i where A1 = activity released of ith radionuclide during the month, pC1. T = average river flow at Chickamauga Das for the month, cubic feet per second. d = fraction of river flow availabic for dilution (1/5). 1 7.34x10 0 = cubic feet per second to milliliters per month. The dose equation then becomes tV D=F (.00692 A1 + 0.00012 A2 + 0.00206 A3 + 0.00342 A ) (2.12) 4 where A1, A2, A3, A4 = the activtties of Co-60, Co-58, Cs-134 and Cs-137 respectively. 2.3.2.4 tignthly Su. mary i Calendar quarter doses are first estimated by suming the doses calculated for each month in that quarter. Calendar year doses are first estimated by summing the deses calculated for each month in that year. However, if the annual doses determined in this manner exceed or approach the specification limits, doses eaclulated for previous quarters with the methodology of section 2.3.3 vill be used instead of those quarterly doses estimated by suming etenthly results. An annual check vill be made to ensure that the monthly dose estimates account for at least 95 percent of the dose calculated by the method described in Section 2.3.3. If less than 95 percent of the dose has been estimated, either a new list of i principal isotopes will be prepared or a new correction factor will be used. The latter option vill not be used if less than 90 percent of the total dose is predicted. i N
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SQN ODCM Page 44 of 117 Revision 20 e h 2.3.2.5 ILqse Projections In accordance with specification 3.11.1.3, dose projections vill be performed. This will be dotte by averaf,ing the calculated dose for the most recent month and the calculated dove for the previous month and assigning that average dose as the projection for ti.e current month. 2.3.3 Ouarterly and Annual _AItalysit A complete analysis utilir.ing the total estimated liquid releases for each calendar quarter vill be performed and reported as required in section 6.9 of the technical specifications. This analysis will replace values calculated using section 2.3.2 methodology and vill also include an approxination of population doaes. 2.3.3.1 IndiXL<lual Doses The dose, Djp, to the maximum individual from n nuclides is described by: 5 n Djk = 1 I Djd (2.13) i m=1 i=1 \\] n 2 5 Dj k = [ ] [DCrijk likn] + 1 (RDCrijs (im T 9] (2.14) m i=1 m=1 m=3 where: D jkm = dost.o the jth organ for the kth age group from i the ith radionuclide via the mth exposure path. J the organ of interest (bene, GI tract, thyroid, liver, = total body and skin). k the age group being eensidered adult and child for = the ingestion pathways; adult for the recreation pathways. m = exposure pathway of interest:
1. water ingestion,

2. fish ingestion,

3. shoreline recreation,

4. above water recreation, and

5. in-water recreation.
O
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SQti ODCM Page 45 of 137 Revision 20 1 w OV) (DCF)ijk = ingestion dose commitment factor for the jth organ from the ith radionuclide for the kth age group, rem /pci (Table 2.1). (RDCF)tjm = recreation dose commitment factor for the jth organ from the ith radionuclide via the mth pathway; a mrem /yr per pCi/cm, (Table 2.3). Tm = assumed exposure time of maximum individual for the mth pathway (3) shoreline 500 h/yr ( 10 h/veek) (4) above-water 1800 h/yr (6 h/d, 300 d/yr) (5) in-water 920 h/yr (6 h/d, for five summer months). Fraction of annual recreation exposure for each quarter 9 = 1st Quarter January-March 0.1 2nd Quarter April-June 0.3 3rd Qutrter July-September 0.4 4th Quarter October-December 0.2. I ya = The activity ingested of the ith radionuclide, via the i m h exposure pathway for the kch age group, pC1. t =Ci Vk N for the water ingestion pathway (2.14) =Ci Bi Mk for the fish ingestion pathway (2.15) whete Vk = vater ronsumption for the kth age group, per Regulatory Guide 1.109 for maximum individuals adult - 2000 mL/d child - 1400 mL/d l 1 for average individual (population): adult - 1010 mL/d child - 710 mL/d. a 4 N = nu:nber of days during the release period, day. 2 Bt = bioaccumMation faci:or for the ith radionuclide in fish, pCi/g per yC1/mL (Table 2.2). \\ Mk = amount of fish consumed during the period for the tk h age group (fraction of year t.imes the annual consumption rate per Regulatory Guide 1.109) for maximum individual: 4 adult - 21 kg/yr { child - 6.9 kg/yr for sverage individual (population): adult - 6.9 kg/yr child - 2.2 kg/yr. l
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SQN ODCM page 46 of 117 Revision 20 .~ V Cg = concentration of the ith radionuclide during the release period, pCi/mL = Ag/(Fgd). where: Ag = Activity raleased of ith radionuclide during the release period, pC1. Fg = Total river flov at location i during period, mL. t = Location of interest (For dose to the maximn:n individual the first down-river exposure point is used. For the population dose, various down-river locations arr used to account for tne total exposi population. Table 2.4 gives the river location of public vater supplies; Tables 2.5 and 2.6 givi the boundaries of the various reaches in which concentrations are calculated for the fish and recreation pathwa/s). O d = fraction of river flow available for dilution (0.20 above Chickamauga Dam, 1 below the dam). (te = the corcentration of the ith radionuelide in the environmental medium pertaining to mth pathway. = (15 = Cg, for above-water and in-vater recreation pathways; = 100 RELt Ci W [1-exp(-Xg t)], for the shoreline recreation pathway; where 100 = transfer constant as defined in Regulatory Guide 1.109 equation A-4, L per m2-day. RHLg = radiological half-life of the ith isotope, days. (* tble 2.1). Cg = concentration of the ith nuclido in water, pCi/mL. W = rhoreline width factor (0.3 for a lake shore, per Table A-2 of Regulatory Cuide 1.109). i
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1 SQN ODCM Page 46 of 117 Revision 20 w Ct = concentratim of the ith radionuclide during the release period, pC1/mL = A /(Fgd). t Where Ag = Activity releaned of ith radionuclide during the release period, pCi. Fg = Total river flow at location i during period, mL. 4 = Location of interest (For dose to the maximum individual the first down-river exposure point is used. For the population dose, various down-river locations are used to account for the 0 total exposed population. Table 2.4 gives the river locktion of public water l d cupplies; Tables 2.5 and 2.6 give the f boundaries of the various reaches in l vhich concentrations are calculated '.or the fish and recreation pathways). 4 / d = fraction of river flow available for dilution (0.20 above Chickamauga Dam, 1 below the dam). i (im = the concentration of the ith radionuelide in the envirormental medium pertaining to ath pathway. = (15 = Cg, for above-water and in-water I recreation pathways; = 100 RELg Ci W [1-exp(-it t)), for the j shoreline recreation pathvay: 1 where: i j 100 = transfer constant as defined in Regulatory Guide 1.109 j equation A-4, L per m8 day. 1 j RHLg = radiological half-life of the ith isotope, days, (Table 2.1). t Ct = concentration of the ith nuclide in water, pCi/mL. W = shoreline width factor (0.3 for a lake shore, per } Table A-2 of Regulatory Guide 1.109). I j i i = 4 l I
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.. - -... - -. ~. ~. - -. - ~_. SQN ODCM Page 48 of 117 i Revision 20 ) i l 2.4 Qnerability of Liould Radvaste Equitm.cn1 j Specification 3.11.1.3 of the Radiological Effluent Technical Specification requires that the liquid radwaste system shall be used to reduce the radioactiate materials in liquid wastes prior to their i discharge when the projected dose due to liquid affluent releases to I unrestricted areas when averaged over 31 days would exceed 0.06 mrem i to the total body of 0.21 mrem to any organ. Doses will be projected monthly to assure compliance. 1 i i i i i i i r e [ I i i i i ? e 4 1 i i l 1 L l 5 l l } t e i i t i 1 ) I i l t i 1 l I r l l i I
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~~. -. SQN.0DCM Tage 49 of 117 - Revision 20 i { \\ 3.0 Radiologig i Environmental MonitortDA i 3.1 lionitorint Pr_Q&tMi i An environmental radiological monitorins program shall be conducted in accordance with Technical Specification 3.12.1. The monitoring program described in Tables 3.1, 3.2, and 3.3, and in Figures 3.1, { j 3.2 and 3.3 shall be conducted. Results of this program shall be i reported in accordance with Technical Specifications 6.9.1.6 and i j 6.9.1.7. i i The atmospheric environmental radiological monitoring program shall l l consist of monitoring stations from which samples of air l particulates and atmospheric radioiodine shall be collected. i The terrestrial monitoring proeram shall consist of the collection i of vegetation, milk, soil, ground water, drinking water, and food i j crops. In addition, direct gamma rad!ation levels will be measured in the vicinity of the giant. 1 The reservoir saepling program rnall corsist of the collection of l samples of surface water, sediment, clams, and fish. Deviations are permitted from the required sampling schedule if i 3 j specimens are unobtainable due to hazardous conditions, sample l unavailability, or to malfunction of sampling equipment. If the 7 latter, every effort shall be made to complete corrective action prior to the end of the nexc sampling period. l l L 3.2 Detection capabilities l Analytical techniques shall be such that the detection capabilities i j listed in Table 3.4 are achieved. i e { 3.3 Initrbipratory Comnarison Pre &IMI l Analyses shall be performed on radioactive caterials supplied as 1 part of an Interlaboratory Comparison Program which has been f approved by the NRC. A sur. mary of the results obtained in the j intercomparison shall be included in the Annual Radiological j Environmental Operating Report (or the EPA program code designation j may be provided). t } i If analyses are not performed as required corrective actions taken l to prevent a recurrence shall be reported in the Annual Radiological j Environmental Operating Report. j i
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SQN ODCM Page 50 of 117 - Revision 20 3.4 Land Use CeDAM2 A land use survey shall be conducted in accordance with SQN Technical Specification 3/4.12.2. The resulto of the survey chall be reported in the Annual Radiological Environmental Operating Report. 5 1 t I I J 1 .j j '4 ) i i 1 1 1 1 j i i I I i 1 l i 1 A i .l I
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SQN ODCM Page 51 of 117 Revision 20 O t 1 'N J 4.0 ADRVal Maximum IndividuaLILqpes - Total To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from SQN radioactive effluents and all othur nearby uranium fuel cycle sources will be censidered. The annual dose to tho maximum individual vill be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarierly total body dose from liquid effluente. the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sum for each quarter and summing over the four quarters. P J i i l 1 l l + s s l "Numbering change only 1157e i l a.... j al
SQN ODCM Page 52 of 117 Revision 20 O Table 1.1 s_- SQN - OPPSITE RECEPTOR LOCATION DATA fp fP fP X/ D/Q (cow (goat (beef) DIST (s/mg) (1/m2) milk) milk) POINT SECTOR (m) Land Site Boundary N 950 5.12E-06 1.29E-08 1.00 1.00 1.00 Land Site Boundary NNE 2260 1.93E-06 5.28E-09 1.00 1.00 1.00 Land Site Boundary NE 1910 2.32E-06 5.33E 1.00 1.00 1.00 Land Site Boundary ENE 1680 1.12E-06 2.64E-09 1.00 1.00 1.00 Land Site Boundary E 1570 7.10E-07 1.46E-09 1.00 1.00 1.00 Land Site Boundary ESE 1460 7.91E-07 1.58E-09 1.00 1.00 1.00 Land Site Boundary SE 1460 9.14E-07 2.41E-09 1.00 1.00 1.00 5 Land Site Eoundary SSE 1550 1.34E-06 3.23E-09 1.00 1.00 1.00 Land Site Boundary S 1570 2.37E-06 4.18E-09 1.00 1.00 1.00 Land Site Boundary SSW 1840 4.51E-06 9.26E-09 1.00 1.00 1.00 Land Site Boundary SW 2470 1.38E-06 2.63E-09 1.00 1.00 1.^J Land Site Boundary WSW 910 2.93E-06 3.86E-09 1.00 1.00 J.00 Land Site Boundary W 670 3.63E-06 3.74E-09 1.00 1.00 1.00 Land Site Boundary WNW 660 2.49E-06 2.44E-09 1.00 1.00 1.00 Land Site Boundary NW 660 2.85E-06 3.67E-09 1.00 1.00 1.00 Land Site Boundary NNW 730 3.95E-06 6.59E-09 1.00 1.00 1.00 Resident H 1370 2.98E-06 7.10E-09 1.00 1.00 1.00 Resident IGG 2710 1.49E-06 3.88E-09 1.00 1.00 1.00 (N P3sident, Garden NE 2140 1.98E-06 5.21E-09 1.00 1.00 1.0C ( ) Resident ENE 2290 7.13E-07 1.57E-09 1.00 1.00 1.00 Resident E 1790 5.85E-07 1.18E-09 1.00 1.00 1.00 Resident ESE 1790 5.86E-07 1.14E-09 1.00 1.00 1.00 Resident SE 1680 7.42E-07 1.92E-09 1.00 1.00 1.00 Resident, Garden SSE 2210 7.99E-07 1.79E-09 1.00 1.00 1.00 Resident S 2020 1.65E-06 2.75E-09 1.00 1.00 1.00 i Resident, Garden SSW 2290 3.31E-06 6.38E-09 1.00 1.00 1.00 i Resident SW 3010 1.04E-06 1.88E-09 1.00 1.00 1.00 Resident WSW 1140 2.09E-06 2.67E-09 1.00 1.00 1.00 Resident W 1750 8.53E-07 7.82E-10 1.00 1.00 1.00 Resident, Garden WNW 1750 5.71E-07 4.98E-10 1.00 1.00 1.00 Resident NW 1140 1.25E-06 1.50E-09 1.00 1.00 1.00 Resident, Garden NNW 800 3.42E-06 5.67E-09 1.00 1,00 1.00 Garden N 16S0 2.20E-06 5.10E-09 1.00 1.00 1.00 Garden NNE 3010 1.28E-06 3.24E-09 1.00 1.00 1.00 Garden E 2630 3.38E-07 6.14E-10 1.00 1.00 1.00 Garden ESE 1980 5.08E-07 9.57E-10 1.00 1.00 1.00 1 Garden SE 3010 3.19E-07 7.16E-10 1.00 1.00 1.00 i Garden S 2290 1.38E-06 2.22E-09 1.00 1.00 1.00 Garden SW 3660 7.96E-07 1.34E-09 1.00 1.00 1.00 Garden WSW 1680 1.16E-06 1.43E-09 1.00 1.00 1.00 ) Garden W 1830 8.02E-07 7.26E-10 1.00 1.00 1.00 l Garden NW 1180 1.19E-06 1.42E-09 1.00 1.00 1.00 Milk Cow Adult N 4120 6.18E-07 1.10E-09 0.10 1.00 1.00 g-Milk Cov Adult NE 6750 3.94E-07 7.03E-10 0.10 1.00 1.00 ) t Milk Cow Adult WNW 1750 5.71E-07 4.98E-10 0.25 1.00 1.00 \\ Milk Cow Adult NW 1980 5.61E-07 6.09E-10 0.57 1.00 1.00 i i
Entire page changed and renumbered 1157c l
.=- - SQN ODCM Page 53 of 117 - Revision 20 l Table 1.2 EXPECTED ANNUAL ROUTINE CASEOUS RELEASES FROM ONE UNIT AT SEQUOYAH NUCLEAR PLAfrE Curies / year AUXILIARY TURBINE SERVICE { @,CLIE BUILDING CONTAIfMENT BUILDING BilUalEG i Kr-85m 2.2E-00 2.3E-00 1.5E-00 6.1E-02 i j Kr-85 2.0E-00 5.1E+02 1.2E-00 5.1E-00 S Kr-87 1.2E-00 8.1E-01 8.2E-01 2.8E-02 l 1 Kr-88 4.1E-00 3.6E-00 2.7E-00 1.0E-Oi Kr-89 , 2.7E-02 8.3E-03 6.4E-02 9.9E-04 I I Xe-131m 1.7E+00 2.6E+01 1.1E+00 2.9E-01 + Xe-133m - 3.7E+00 1.6E+01 2.4E+00 2.2E-01 I Xe-133 2.9E+02 2.4E+03 1.8E+02 2.9E+01 1 Xe-135m 1.8E+01 7.8E-02 2.0E-01 1.8E-01 Xe-135 6.8E+00 9.9E+00 4.4E+00 2.1E-01 4 i Xe-137 5.6E-02 1.8E-02 1.2E-01 1.9E-03 i Xe-138 5.9E-01 2.4E-01 6.2E-01 1.5E-02 k Br-84 3.5E-04 4.9E-06 1.7E-05 3.7E-06 i Br-85 1.2E-05 1.3E-07 2.4E-07 1.2E-07 I I-131 4.5E-02
1. 2 E -02 9.2E-03 6.6E-04 I-132 1.7E-02 3.7E-04 2.6E-03 2.0E-04 I-133 6.5E-02 3.3E-03 1,4E-02 8.2E-04
) I-134 7.1E-03 1.1E-04 5.0E-04 7.7E 05 I-135 1.3E-02 9.0E-04 5.4E-03 3.9F-04 [ j Rb-88 1.6E+00 2.1E-02 1.0d-04 1.6E-02 L j Cs-134 5.5E-05 1.1E-05 6.3E-05 1.3E-06 l Cs-136 2.9E-05 2.6E-06 3.6E-05 6.8E-07 Cs-137 4.0E-05 7.8E-06 5.3E-05 1.0E-06 Cr-51 2.0E-06 2.6E-07 3.6E-07 2.6E-08 Mn-54 1.6E-06 3.1E-07 4.5E-07 2.4E-08 Fe-59 2.1E-06 3.2E-07 5.4E-07 3.0E-08 i j Co-58 5.3E-07 8.8E-08 9.0E-06 9.6E-08 ( Co-60 1.6E-06 3.1E-07 2.7E-07 2.2E-08 Sr-89 7.6E-07 1.2E-07 1.6E-07 1.0E-08 j Sr-90 2.2E-08 4.3E-09 8.4E-09 3.5E-10 l Sr-91 1.5E-06 1.2E-08 8.9E-08 1.6E-08 4 Y-90 3.8E 08 4.7E-09 8.2E-09 5.1E-10 l l Y-91m 9.1E-07 7.4E-09 4.1E-08 9.6E-09 t i Y-91 4.4E-06 7.0E-07 1.9E-06 7.0E-08 3 Y-93 3.0E-07 2.4E-09 3.6E-08 3.4E-C9 2r-95 1.3E-07 2.1E-08 8.4E-08 2.4E-09 j Nb-95 1.1I-07 2.2E-08 8.4E-08 2.2E-09 Mo-99 9.9E-04 3.0E-05 1.4E-04 1.2E 45 I Tc-993 8.9E-04 2.8E-05 1.0E-04 1.0E-05 i Ru-106 2.2E-08 4.1E-09 8.42-09 3.5E-10 { Te-132 6.0E-05 2.0E-06 2.1E-05 8.3E-C7 Ba-140 4.8E-07 4.4E-08 2.1E-07 7.3E-09 } La-140 3.4E-07 4.6E-08 1.4E-07 5.3E-09 1 Ce-144 7,2E-08 1.4E-08 4.2E-08 1.3E-09 Pr-143 1.1E-07 1.1E-08 4.2E-08 1.3E-09 i Pe-144 7.7E-08 1.4E-08 2.8E-08 1.2E-09 ) N -239 2.7E-06 7.0E-08 1.2E-06 4.0E-08 P ) 1 i
Entire page chan8ed and renumbered
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SQN ODCM Page 54 of 117 " Revision 20 .......~e o o o o o o o o o o o o o..."s s s ooo N N. o*o**99o9aooooo* o o ooooooooooooooo o oooooooooooooooo o i dddddddddddddddd 4 i tl o .2 eBooo5oE550&oE55 M A dddddddddddddddd & C i L d 3 a $= 3 9 d 2$ r W W 8 Ed 3 w * <h J E.#.Sct.o.o..k#.k U..E.8.E @ g e3,- g oooooooooooooooo. o = ev w* 93 3d b d 0 ~ 5 ud
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~ -. - - - - - - _ _. - _. - _ _ _ - - - i o 2: 5cr 1 g TABLE 1.3 (4 of 8) -o JOINT PfieCENTAGE FRE NCIES OF WIND DIRECTION AND WIND SPEED F0ll DI JAMILIIV CL/55ET* n 7 STABIL TY CLASS D g -1.5 < DELTA T1-0.5 DEG. C/100M l e 2[QUOYAN NUCLEAR P ANT METEOROLOGICAL FACILITY
3 JAN. 1. 72 - DEC. 31, 75 j
i WING WIND SPEED (MPH) OIRECTION CAtM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4, >24.5 TOTAt N 0.003 0.01 0.24 0.22 0.16 0.17 0.0 0.0 0.0 0.80 NME 0.017 0.05 0.73 1.03 0.84 0.78 0.07 0.0 0.0 3.51 NE 0.006 0,02 0.76 0.88 0.42 0.42 0.05 0.0 0.0 2.55 ENE 3.003 0.04 0.21 0.11 0.03 0.0 0.0 0.0 0.0 0.36 E 0.003 0.01 0.12 0.03 0.02 0.01 0.0 0.0 0.0 0.19 i [5E 0.003 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.0 0.09 i SE 0.0 0.0 0.12 0.08 0.0 0.0 0.0 0.0 0.0 0.20 l SSE 0.0 0.' O.15 0.15 0.05 0.06 0.01 0.01 0.0 0.43 i 5 0.003 0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 55W 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 4 'J 0.003 0.01 0.47 1.17 1.03 OA2 0.03 0.01 0.0 3.24 I WSW 0.0 0.0 0.22 0.34 0.18 0..:1 0.07 0.01 0.0 1.03 W 0.003 0.01 0.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47 l WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 0.42 NW 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72 NNW 0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 0.93 l SUBIOTAL 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 i I* l-l 6567 STABILITY CLASS D OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE DIFFERENCE READINGS i MNm 6345 VALIO WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 6567 STA81LITY CLASS 0 OCCURRENCES Qjj ALL COLUMMS AND CALM TOTAL 100 PERCENT OF MET VALID READIP%S ",,O 8"9 MTEON0'OCICAL FACILITY LOCATED.74 MILES SW OF SEQUOYAH NUCLIAR PLANT w$ TEMPERATURE INSTRUMENTS 33 and 150 TEET ABOVE GRouMD C WIND INSTRUMENIS 33 FEET ABOVE GROUND U ~ W %J9 4 O + l Q, a. . - = - -.
- - - - ~... ~. -.. -. -. -.. ~ -= - = - - Z fi TABLE 1.3 (5 of 8) JOINT PfRCINTAGF FRFQJINCITS OF WIND O!RECTION AND WIND SPFfD a FDIFEFFTEniT 5TABTETTY CFA';5FP ~ n 7 STA81LITY CLASS E ^ E .0.5 < DELTA T< 1.5 DEG. C/100M ee SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
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.1AN.1, 72 - DEC. 31, 75 l 'C \\ l WINO WIND SPEED (MPH) l OIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >24.5 TOTAL N 0.017 0.23 1.26 0.83 0.39 0.27 0.0 0.0 0.0 2.98 NME 0.023 0.31 2.83 2.46 1.07 0.92 0.03 0.0 0.0 7.62 NE 0.011 0.15 1.03 0.71 0.31 0.18 0.01 0.0 0.0 2.39 ENE 0.009 0.12 0.48 0.16 0.04 0.0 0.0 0.0 0.0 0.80 E 0.010 0.14 0.24 0.05 0.01 0.01 0.0 0.0 0.0 0.C5 ESE 0.007 0.09 0.11 0.01 0.01 0.01 0.01 0.0 0.e 0.24 SE 0.007 0.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 SSE 0.008 0.31 0.58 0.24 0.13 0.23 0.04 0.02 0.0 1.35 1 5 0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0 5.03 ( 55W 0.007 0.10 1.67 2.32 1.67 1.e5 0.11 0.0 0.0 7.32 SW 0.013 0.17 1.59 2.07 1.30 0.99 0.10 0.0 0.0 6.22 W5W 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.C 0.0 2.36 W 0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0 0.0 1.26 Id M 0.010 0.14 0.37 0.22 0.19 0.27 0.02 0.0 0.0 1.21 NW 0.007 0.10 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 '.l NNW 0.011 0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 l SU8 TOTAL 0.17 2.31 14.45 12.53 7.60 6.79 0.52 0.02 0.0 44.19 I* 14624 STABILITY CLASS E OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE OIFFERENCE RE3 DINGS 14146 VALID WING OIRECTIOh - WIND SPEED READINGS OUT OF TOTAL 14624 STABILITY CLASS E OCCURRENCES EN e 1"" ALL COLL #Nf5 AND CAIA TOTAL 100 PERCENT OF NET VALIO REA0!NGS se o E$N D 2 l METEOR 040GICAL FACILITY LOCATED.74 MILES SW OF SEQUDYAH Nu* LEAR PLANT 0 y TEMPERATURE IN51RUMEN15 33 and 150 FEET Aa0VE GRobMD o WINO INSTRUMENTS 33 TEET A80VE GRouMD 0 a t l l
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P"RCfMTACT OCCUPRINCE OF WIC a srrrrrontruNrmrcrms S SEQUDYet NUCLEAR PLANT METEOROLOGICAL FACILITT* .1AN. 1, 72 - DEC. 31, 75 o3 WING WIC SPELD(MMt) M DIRECTION CAI M 0.6-1.4 1.5-3.4 3J-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 =24.5 TOTAL N .044 0.51 3.20 1,63 0.67 0.58 0.0 0.0 0.0 6.59 MJE .063 0.82 8.30 5.05 2.46 2.18 0.11 0.0 0.0 18.92 NE .043 0.48 3.86 2.59 1.01 0.83 0.06 0.0 0.0 8.83 [hE .027 0.42 1.58 0.39 0.09 0.0 0.01 0.0 0.0 2.49 E .030 0.50 0.83 0.11 0.03 0.02 0.01 0.0 0.0 1.47 ESE .023 0.33 0.45 0.0F 0.02 0.01 0.02 0.0 0.0 0.90 5E .019 0.34 0.82 0.!9 0.01 0.02 0.0 0.0 0.0 1.38 SSE .024 0.4: 1.36 3.55 0.23 0.36 0.06 0.02 0.0 2.99 5 .011 0.47 2.89 2.49 1.58 1.53 0.14 0.0 0.0 9.10 55W .019 0.29 3.79 4.91 3.44 2.88 0.24 0.0 0.0 15.51 '.,W 923 0.33 3.55 4.79 3.02 1.':3 0.20 0.02 0.0 13.81 WSW .016 0.24 1.68 1.39 0.66 0.69 0.16 0.02 0.0 4.64 W .016 0.21 0.78 0.47 0.35 0.44 0.06 0.01 0.0 2.32 IJM .019 0.21 0.70 0.36 0.34 0.51 0.03 0.0 0.0 2.21 NW .011 0.18 0.93 0.63 0.74 0.83 0.07 0.0 0.0 3.38 NNW .020 0.27 1.55 1.23 0.93 0.93 0.04 0.0 0.0 5.01 SUBTOTAL 0.43 6.04 36.24 26.65 15.58 13.76 1.21 0.07 0.0 99.55 32338 VALIO WIC DIRECTION - WIQ SPL[D READIN05 OUT OF 35043 TOTAL HOURS = 92.29 PERC[NT ALL COLUMNS AND CALM TOTAL 100 PtkCENT OF NE! VALIO READINGS w -o us 5 auo
P.IT[OROLOGICAL FACILITY 10CAICO.74 FILLS SW OF SEQUOY41 W3 CLEAR PLANT
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SQN ODCM Page 62 of 117 Revision 20 7m Table 1.4 s-DOSE TACTORS FOR SUBMERSION IN NOBLE CASES DFB
DTS

DTxt**
DFgt** t t mrem /yr per pC1/m3 mrad /yr per pC1/m3 Kr-85m 1.17E+03 1.46E+03 1.21E+03 3.86E+03 Kr-85 1.61E+01 1.34E+03 1.69E+01 3.83E+03 Kr-87 5.92E+03 9.73E+03 6.05E+03 2.01E404 ) Kr-88 1.4* 2,37E+03 1.50E+04 5.72E+03 s. Kr-88+D 2.02E+04 3.72E+04 { Kr-29 1.66E+04 A.01E+04 1.59E+04 1.88E+04 Xe-131m 9.15E+01 4.76E+02 1.53E+02 2.18E+03 Xe-133m 2.51E+02 9.94E+02 3.17E+02 2.90E+03 Xe-133 2.94E+02 3.06t+02 3.46E+02 2.06E+03 Xe-135m 3.12E+03 7.11E+02 3.30E+03 1.45E+03 ) Xe-135 1.81Et03 1.86E+03 1.88E+03 4.84E+03 Xe-137 1.42E+03 1.22E+04 1.48E+03 2.50E+04 I Xe-138 8.83E+03 4.13E+03 9.00E+03 9.25E+03 Xe-138+D 2.65E+04 2.81E+04 I Ar-41 8.84E+03 2.69E+03 9.76E+03 5.54E+03 ) Referencest sj
Regulatory Guide 1.109.
TVA generated values.
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SQti ODCM Page 63 of 117 i " Revision 20 i i Table 1.5 [ SECTOR ELEMEtrIS C0!!SIDERED TOR F0FULATION DOSES L i Range of Midpoint of f Sector Element Sector Element l 4 i Site boundary - 1 mile 0.8 mile l q 1-2 miles 1.5 miles ? 2-3 miles 2.5 miles 3-4 miles 3.5 miles i l i 4-5 miles 4.5 miles 5 - 30 miles 7.5 miles 10 - 20 miles 15 miles { 20 - 30 miles 25 miles I 30 - 40 miles 35 miles l 40 - 50 miles 45 miles I 1 { f 1 4 i I 4 I l i i s i 4 l l 1 d ) l J i i i
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SQN ODCM Page 64 of 117 Re'tision 20 -a Table 1.6 P0FULATIO.1 WIT!!!N EAClt SECTOR ELEMElff 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N 0 15 35 10 5 615 4865 2725 2535 10050 UNE O 0 45 65 35 265 8315 4770 4635 6275 NE O 0 0 35 20 235 1220 2765 7000 14370 ENE o lo 0 75 100 335 3715 8470 37275 12635 E 0 20 15 60 50 330 17245 3625 3450 4415 ESE 5 50 50 100 60 875 60490 3660 1190 11935 SE 5 145 15 65 65 550 12205 3165 1795 2370 SSE O 25 85 255 80 530 10085 9950 64775 3470 S 0 60 5 145 200 775 12560 10250 36795 8350 s SSW 0 45 40 155 85 2260 139250 72170 17640 6430 SW r 0 35 130 35 3770 174125 44450 10435 5170 USW 5 50 250 490 465 7305 33710 5435 17105 14995 W 5 30 85 205 215 6245 1655 5700 4005 3880 VNW 0 20 110 305 790 4730 3210 3465 3835 1835 tiW 5 30 140 160 390 9050 1235 1660 870 16300 NNW 5 60 10 30 270 1200 505 2725 1635 4420 0
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I SQN ODCM Page 65 of 117 Revision 20 OV Table 1.7 (1 of 8) INGESTION DOSE TACTORS (mrem /pci ingested) i ADULT bone livei t body thyroid kidney lung gi-111 ] H-3 1.05E-07 1.05E-07 1.05E-07 1.0$E-07 1.0$E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 I Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 7 j Mn-54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 1 Te-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 1 Te-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.45E-06 3.40E-05 t I j Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9. 0 3 F.-0 6 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.2SE-07 6.36E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 I Cu-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 i 1 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 2n-69 1.03E-03 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 1 Br-84 0.0cE+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 l Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E600 ( I Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 Ac16E-06 Rb-88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 3.36E-19 ) Rb-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 l i Sr-89 3.05E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 4 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 l 3r-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 l St-92 2.15E-06 0.00E+00 9.30E-08 0.00E+0C 0.00E+00 0.0 U+00 4.26E-05 l Y-90 9.6?E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.0 400 1.02E-04 l 1 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.0 t+00 2.67E-10 ) Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E400 0.ccE+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E 05 ) 2r-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 { s 2r-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 i Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 C.00E+00 2.10E-05 j Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 1 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 l Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 4 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 l Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 As-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-03 2.38E-08 8.15E-08 4.4tE-07 0.00E+00 8.68E-06 j
N obering chan8e only 1157c s
l i SQN ODCM l Page 66 of 117 Revision 20 I I Table 1.7 (2 of 8) INGESTION DOSE TACTORS (mrem /pci ingested) [ t ADULT bone liver t body thyroid kidney lung gi-111 i j Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 L i Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 l I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 ) I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 4 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.590-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E 06 2.92E-06 t Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05
1. 2 3 E- 0 5 2.11E-06 i
Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 I Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 j Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 3.00E-26 j La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 I { La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 j Ce-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 ] Ce-143 1.65E-09 1.22E-06 1.3)E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 1 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E400 2.13E-09 0.00E+00 4.03E-05 t j Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 i 1 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 l W-187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 i l Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 1 i i i i References Regulatory Guide 1.109. Table E-11 j NOTE: The tritium dose factor for bone is assumed to be equal to the l 1 total body dose factor. I 1 i l l I I I
Numberin8 chan8e only 1157c
I SQN ODCM Page 67 of 117 Revision 20 1 i t Table 1.7 (3,f 8) INGESTION DeSE TACTORS j (mrem /pC1 ingested) l TEEN bone liver t body thyroid kidney luna 81-111 ] H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.05E-07 i C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E.L7 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 I P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00Edo 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 l Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 ] Mn-56 0.00E+00 1.5SE-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Te-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 i Te-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 i Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 i a Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 j Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 i Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 r j Cu-64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 2n-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 i Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-05 0.00E+00 5.16E-08 l Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E600 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 3.0$E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Eb-86 0.00Z+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 ) Rb-88 0.00E+00 8.52E-05 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 i St-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 j Sr-90 8.30E-03 0.00E+00 2.0$E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 i Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 l Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 i j Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.COE+00 6.09E-09 l 1 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 l l Y-92 1.21E-09 0.00E+v0 3.50E-11 0.00E400 0.00E+00 0.00E+00 3.32E-05 ) Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 j Zr-95 4.1?E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 l 1 Zr-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 l j Hb-95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 l i Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.0$E-05 i l Tc-99m 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.3SE-08 5.14E-10 6.08E-07 q Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 l R2-103 2.55E-07 0.00E+00 1.09E-07 0.00E400 8.99E-07 0.00E+00 2.13E-05 l Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 i Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 1 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 l Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 ^ Te-127 1.58E-07 5.60E-05 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 i 1 l
Nu-bering change only 1157c l
SQN ODCM Page 68 of 117 Revision 20 Table 1.7 (4 of 8) INCESTION DOSE FACTORS (mrem /pci ingested) TEEN bone liver t body thyrois Xidney lun8 81-111 Te-129m 1.63E-05 6.0$E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 I-130 1.01E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 I-131 5.85?-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 I-132 2.79E-41 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 I-134 1.46E-0? 3.87E-07 1.39E-07 6.45E-s6 6.10E-07 0.00E+00 5.10E-09 I-135 6.10E-07 1.57F-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 . 05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-L8 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.56E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.00E+00 4.74E-la Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 V-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05
Reference:
Regulatory Guide 1.109. Table E-12 NOTE: The tritius dose facter for bone is assumed to be equal to the total body dose factor.
Numbering change only 1157c m
Y
SQN ODCM Page 69 of 117 Revision 20 \\' Table 1.7 (5 of 8) INGESTION DOSE FACTORS (mrem /pCi ingested) CHILD bone liver t body thyroid kidney lung gi-111 H-3 2.03E-07 2.03E-07 2.032-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 S.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 Mn-56 0.00E+00 3.343-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E400 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co-60 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 2n-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 2n-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 [ ) Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 \\s_/ Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E400 4.31E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 Rb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00
0. 0E+00 5.11E-05 Sr-90 1.70E-02 0.00E+00 4.312-03 0.00E400 0.00E+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 Oe00E+00 0.00E+00 0.00E+00 1.71E-04 Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 1
6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 12 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 2r-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Hb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-Of 9,19E-10 1.03E-06 Tc-101 1.07E-09 1 12E-09 1.42E-08 0.00E+00 1.91E-08 S.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 (NI Te-32/ 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 j
Numbering change oni, 1157e
SQN ODCM Page 70 of 117 Revision 20 [ h Table 1.7 (6 of 8) JNGESTION DOSE FACTORS (mrem /pci ingested) CHILD bone liver t body thyroid kidney lung gi-111 Te-129c 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.9?E-07 0.00E+00 8.34E-06 Te-131m 7.203-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cc-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-133 2.28E-07 3.??E-C' 2.01E-07 0.00E+00 2.23E-07 2.40E-OS 1.46E-07 Ba-139 4.142-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 g~g Ba-140 8.31E-05 7.28E-08 4.8 5E -06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 ( Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 N _- Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 s La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Cc-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-00 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11
6. 49 E -12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-03 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+0C 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05
Reference:
Regulatory Guide 1.109, Table E-13 NOTE: The tritium dose factor for bone is assumed to be equal to the tot 1 body dtse factor, j O s_-
Numbering change only 1157c
SQN ODCM Page 71 of 117 Revision 20 OV Table 1.7 (7 of 8) INGESTION DOSE FACTORS (mrem /pci ingested) INFANT bone liver t body thyroid kidney lung gi-111 H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 l Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39F-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E400 0.00E600 1.59E-05 2.57E-05 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-0E 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 } 2n-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 i Br-83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+0D 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4.96E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+0s 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+30 0.00E+00 0.00E+00 2.07E-04 i Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 I Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 l Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 l Nb-95 4.20' 8 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Mo-99 0.00' va 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92b-09 3.96E-09 !.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 i Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 l Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 i Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83L-04 l Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Ts-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 1 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 i
Numbering change only 1157c
SQN ODCM PaSe 72 of 117 Revision 20 ( / Table 1.7 (8 of 8) INGESTION DOSE FACTORS (mrem /pci ingested) INFANT bone liver t body thyroid kidney lung gi-111 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.052-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05.1-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E- 06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 gs Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 \\ f Ba-141 4.25E-07 2.91E-10 1.?4E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 \\s./ Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Cc-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Cc-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05 l i i
Reference:
Regulatory Guide 1.109, Table E-14 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. l (h \\s_s
Numbering change only 1157c A
h SQN ODCM l Page 73 of 117 --- Revision 20 O Table 1.8 (1 of 2) RADIONUCLIDE DECAY AND TRANSFER DATA f Half-Live A Biy Fmi Fmi Ifi (Dr. ) (1/s) (cow) (goat) (beef) 1 H-3 4.4VL+03 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 l C-14 2.09E+06 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 N-13 6.94E-03 1.16E-03 7.50E+00 2.20E-02 2.20E-02 7.70E-02 0-19 3.36E-04 2.39E-02 1.60E+00 2.00Ev02 2.J0E-02 1.60E-02 i F-18 7.62E-02 1.03E-04 6.50E-U4 1.40E-02 ' 40E-02 1.50E-01 l Na-24 6.33E-01 1.27E-05 5.20E-02 4.00E-02 4.00E<02 3.00E 02 i P-32 1.43E+01 L.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Ar-41 7.63E-02 1.05E-04 6.00E-01 2.00E-02 2.00E-02 2.00E-02 Cr-51 2.78E+01 2.39E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 3.03E+02 2.65E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.07E-01 7.50E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-59 4.50E+01 1.78E-07 6.60E-04 1.20E-03 1.30E-04 4.00E-02 Co-58 7.13E-01 1.12E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 i Co-60 1.92E-03 4.18E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 i Zn-69m 5.75E-01 1.39E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 3.96E-02 2.03E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 I Br-84 2.21E-02 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 l Br-85 2.08E-03 3.86E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 { Kr-85m 1.83E-01 4.38E-05 3.00E+00 2.00E-02 2.00E-02 2.00E-02 l Kr-85 3.93E+03 2.04E-09 3.00E-00 2.00E-02 2.00E-02 2.00E-02 Kr-87 5.28E-02 1.52E-04 3.00E-00 2.00E-02 2.00E-02 2.00E-02 l ( ^ Kr-88 1.17E-01 6.86E-05 3.00E-00 2.00E-02 2.00E-02 2.00E-02 ) Kr-89 2.21E-03 3.63E-01 3.00E-00 2.00E-02 2.00E-02 2.00E-02 Rb-88 1.24E-02 6.47H-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.07E-02 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 5.20E+01 1.54E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.03E+04 7.79E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 4.03E-01 1.99E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.132-01 7.10E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-93 5.56E-03 1.44E-03 1.70E-02 1.40E-03 1.40E-02 6.00E-04 i Y-90 2.67E+00 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 3.47E-02 2.31E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 5.88E+01 1.36E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 1.47E-01 5.46E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 l Y-93 4.?9E-01 1.87E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 6.50E+01 1.23E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95m 3.75E+00 2.14E-06 9.40E-03 2.50E-03 2.50E-03 2.80E-01 i l Nb-95 3.50E+01 2.29E-07 9.40E-03 2.30E-03 2.50E-03 2.80E-01 1 Mo-99 2.79E+00 2.87E-06 1.20E-01 7.50E-03 7.50E-03 8.00E-03 I Tc-99m 2.50E-01 3.21E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-99 7.74E+07 1.04E-13 2.50E-01 2.50E-02 2.50E-02 4.00E-01 l l Tc-104 1.25E-02 6.42E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 l
References:
NUREG/CR-1004 for Iodine, Strontium, and Cesium milk transfer factors. 4 Regulatory Guide 1.109 for all other nuclides' transfer factors. I
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SQN ODCM Page 74 of 117 Revision 20 \\s /' Table 1.8 (2 of 2) RADIONUCLIDE DECAY AND TRANSFER DATA Half-Live A By Fmi Fmi Fri i (Days) (1/s) (cow) (goat) (beef) Ru-106 3.67E+02 2.19E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Te-132 3.24E+00 2.48E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-129 6.21E+09 1.290-15 2.00E-02 1.20E-02 4.30E-01 2.86E-03 I-131 8.08E+00 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 9.58E-02 8.37E-05 2.00E-02 1.20E-02 4.30E-91 2.90E-0.t I-133 8.75E-01
9. lie-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134 3.61E-02 2.22L 04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-135 2.79E-01 2.87E-03 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Xe-131m 1.18E+01 6.80E-07 1.00E+01 2.00E-02 2.00E-02 2.00E-03 Xe-133m 2.26E+00 3.55E-06 1.00E+01 2.00E-02 2.00E-02 2.00E-03 Xc-133 5.27E+00 1.52E-06 1.00E+01 2.00E-02 2.00E-02 2.00E-03 Xe-135m 1.08E-02 7.43E-04 1.00E+01 2.00E-02 2.00E-02 2.00E-03 Xe-135 3.83E-01 2.09E-05 1.00E+01 2.00E #:
2.00E-02 2.00E-03 Xc-137 2.71E-03 2.96E-03 1.00E+01 2.00E-02 2.00E-02 2.00E-02 Xe-138 1.18E-02 6.80E-04 1.00E+01 2.00E-02 2.00E-02 2.00E-02 Cs-134 7.48E+02 1.07E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-135 1.10E+09 7.29E-15 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 3.30E+01 6.17E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cc-137 1.10E+04 7.29E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 k'~'Nj Ba-139 5.76E-02 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Cs-138 2.24E-02 3.58E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-140 1.28E+01 6.27E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 1.68E+00 4.77E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-144 2.84E+02 2.82E-08 2.50E-03 1.00E-04 6.00E-04 1.20E-03 Pr-143 1.36E+01 5.90E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.20E-02 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Np-239 2.35E+00 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04
References:
NURFC/CR-1004 for Iodine, Strontium, and Cesium milk transfer factors. Regulatory Guide 1.109 for all other nuclides' transfer factors. L U
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~. ~ SQN ODCM Page 75 of 117 - i Revision 20 \\ j Table 1.9 (1 of 2) DOSE CALCULATION FACTORS Factor Value Units Reference bra (infant) 1400 m3/ year ICRP 23 bra (child) 5500 m3/ year ICRP 23 bra (teen) 8000 m3/ year ICRP 23 bra (adult.. 8100 m3/ year ICRP 23 f 1 TVA Value g ft 1 TVA Value f (monthly) 1 TVA Value fp (for calculations other than monthly see Table l'.4 doses) f (monthly) 0 TVA Value 3 f (for calculations 3 other than monthly 1-fp doses) H 9 g/m3 TVA Value P 240 kg/m2 R. G. 1.109 8 Qt (cow) 64 kg/ day IWREG/CR-1004 (Sect. 3.4) Qg (goat) 08 kg/ day NUREG/CR-1004 (Sect. 3.4) r 0.47 fiUREG/CR-1004 (Sect. 3.2) tb 1.11E+09 seconds TVA Value (35 years) + teb 7.78E+06 seconds TVA Value (90 days) tear 1.56E+07 seconds TVA Value (180 days) t 5.18E+06 seconds R. G. 1.109 e (60 days) t 2.59E+06 seconda R. G. 1.109 a ep (30 days) test 7.78E+06 seconda R. G. 1.109 (90 days) { tfm 8.64E+04 seconds TVA Value l (1 day) the 8.64E404 seconds !NREG/CR-1004, Table 3.40 (1 day) to 1.12E+06 seconds fiUREG/CR-1004, Table 3.40 (13 days) i ty 2.38E+07 seconds TVA Value 3 (275 days) i Uam (infant) 0 kg/ year R. G. 1.109 Uam (chlid) 41 kg/ year R. G. 1.109 j Uam (teen) 65 kg/ year R. G. 1.109 l Uam (adult) 110 kg/ year R. G. 1.109 ap ((infant) U 330 L/ year R. G. 1.109 [ U child) 330 L/ year R. G. 1.109 ap l Uap (teen) 400 L/ year R. G. 1.109 Uap (adult) 310 L/ year R. G. 1.109 l
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SQti ODCt! Page 76 of 117 Revision 20 \\d Table 1.9 (2 of 2) DOSE CALCULATIO!I FACTORS Factor Value Units Reference UFLa (infant) 0 kg/ year R. G. 1.109 UFLa (child) 26 kg/ year R. G. 1.109 UFLa (teen) 42 kg/ year R. G. 1.109 UFLa (adult) 64 kg/ year R. G. 1.109 usa (infant) 0 kg/ year R. G. 1.109 usa (child) 520 kg/ year R. G. 1.109 usa (teen) 630 kg/ year R. G. 1.109 usa (adult) 520 kg/ year R. G. 1.109 Yf 1.85 kg/m2 IWREG/CR-1004, Sect. 3.1 Y 1.18 kg/m2 p !WREG/CR-1004, Sect. 3.1 Ysf 0.64 kg/m2 tWREG/CR-1004, Sect. 3.1 Y.3 y 0.57 kg/m2 INREG/CR-1004, Sect. 3.1 (value selected is for non-leafy vegetables) 1 (iodines) 7.29E-07 see-1 fmREG/CR-1004, Sect. 3.3 9 Av (particulates) 5.35E-07 sec-1 IGREG/CR-1004, Sect. 3.3 s
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SQN ODCM Page 77 of 117 Revision 20 Table 1.10 (1 of 8) INHALATION DOSE FACTORS l (crem/pci inhaled) l ADULT bone liver t body thyroid kidney lung gi-111 H-3 0.00E+00 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 i Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 4 i Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 5.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 l Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 [ Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-13 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 0.48E-07 6.12E-06 2n-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 i Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-07 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 t Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 i Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4'.18 E-19 l Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 i Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0.00E$00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.33E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 I Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 2r-95 1.34Et05 4.30E-06 2.91E-06 0.00E+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54B-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31E-05 1.30H-05 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.100-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-03 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 { Ru-106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 i Ag-110m 1.35E-06 1.25E-06 7.48E-07 0.00E+00 2.46E-06 5.79E-04 3.78E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 j Te-127 1.75E-10 8.032-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 l
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j SQN ODCM Page 78 of 117 Revision 20 O Table 1.10 (2 of 8) ImlALATION DOSE FACTORS l (mrem /pci inhaled) ADULT bone liver t body thyroid kidney lung gi-111 I Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E 07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 l I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 I-131 ~ 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 l Co-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 i Cc-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 I Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-03 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 t La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Cc-143 2.33E-08 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.7JE-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00Et00 3.63E-06 1.94E-05 l Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 l i i 1 References Regulatory Guide 1.109, Table E-7 I l 1 1, ) i i 1 l
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SQN ODCM Page 79 of 117 - Revision 20 Table 1.10 (3 of 8) INHALATION DOSE FACTORS (crem/pci inhaled) TEEN bone liver t body thyroid kidney lung gi-111 i H-3 0.00E+00 1.59E-07 1.59E-07 1.39E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00r+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 a 9 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 j Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 2n-65 4.822-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s Br-84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E400 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 l Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00Ft00 3.6SE-15 i 4 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.223-17 Sr-89 5.43E-05 0.00E+00 1.5CE-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 l Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 l Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 ) Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 i Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 i Zr-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 i ,l Hb-95 2.32E-06 1.29E-06 7.0$E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3,36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 1 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.00E+00 1.55E-06 0.00E+00 2.38E-05 3.01E-03 1.20E-04 As-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-05 l Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.7CE-05 9.38E-06 n Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 ( Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 j
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SQN ODCM Page 80 of 117 Revision 20 p x_, Table 1.10 (4 of 8) INHALATION DOSE FACTORS (mrem /pci inhaled) TEEN bone liver t body thyroid kidney lung gi-111 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44U-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30R-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E-0/ 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00F+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 3.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.33E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 /'~'N Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 ( ) Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.62E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 .a-142 1.20E-10 5,31E-11 1.32E-11 0.00E+00 0.00Ee00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00S+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19 E-0.* Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2,20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.252-08 8.11E-06 1.65E-05
Reference:
Regulatory Guide 1.109, Table E-8 OV
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'SQN ODCM Page 81 of 117 .I Revision 20 ( N Table 1.10 (5 of 8) INHALATION DOSE FACTORS (mrem /pci inhaled) CHILD bone liver t body thyroid kidney lung gi-111 H-3 0.00E+0C 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 i C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 I Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E 06 4.35E-06 4.35E-06 4.35E-06 P-3^ 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-04 6.57E-09 4.59E-06 2.93E-07 f Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 i Mn-56
0.00E+00 4.48E-10 8.43E-11 0.00E+00 0.00E+00 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 i
Fe-59 5.592-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-05 Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 l Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00Z+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 i Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 l Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.815-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 4 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 t Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 C J0E+00 5.83E-04 4.52E-05 i Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 i Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 [ j Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 i Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 ) Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 l Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.0$E-04 2r-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 l Nb-95 6.35E-06 2.48E-06 1.77E406 0.00E+00 2.33E-06 1.66E-04 1.00E-05 l Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00
1. 37P -11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00A+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.h1E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.6aE-05 0.00R+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1.16E-04 l
Ag-110m 4.56E-06 3.08E-06 2.471-06 0.0VE+00 5.74E-06 1.48E-03 2.71E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 l Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-0? 2.71E-06 1.52E-05
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SQN ODCM 7 age 82 of 117 - ' Revision 20 N Table 1.10 (6 of 8) INHALATION DOSE FACTORS l (mrem /pci inhaled) CHILD bone liver t body thyroid kidney lung 31-111 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 j Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 l Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.600-07 r Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 t 2 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 I-131 - 1. 30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 [ I-132 5.72E-07 1.10E-06 5.07E-07 5,23E-05 1.69E-06 0.00E+00 8.65E-07 I-133 4.48E-06 5.49E-09 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 I-135 1.33E 06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.10E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14Es05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cc-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 l Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.7dE-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.050-05 j Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 e-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 l Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 i Pr-143 4.99E-06 1.5]E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 1 Nd-147 2.92E-06 2.36E-06
1. 8 /.E-0 7 0.00E+00 1.30E-06 9.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E.05 2.46E-05
{ Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-03 1.7JE-05 j
Reference:
( Regulatory Guide 1.109, Tablo E-9 e 1 l I j arage added 1157c 1 4 4 4
SQN ODCM Page 83 of 117 Revi; ion 20 1 \\ t. / Table 1.10 (7 of 8) I!OIALATION DOSE FACTORS (mrem /pci inhaled) INFANT bone liver t body thyroid kidney lung gi-111 H-3 0.00E+00 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 /.SAE-Oo 7.54E-06 7.54E-06 7.54E-06 7.54E-06 l P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr-51 0.OnE+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 e Mn-54 0.00E+00 1.81E-05 3.560-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 j Mn-56 ' O.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 l Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 0.00H+00 7.25E-04 1.77E-05 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+0C 0.00E+00 5.55E-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.?.9E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 ] Zn,65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.30E-05 4.62E-04 3.67E-05 2n-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 1 Br-83 0.00E+00 0.00E+00 2.722-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-37 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-A9 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-03 5.24E-05 i Sr-92 7.50E-09 9.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-03 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-00 7.43E-05 Y-91m 2.91E-10 0.00E+00 0.90E-12 0.00E+00 0.00E+00 1.'9E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 i Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+C0 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.998-05 1.45E-05 0.00E+00 2.22E-05 1.25F-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+VO 1.858-08 7.842-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Mo-99 0.00E400 1.18E-07 2.312-08 0.0dE+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-04 5.80E-13 0.00E+00 6.99E-13 4.17E407 6.03E-07 i Ru-10.s 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 l Ru-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.42E-10 1.12E-05 3.46E-05 l Ru-106 6.20E-05 0.00E+00 7.770-06 0.00E+00 7.61E-05 4.26E-03 1.17E-04 1 i Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 l Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 j Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 g \\s_ / n 4 I ]
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SQN ODCM Page 84 of 117 Revision 20 Table 1.10 (8 of 8) l!GiALATION DOSE FACTORS (mrem /pci inhaled) INFANT bone liver t body thyroid kidney lung 31-111 l Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.6v2-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 8.15E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 ) I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E400 7.56E-07 l I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 l Cs-137 3.92E-04 4.375-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-13S 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.57E-08 6.26E-07 La-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 i Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.121 10 7.70E-04 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00B+00 1 36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.*~E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.8?E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3 75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-01 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Cc-144 2.28E-03 P.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E&OO 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72"-12 0.005&OO 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+0? 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 l Up-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05 Reference Regulatory Guide 1.109, Table E-10
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SQN ODCM Page 35 of 117 '"' Re. vision 20 [ } Table 1.11 (1 of 2) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (crem/h per pCi/m2) Nuclide Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-03 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe'-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2. 0.'E -0 8 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 / i Br-85 0.0 0.0 (,) Rb-86 6.30E-10 7.20E-10 Rb -8 8 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 St-89 5.60E-13 6.5CE-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 i Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-9fs 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-03 Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 \\ )
Reference:
Regulatory Guide 1.109. h.
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SQN ODCM Pa8e 86 of 117 -"' Revision 20 T Table 1.11 (2 of 2) EXTERNAL DOSE EACTORS FOR STANDING ON CONTAMINATED GROUND 2 (mrem /h per pCi/m ) Nuclide Total Body Skin Te 129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 i Te-131m 8.40E-09 9.90E-09 l Te-131 2.20E-09 2.60E-06 j Te-132 1.70E-09 2.00E-09 i I-130 1.40E-08 1.70L-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 i a l I-135 1.20E-08 1.40E-08 i I Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 i Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 i Ba-142 7.90E-09 9.00E-09 l La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Cc-141 5.50E-10 6.20E-10 l 4 Ce-143 2.20E-09 2.50E-09 I j Ce-144 3.20E-10 3.70E-10 [ g Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 t 4 j Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 l Np-239 9.50E-10 1.10E-09
Reference:
Regulatory Guide 1.109. 1 %w/ epa 8e added 1157c
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. ---=- O I l TABLE 2.1 (1 of 4) { DOSE COMMIIMENT FACTORS-(REM /MICROCI) cr HALF-LIFE NUCLIDE (CAYS) ADutT rHIt D E 80kE GI TRACT THYR 010 TOTAL 800Y LIVER B0t4E GI TRACT
THYROID TOTAL 800Y LIVER H-3 4.50E.03 1.05E-04 1.05E-04 1.0$E-04 1.05E-04 1.05E-04 2.03E-04 2.03E-04 2.03E-04 2.03E44 2.01E-04 E-C-14 2.08E.06 2.84E-03 5.6SE-04 5.68E-04 5.68E-04 5.68E-04 1.21E-02 2.42E-03 2.42E-03 2.42E-03 2.42E 03 E
Na-22 9.49E.02 2.50E-02 1.35E-02 1.21E-02 1.36E-02 1.40E-02 2.50E-02 1.35E-02 1.21E-02 '.36E-02 1.40E-02 N-24 6.26E-01 1.70E-03 1.70E-03 1.70E-03 1.70E-03 1.70E-03 5.80E-03 5.80E-03 5.80E-03 5.80E-03 5.80E-03 o f'-32 1.43E.01 1.93E-01 2.17E-02 7.46E-03 7.46E-03 1.20E-02 8.25E-01 2.28E-02 3.18E-02 3.18E-02 3.86E-02 3. Cr-51 2.77E.0: 2.66E-06 6.68E-04 1.59E-16 2.66E-06 2.66E-06 8.90E-06 4.72E-04 4.94E-06 8.90E-06 8.90E-06 Mn-54 3.12E.02 8.72E44 1.40E-02 S.72E-04 8.72E-04 4.57E-03 2.85E-03 8.98E-03 2.85E-03 2.85E-03 1.07E-02 Mn-56 1.08E-01 2.04E-05 3.67E-03 2.04E-05 2.04E-05 1.15E-04 7.54E-05 4.84E-02 7.54E-05 7.54E-05 3.34E-04 Fe-55 9.96E.02 2.75E-03 1.09E-03 4.43E-04 4.43E-04 1.90E-03 1.15E-02 1.13E-03 1.89E-03 1.89E-03 6.10E-03 Fe-59 4.46E.01 4.34E-03 3.40E-02 3.91E-03 3.91E-03 1.02E-02 1.65E-02 2.78E-02 1.33E-02 1.33E-02 2.67E-02 Co-57 2.71E.02 3.57E-04 4.56E-03 1.10E-04 1.84E-04 2.53E-04 3.57E-04 4.56E-03 1.10E-04 1.84E-04 2.53E-04 Co-58 7.C8E.01 1.67E-03 1.51E-02 1.67E-03 1.67E43 7.45E-04 5.51E-03 1.0$E-02 5.51E-03 5.51E-03 1.80E-03 Co40 1.92E 03 4.72E-03 4.02E-02 4.72E-03 4.72E-03 2.14E-03 1.56E-02 2.93E-02 1.56E-02 1.56E-02 5.29E-03 l Ni43 3.65E.04 1.30E-01 1.88E43 4.36E-03 4.36E-03 9.01E-03 5.38E-01 1.94E-03 1.83E-02 1.83E-02 2.88E-02 l Ni-65 1.05E-01 5.28E-04 1.74E-03 3.13E-05 3.13E-05 6.86E-05 2.22E-03 2.56E-02 1.22E-04 1.22E-04 2.09E-04 Cu44 5.30E-01 3.91E-05 7.10E-03 3.91E-05 3.91E-05 8.33E-05 1.48E-04 1.15E-02 1.48E-04 1.48E-04 2.45E-04 In45 2.44E.02 4.84E-03 9.70E-03 6.86E-03 6.96E-03 1.54E-02 1.37E-02 6.41E-03 2.27E-03 2.27E-03 3.65E-02 In49 3.96E-02 1.03E-05 2.%E-06 1.37E-06 1.37E-06 1.97E-05 4.38E-05 3.99E-03 5.85E-06 5.85E-06 6.33E-05 As-74 1.78E.01 2.90E-04 3.8SE-02 2.90E-04 2.90E-04 2.51E-04 2.90E-04 3.88E-02 2.90E-04 2.90E-04 2.51E-04 As-76 1.10E.00 4.49E-05 9.70E-02 4.49E-05 4.49E-05 4.70E-05 4.49E-05 9.70E-02 4.4SE-05 4.49E-05 4.70E-05 l Sr-43 1.00E-01 4.02E-05 5.79E-05 4.02E-05 4.02E-05 4.02E-05 1.71E.04 0.00E+00 1.71E-04 1.71E-04 1.71E-04 i Br-44 2.21E-02 5.21E-05 4.0 E-10 5.21E-05 5.21E-05 5.21E-05 1.90E-04 0.00E+00 1.98E-04 1.98E-04 1.98E-04 Sr-45 1.99E-03 2.14E-06 D OE-21 2.14E-06 2.14E-06 2.14E-06 9.12E-06 0.00E+00 9.12E-06 9.12E-06 9.12E-06 Kr-439 7.75E-02 0.00E+00 1.46E-04 0.00E.00 0.00E 00 0.00E.00 0.00E+00 1.46E-04 0.00E 00 0.00E.00 0.00E+00 l: Kr-85m 1.87E-01 0.00E.00 3.30E-03 0.00E.00 0.00E+00 0.00E+00 0.00E+00 3.30E-03 0.00E.00 0.00E+00 0.00E+00 Kr-85 3.91E.03 0.00E.00 4.62E-02 0.00E.00 0.00E+00 0.00E.00 0.00E+00 4.62E-02 0.00E 00 0.00E 00 0.00E+00 m.o en h-86 1.87E.01 9.83E-03 4.15E-03 9.83E-03 9.83E-03 2.11E-02 4.12E-02 4.31E-03 4.12E-02 4.12E-02 6.70E-02 7*o Sit -48 1.23E-02 3.21E45 S.36E-16 3.21E-05 3.21E-05 6.05E-05 1.32E-04 9.32E-06 1.32E-04 1.32E-04 1.90E-04 708 m-39 1.07E-02 2.82E-05 2.33E-18 2.82E-05 2.82E-05 4.01E-05 1.04E-04 1.02E-06 1.04E-04 1.04E-04 1.17E44 8 2 t Sr-89 5.05E.01 3.0SE-01 4.94E-02 8.84E-03 8.84E-03 8.84E-03 1.32E 00 5.11E-02 3.77E-02 3.77E-02 3.77E-02 o { Sr-90 1.06E.04 7.5aE.00 2.19E-01 1.86E+00 1.86E+00 1.66E+00 1.70E+0i 2.29E-01 4.31E.00 4.31E 00 4.31E*00 7" Sr-91 3.97E-01 5.67E-03 2.70E-02 2.29E-04 2.29E-04 2.29E-04 2.40E-02 5.30E-02 9.06E-04 9.06E-04 9.06E-04 Sr-92 1.13E-01 2.15E-03 4.26E-02 9.30E-05 9.30E-05 4.30E-05 9.03E-03 1.71E-01 3.62E-04 3.625-04 3.62E-04 ~ I% Y-90 2.67E.00 9.62E-06 1.02E-01 2.5SE-07 2.58E-07 2.58E-07 4.11E-05 1.17E-01 1.10E-06 1.10E-06 1.10E-06 % Y-91 5.86E.01 1.41E-04 7.76E-02 3.77E-06 3.77E-06 3.77E-06 6.02E-04 8.02E-02 1.61E-05 1.61E-05 1.61E-05
- - ~ _ - - O Di
S YABtE 2.I (2 of 4) h DOSE COMM11 MENT FACTORS-(REM /MICROCl)
HALF-LIFE y NUCLIDE (DAY 3) ADutT CHitD 80EE CI TRACT THYR 0!D TOTAL BODY LIVER BOAE O! TRACT THYROID TOTAL 800Y LIVER T-91R 3.45E-02 9.09E-08 2.67E-07 3.52E-09 3.52E-09 3.52E-09 3.82E-07 7.48E-04 1.39E-08 1.39E-08 1.39E-08 g Y-92 1.48E-01 1.48E-02 2.47E-08 2.47E-08 2.47E-06 2.47E-08 3.60E-06 1.04E-01 1.03E-07 1.03E-07 1.03E-07 a Y-93 4.21E-01 2.68E-06 8.50E-02 7.40E-08 7.40E-08 7.40E-08 1.14E-05 1.10E-01 3.13E-07 3.13E-07 3.13E-07 2r-95 6.40E.01 3.04T-05 3.09E-02 6.60E-06 6.60E-06 9.75E-06 1.16E-04 2.66E-02 2.27E-05 2.27E-05 2.55E-05 ,g Zr-97 7.00E-01 1.68E-06 1.05E-01 1.55E-07 1.55E-07 3.39E-07 6.99E-06 1.53E-01 5.%E-07 5.%E-07 1.01E-06 x at>-95 3.50E.00 6.22E-06 2.10E-02 1.86E-06 1.86E-06 3.46E-06 2.2SE-05 1.62E-02 E.26E-06 6.26E-06 8.76E-06 4 95m 3.61E.00 5.95E-07 2.43E-02 2.54E-07 2.54E-07 4.63E-07 5.95E-07 2.43E-02 2.54E-07 2.54E-07 4.63E-07 Nt>-97 5.llE-02 1.56E-05 1.43E-03 7.85E-07 2.90E-05 1.62E-05 1.56E-05 1.43E-03 7.65E-07 2.90E-05 1.62E-05 4 97m 6.25E-04 3.48E-07 2.71E-05 3.12E-08 6.28E-07 4.73E-07 3.48E-07 2.71E-05 3.12E-08 6.28E-07 4.73E-07 Mo-99 2.75E.00 8.20E-04 9.99E-03 8.20E-04 8.20E-04 4.31E-03 3.29E-03 1.10E-02 3.29E-03 3.29E-03 1.33E-02 Tc-99 7.77E.07 4.10E-04 3.20E-03 1.41E-02 2.14E-04 6.28E-04 4.10E-04 3.20E-03 1.41E-02 2.14E-04 6.28E-04 l Tc-99m 2.51E-01 2.47E-07 4.13E-04 8.89E-06 8.89E-06 6.98E-07 9.23E-07 1.03E-03 3.00E-05 3.00E-05 1.81E-06 Au-103 3.94E.01 1.85E-04 2.16E-02 7.97E-05 7.97E-05 7.97E-05 7.31E-04 1.89E-02 2.81E-04 2.81E-04 2.81E-04 l As-105 1.85E-01 1.54E-05 9.42E-03 6.08E-06 6.08E-06 6.08E-06 6.45E-05 4.21E-02 2.34E-05 ?.34E-05 2.34E-05 l au-106 3.68E.02 2.75E-03 1.78E-01 3.48E-04 3.48E-04 3.48E-04 1.17E-02 1.82E-01 1.46E-03 1.46E-03 1.46E-03 Rh103sn 3.89E-02 4.05E-08 9.27E-05 1.58E-08 8.%E-07 2.21E-08 4.05E-08 9.27E-05 1.58E-08 8.%E-07 2.21E-08 ah-105 1.48E.00 5.6SE-05 1.41E-02 1.30E-05 1.02E-04 3.35E-05 5.68E-05 1.41E-02 1.30E-05 1.02E-04 3.35E-05 Rh105m 4.40E-04 2.72E-08 7.78E-06 4.91E-09 6.34E-08 2.00E-08 2.72E-08 7.78E-06 4.91E-09 6.34E-08 2.00E-08 ah 106 3.46E-04 1.86E-08 7.20E-05 2.80E-09 1.89E-07 3.57E-08 1.86E-08 7.20E-05 2.80E-09 1.89E-07 3.57E-08 l Agilen 2.52E.02 1.6CE-04 6.04E-02 8.79E-05 9.79E-05 1.48E-04 5.39E-04 4.33E-02 2.91E-04 2.91E-04 3.64E-04 l Ag-113 7.47E 00 5.65E-05 4.85E-02 1.26E-05 1.26E-05 2.46E-05 5.65E-05 4.85E-02 1.26E-05 1.26E-05 2.46E-05 5t>-122 2.72E.00 2.29E-04 6.47E-02 3. lie-06 6.70E-05 4.51E-06 2.29E-04 6.47E-02 3.IIE-06 6.70E-05 4.51E-06 56-124 6.02E.01 2.75E-03 9.70E-02 7.14E-06 1.16E-03 5.47E-07 2.75E-03 9.70E-02 7.14E-06 1.16E-03 5.47E-07 i 5b-127 3.80E.00 5.'4E-04 7.00E-02 1.19E-04 6.13E-04 2.95E-04 5.45E-04 7.00E-02 1.19E-04 6.13E-04 2.95E-04 f. Te125m 5.80E.01 2.69E-03 1.07E-02 8.06E-04 3.59E-04 8.71E-04 1.14E-02 1.10E-02 3.20E-03 1.52E-03 3.09E-03 y Te-127 3.92E-01 1.10E-04 8.68E-03 8.15E-05 2.38E-05 3.95E-05 4.71E-04 1.84E-02 3.26E-04 1.01E-04 1.27E-04 aao Te127m 1.09E.02 6.77E-03 2.27E-02 1.73E-03 8.25E-04 2.42E-03 2.89E-02 2.34E-02 6.91E-03 3.43E-03 7.78E-03 Te-129 4.86E-02 3.14E-05 2.37E-05 2.41E-05 7.65E-06 1.18E-05 1.34E-03 8.34E-03 9.54 -0 5 3.18E-05 3.74E-05 gag i Tel2tn 3.34E 01 1.15E-02 5.79E-02 3.95E-03 1.82E-03 4.29E-03 4.87E-02 5.94E-02 1.57E-02 7.56E-03 1.36E-02 3, :4 l Te-131m 1.25E.00 1.73E-03 8.40E-02 1.34E-03 7.05E-04 8.46E-04 7.20E-03 1.01E-01 5.12E-03 2.65E-03 2.49E-03 gm l Te-131 1.74E-02 1.97E-05 2.79E-06 1.62E-05 6.22E-06 8.23E-06 8.30E-05 4.36E-04 6.35E-05 2.47E-05 2.53E-05 [ [ Te-132 3.25E.OD 2.52E-03 7.71E-02 1.80E-03 1.53E-03 1.63E-03 1.01E-02 4.50E-02 5.51E-03 5.40E-03 4.47E-03 4 C 1-129 5.80E.09 9.42E-04 7.84E-05 7.ECE 00 3.18E-03 7.24E-04 9.42E-04 7.84E-05 7.80E+00 3.18E-03 7.24E-04 0 I ~ 1-130 5.15E-01 7.56E-04 1.92E-03 1.89E-01 8.80E-04 2.23E-03 2.92E-03 2.76E-03 6.50E-01 3.04E-04 5.902-03 I-131 8.04E.00 4.16E-03 1.57E-03 1.95E.00 3.41E-03 5.95E-03 1.72E-02 1.54E-03 5.72E.00 9.83E-03 1.73E-02 i: a = _ _ _ _, _
1 o TABtE 2.1 (3 of 4) h OOSE COMM11 MENT FACIORS-(REM /MICROCI) o PALF-LIFE h IIUCLIDE (OAYS) ADutT CHItD e+ IKAE Cl TRAC 7 INTR 0!D TOTAL BODY LIVER BONE GI TRACT THYROID TOTAL 80DY LIVER n 1-132 9.54E-02 2.03E-04 1.02E-04 1.90E-02 1.90E-04 5.43E-04 8.00E-04 1.73E-03 6.82E-02 6.76E-04 1.47E-03 E I-133 8.67E-01 1.42E-03 2.22E-03 3.63E-01 7.53E-04 2.47E-03 5.92E-03 2.95E-03 1.36E+00 2.77E-03 7.32E-03 e". I-134 3.65E-02 1.06E-04 2.51E-07 4.99E-03 1.03E-04 2.88E-04 4.19E-04 5.16E-04 1.79E-02 3.58E-04 7.78E-04 I-135 2.74E-01 4.43E-04 1.31E-03 7.65E-02 4.28E-04 1.16E-03 1.75E-03 2.40E-03 2.19E-01 1.49E-03 3.15E-03 E Ie133m 2.19E+00 0.00E+00 2.45E-02 0.00E+00 0.00E+00 0.00E+00 0.00E.00 2.45E-02 0.00E+00 0.00E+00 0.00E+00 E Ie-133 5.25E.00 0.00E 00 2.5SE-02 0.00E 00 0.00E+00 0.00E+00 0.00E 00 2.58E-02 0.00E+00 0.00E+00 0.00E+00 Iel35m 1.06E CZ 0.00E+00 3.29E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.29E-04 0.00E+00 0.00E+00 0.00E+00 Ie-135 3.79E-01 0.0CE 00 1.00E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-02 0.00E+00 0.00E+00 0.00E+00 Cs-134 7.53E+02 6.22E-02 2.59E-03 1.21E-01 1.21E-01 1.48E-01 2.34E-01 2.07E-03 8.10E-02 8.10E-02 3.84E-01 Cs-135 8.40E.08 1.30E-02 5.35E-04 1.13E-02 6.61E-03 1.12E-02 1.30E-02 5.35E-04 1.13E-02 6.61E-03 1.12E-02 Cs-136 1.31E+01 6.51E-03 2.92E-03 1.85E-02 1.85E-02 2.57E-02 2.35E-02 2.27E-03 4.18E-02 4.18E-02 6.46E-02 Cs-137 1.10E 04 7.97E-02 2.11E-03 7.14E-02 7.14E-02 1.09E-01 3.27E-01 1.%E-03 4.62E-02 4.62E-02 3.13E-01 Cs-138 2.24E-02 5.52E-02 4.65E-10 5.40E-05 5.40E-05 1.09E-04 2.28E-04 1.46E-04 2.01E-04 2.01E-04 3.17E-04 Sal 37m 1.77E-03 2.93E-07 2.87E-05 4.07E-C3 5.12E-07 5.29E-07 2.93E-07 2.87E-05 4.07E-08 5.12E-07 5.29E-07 Ba-141 5.78E-02 9.70E-05 1.72E-04 2.84E-06 2.84E-06 6.91E-08 4.14E-04 2.39E-02 1.20E-05 1.20E-05 2.21E-07 Sa-140 1.28E 01 2.03E-02 4.18E-02 1.33E-03 1.33E-03 2.55E-05 8.31E-02 4.21E-02 4.85E-03 4.85E-03 7.28E-05 Sa-141 1.26E-02 4.71E-05 2.22E-14 1.59E-06 1.59E-06 3.56E-08 2.00E-04 1.14E-04 6.51E-06 6.51E-06 1.12E-07 Sa-142 7.43E-03 2.13E-0> 3.00E-23 1.34E-06 1.34E-06 2.19E-08 8.74E-05 1.14E-06 4.88E-06 4.88E-06 6.29E-08 La-140 1.68E 00 2.50E-06 9.25E-02 3.33E-07 3.33E-07 1.26E-06 1.01E-05 9.84E-02 1.19E-06 1.19E-06 3.53E-06 La-142 6.42E-02 1.28E-07 4.25E-04 1.45E-08 1.45E-08 5.82E-08 5.24E-07 3.31E-02 5.23E-08 5.23E-08 1.67E-07 Ce-141 3.25E.01 9.36E-06 2.42E-02 7.18E-07 7.lSE-07 6.33E-06 3.97E-05 2.47E-02 2.94E-06 2.94E-06 1.98E-05 Ce-143 1.39E 00 1.65E-06 4.56E-02 1.35E-07 1.35E-07 1.22E-03 6.99E-06 5.55E-02 5.49E-07 5.49E-07 3.79E-03 Ce-144 2.84E 02 4.68E-04 1.65E-01 2.62E-05 2.62E-05 2.04E-04 2.08E-03 1.70E-01 1.11E-04 1.81E-04 6.52E-04 8. Pr-143 1.36E.01 9.20E-06 4.03E-02 4.56E-07 4.56E-07 3.69E-06 3.93E-05 4.24E-02 1.95E-06 1.95E-06 1.18E-05 Pr-!44 1.20E-02 3.01E-08 4.33E-15 1.53E-09 1.53E-09 1.2SE-08 1.29E-07 8.59E-05 6.49E-09 6.49E-09 3.99E-08 m 'o m I Pr144s 5.00E-03 8.86E-08 5.69E-04 5.14E-09 3.29E-06 9.58E-08 8.86E-08 5.69E-44 5.14E-09 3.29E-05 9.58E-08 E$$ hd-147 1.10E 01 6.29E-06 3.49E-02 4.35E-07 4.35E-07 7.27E-06 2.79E-05 3.58E-02 1.75E-06 1.75E-06 2.26E-05 E*o h 147 9.57E 02 2.87E-05 1.17E-02 5.38E-07 5.02E-05 1.02E-04 2.87E-05 1.17E-02 5.38E-07 5.02E-05 1.02E-04 E$E h 149 2.21E.00 1.53E-06 4.85E-02 1.24E-07 1.24E-07 2.50E-07 1.53E-06 4.85E-02 1.24E-07 1.24E-07 2.50E-07 "o* $m-147 3.94E.13 3.20E-01 4.26E-02 1.18E-03 2.98E-02 2.20E-01 3.20E-01 4.26E-02 1.18E-03 2.98E-02 2.20E-01 5m-151 3.37E 04 6.87E-05 4.85E-03 2.84E-06 2.84E-06 1.18E-05 6.87E-05 4.85E-03 2.84E-06 2.84E-06 1.18E-05 U Sm-153 1.95E 00 7.90E-07 2.43E-02 6.13E-08 6.13E-08 7.61E-07 7.90E-07 2.43E-02 6.13E-08 6.13E-08 7.61E-07 C Es-155 1.74E 03 4.63E-05 9.70E-03 5.26E-06 5.26E-06 1.08-05 4.63E-05 9.70E-03 5.26E-06 5.I6E-06 1.08E-05 y Ta-182 1.15E.02 1.72E-05 4.85E-02 8.75E-06 8.75E-06 6.37E-05 1.72E-05 4.85E-02 8.75E-06 8.75E-06 6.37E-05 i k. w- -
l TABLE 2.1 (4 of 4) _,{ DOSE COMMIIMENT FAC10RS-(REP /M7 CROCI) I cf HALF-LIFE MUCLICE (DAYS) ADUti child E BONE GI TRACT THYROID TOTAL 800Y LIVER 80t;E GI TRACT' THYR 010 TOTAL BODY LIVER i 16187 9.96E-01 1.03E-04 2.82E-02 3.01E-05 3.01E-05 8.61E-05 4.7 E-04 3.57E-02 1.14E-04 1.14E-04 2.54E-04 Er Pb-210 8.14E+03 2.10E+01 2.03E-02 3.00E-01 1.70E+00 1.40E*00 2.10E+01 2.03E-02 3.00E-OI 1.70E+00 1.40E*00 Pb-212 4.43E-01 1.20E-01 7.57E-02 5.22E-04 2.57E-03 5.85E-03 1.20E-01 7.57E-02 5.22E-04 2.57E-03 5.85E-03 l Pb-214 1.86E-02 3.03E-04 3.14E-03 1.18E-OS 5.64E-05 2.97E-05 3.03E-04 3.14E-03 1.lBE-05 5.64E-05 2.97E-05 l o Si-212 4.21E-02 3.03E-04 5.90E-03 4 97E-05 1.26E-04 7.24E-05 3.03E-04 5.90E-03 4.97E-05 1.26E-04 7.24E-05 3. 81-214 1.38E-02 4.144-05 3.18E-03 5.l!E-06 2.97E-05 1.58E-05 4.16E-05 3.18E-93 5.11E-06 2.97E-05 1.58E-05 t l Po-212 3.50E-12 1.50E-33 9.17E-13 3.48E-34 1.%E-15 1.08E-33 1.50E-33 9.17E-13 3.48E-34 1.%E-15 1.08E-33 P M I4 1.89E-09 4.80E-12 4.28E-10 1.01E-14 1.30E-12 3.35E-13 4.60E-12 4.28E-10 7.01E-14 1.30E-12 3.35E-13 Po-216 1.74E-06 9.35E-07 3.68E-07 3.11E-09 1.85E-09 7.39E-08 9.35E-07 3.68E-07 3.11E-09 1.8SE-08 7.39E-08 Po-219 2.12E-03 9.60E-05 6.84E-04 1.64E-06 8.62E-06 1.llE-05 9.60E-05 6.84E-04 1.64E-96 8.62E-06 1.11E-09 l Ra-224 3.66E+00 3.30E+00 6.60E-01 8.32E-02 7.47E-02 8.90E-02 3.30E+00 6.60E-01 8.32E-02 7.47E-02 8.90E-02 Ra-226 5.84E+05 4.30E.01 3.30E-01 5.90E-01 3.40E*00 5.90E-01 4.30E+01 3.30E-01 5.90E-01 3.40E+00 5.90E-01 Ra-228 2.10E 93 2.10E 01 7.14E-02 4 00E-01 1.70E+00 4.00E-01 2.10E*01 7.14E-02 4.00E-01 1.70E+00 4.00E-01 Ac-228 2.55E-01 3.42E-03 8.07E-03 6.13E-06 1.99E-04 3.54E-04 3 48E-03 8.07E-03 6.13E-06 1.99E-04 3.54E-04 Tb222 6.98E+02 4.10E 00 4.70E-01 7.42E-03 2.80E-02 2.34E-02 4.10E+00 4.70E-01 7.42E-03 3.80E-02 2.34E.02 lb230 2.81E+07 1.60E+01 1.80E-Ol 4.56E-03 9.24E-02 2.18E-02 1.60E+01 1.80E-01 4.56E-03 9.24E-02 2.18E-02 lb232 5.11E,12 1.80E+0i 1.50E-01 3.94E-03 9.63E.92 1.68E-02 1.80E+01 1.50E-01 3.94E-03 9.63E-02 1.88E-02 l Tb234 2.41E*01 4.91E-05 1.60E-01 1.60E-06 6.39E-04 1.46E-05 4.91E-05 1.60E-01 1.60E-06 6.39E-04 1.46E-05 Pa-224 2.79E-01 3.00E-04 1.11E-02 7.20E 06 3.12E-04 2.28E-04 3.00E-04 1.11E-02 7.20E-06 3.12E-04 2.28E-04 U-234 8.9 %C7 3.10E 01 1.80E-01 6.32E-02 2.30E 00 6.32E-02 3.10E+01 1.80E-01 6.32E-02 2.30E+00 6.32E-02 t!-238 1.63E+12 2.80E.01 1.70E-01 5.63E-02 2.00E+00 5.35E-02 2.80E*01 1.70E-01 5.63E.02 2.00E+00 5.35E-02 mp-238 2.12E+00 4.42E-03 3.21E-02 1.22E-05 4.03E-04 1.06E-03 4.42E-03 3.21E-02 1.22E-05 4.03E-04 1.08E-03 W 2.352+00 1.19E-06 2.40E-02 6.45E--08 6.45E-08 1.17E-07 5.25E-06 2.79E-02 2.65E-07 2.6SE-07 3.77F-07 Pu-238 3.20E*04 2.10E.00 2.10E-01 3.23E-03 2.83E-42 4.40E-01 2.10E.00 2.10E-01 3.23E-03 2.83E-02 4.40E-01 l ,l Pu-239
8. DOE +06 2.60E+00 2.00E-01 3.63E-03 3.13E-C2 4.90E-01 2.60E+00 2.00E-01 3.63E-03 3.13E-02 4.90E-01 Pu-240 2.39E+06 2.60E+00 2.00E-01 3.62E-03 3.13E-01 4.90E-01 2.60E+00 2.00E-01 3.62E-03 3.13E-02 4.90E-01 E$$

o m ca Pu-241 5.37E 03 4.83E-02 9.92E-04 7.49E-05 6.19E-04 9.50E-03 4.83E-02 9.92E-04 7.49E-05 6.19E-04 9.50E-03 E*o Pu-242 1.37E+08 2.60E+00 1.90E-01 3.45E-03 2.98E-02 4.70E-01 2.60E+00 1.90E-01 3.45E-03 2.98E-02 4.70E-01 7$E An-241 1.58E 05 8.00E+01 2.10E-01 1.20E-01 1.00E+00 1.70E+01 8.00E+01 2.10E 41 1.20E-01 1.00E+00 1.70E+01 Am.242 6.68E-01 5.19E-03 9.26E-03 1.06E-05 1.44E-04 1.51E-03 5.19E-03 9.26E-03 1.06E-05 1.44E-04 1.51E-03 o"
o An-243 2.69E 06 8.50E+01 2.20E-01 1.30E-Cl 1.00E+00 1.70E+01 8.50E+01 2.20E-01 1.30E-01 1.00E+00 1.70E+01 U Os-242 1.63E+02 1.50E 00 2.30E-01 2.72E-03 0.58E-02
4. ".0E-01 1.50E+00 2.30E.01 2.72E 03 2.58E-02 4.40E-01 Co-243 1.04E+04 4.8C31 2.50E-01 8.22E-02 7.10E-01 1.20E+01 6.00E+03 1.00E+03 1.CIE+03 2.01E+03 1.00E+03 0 cm.244 6.61E+03 3.80E+01 2.20E-01 6.40E-02 5.60E-01 9.30E+00 3.80E+01 2.20E-01 6.40E-02 5.60E-01 9.30E-00
Dose factors were tairen from the following references in order of preference:
1 Regulatory Guide 1.109, ushRC, Obtaber 1977 2. NUREG/CR-0150, D. E. Dunning, O*EL, October 1981 3. ORut-4992, G. G. Killough and L. R. McKay, m rch 1976 1 $ m.
SQN ODCM t Page 91 of 117 I a Revision 20 Table 2.2 (1 of 2) 1 FISH CONCENTRATION FACTORS
i NUCLIDE NUCLIDE NUCLIDE i
r H-3 9.00E-01 Tc-99m 1.50E+01 Ce-144 1.00E+00 C-14 4.60E+03 RJ-103 1.00E+01 Pr-143 2.50E+01 4 l Na-22 1.00E+02 Ru-105 1.00E+01 Pr-144 2.50E+01 t i Na-24 1.00E+02 Ru 106
1. C.SE + 01 Pr-144m 2.30E+01 t
P-32 3.00E+03 Rh-103m 1.00E+01 Nd-147 2.50E+01 Cr-51 ,2.00E+02 Rh-105 1.00E+01 Pm-147 2.50E+01 ( Mn-54 4.00E+02 Rh-105m 1.00E+01 Pm-149 2.50E+01 Mn-56 4.00E+02 Rh-105 1.00E+01 Sm-147 2.50E+01 Fe-55 1.00E+02 Ag-110m 2.31E+00 Sm-151 2.50E+01 3 Fe-59 1.00E+02 Ag-111 2.31E+00 Sm-153 2.50E+01 Co-57 5.00E+01 Sb-122 1.00E+00 Eu-155 2.50E+01 i Co-58 5.00E+01 Sb-124 1,00E+00 Ta-181 3.00E+04 Co-60 5.00E+01 Sb-127 1.00E+00 W-187 1.20E+03 j N1-63 1.00E+02 Te-125m 4.00E+02 Pr-210 3.00E+02 Ni-65 1.00E+02 Te-127 4.00E+02 Pb-212 3.00E+02 Cu-64 5.00E+01 Te-127m 4.00E+02 Pb-214 3.00E-02 2n-65 2.00E+03 Te-129 4.00E+02 Bi-212 1.50E+01 Zn-69 2.00E+03 Te-129m 4.00E+02 Bi-214 1.50E+01 As-74 1.00E+02 Te-131 4.00E+02 Po-212 5.^0E+01 t As-76 1.00'.+02 Te-131m 4.00E+02 Po-214 5.00E+01 l Br-83 4.20E+02 Te-132 4.00E+02 Po-216 5.00E+01 Br-84 4.20E+02 I-129 1.50E+01 Po-218 5.00E+01 L Be-85 4.20E+02 1-130 1.50E+01 Ra-224 5.00E+01 i ) Kr-83m 1.00E+00 I-131 1.50E+01 Ra-226 5.00E+01 i Kr-85m 1.00E+00 I-132 1.50E+01 Ra-228 5.00E+01 l Kr-85 1.00E+00 1-133 1.50E+01 Ac-228 2.50E+01 2 Rb-86 2.00E+03 I-134 1.50E+01 Th-223 3.00E+01 Rb-88 2.00E+03 I-135 1.50E+01 Th-230 3.00E+01 i Rb-89 2.0CE+03 Xe-133m 1.00E+0J Th-232 3.00E+01 i { Sr-89 3.00E+01 Xe-133 1.00E+00 Th-234 3.00E+01 Sr-90 3.00E+01 Xe-135m 1.00E+00 Pa-234 1.10E+01 Sr-91 3.00E+01 Xe-133 1.00E+00 U-234 1.00Et01 Sr-92 3.00E+01 Cs-134 2.00E+03 U-238 1.00E+01 t Y-90 2.50E+01 Cs-135 2.00E+03 NP-238 1.00E+01 Y-91 2.50E+01 Cs-136 2.00E+03 Np-239 1.00E+01 Y-91u 2.50E+01 Cs-137 2.00E+03 Pu-238 3.50E+02 Y-92 2.50E+01 Co-138 2.00E+03 Pu-239 3.50E+02 Y-93 2.50E+01 Ba-137m 4.00E+00 Pu-240 3.50E+02 Zr-95 3.33E+00 Ba-139 4.00E+00 Pu-241 3.50E+02 1 Zr-97 3.33E+00 Ba-140 4.00E+00 Pu-242 3.50E+02 Nb-95 3.00E+04 Ba-141 4.00E+00 Am-241 2.50E+01 Hb-95m 3.00E+04 Ba-142 4.00E+00 Am-247 2.50E+01 Hb-97 3.00E+04 La-140 2.50E+01 Am-243 2.50E+01 i O i t
Numbering change only 1157c j
f N;'
SQH ODCM Page 92 of 117 Revision 20 -a cm / \\ 'Gl Table 2.2 (2 of 2) FISH CONCENTRATION FACTORS * !NCLIDE INCLIDE !NCLIDE Nb-97m 3.00E+04 La-142 2.50E+01 Cc-242 2.50E+01 Mo-99 1.00E+01 Ce-141 1.00E+00 cm-243 2.50E+01 Tc-99 1.50E+01 Cc-143 1.00E+00 cm-244 2.50E+01
The source for the fish concentretion factors, given in order of preference ist NUREG/CR-1336, "The Bioaccumulation Factor for Phosphorus-32 in Fdible Fish Tissue," B. Kahn and K. S. Turgeon, Georgia Institute of Technology, March 1980.
Regulatory Guide 1.109, October 1977. ) \\,/ UCRL-50564, "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," S. E. Thompson, et al. ; Lawrence Livermore Laboratory, October 1972. UCRL-50163, "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices: IV. Handbook for Estimating the Maximum Internal Dose from Radionuclides Released to the Biosphere," Y. C. Ug, et al.; Lavrence Livermore Laboratory, May 1968. Regulatory Guide 1.109, Draf*., Marcy 1976. TVA generated numbers for noble gases. aNumbering change only 1157c .r
x u- ~$ 5 .,y TA8tE 2.3 (1 of 4) RECREATION 005E FACTORS S g EJCEICE %I".HMG 5HOREIINE g (MREM / YEAR PER UCI/ML) (MRIM/ YEAR PER UCI/ SQUARE CENTIMETER) BONE GI TRACT THTR010 18 tlVER SKIN BONE GI 1RACT THYROID 18 flVER SKIN D H-3 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E+00 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E 00 M C-14 0.00E.00 0.COE.00 0.00E.00 0.00E+00 0.00E.00 0.00E+00 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E 00 0.00E.00 Ma-22 3.14E.07 2.49E.07 2.30E.01 2.67E.07 2.27E.07 3.16E.07 2.76E.06 2.19E.06 2.01E.06 2.33E.M 1.99E+06 2.76E+06 Ma-24 5.66E.07 5.92E+07 6.22E.07 5.39E+07 4.80E.07 6.16E+07 3.96E.06 4.10E.06 4.28E.06 3.76E.06 3.33E+06 4.29E.06 P-32 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E+00 0.00E.00 0.00E.00 0.00E.00 0.00E 00 0.00E.00 0.00E.00 0.00E.00 Cr-51 5.43E+05 3.07E+05 3.38E.05 3.ME.05 3.09E.05 4.56E.05 5.45E.04 3.08E.04 3.39E.04 3.81E.04 3.10E.04 4.69E.04 Ma-54 1.16E.07 8.57E.06 7.35E+06 9.6BE.06 8.2tE+07 1.24E+06 1.04E.05 7.69E.05 6.60E.05 8.63E.05 7.42E+05 1.11E.06 th-56 2.33E.07 2.14E 07 1.82E.07 2.07E.07 1.81E.07 2.54E+07 1.88E.06 1.69E+06 1.44E.06 1.66E.06 1.45E.06 2.05E.06 Fe-55 3.16E.01 3.47E.Cl 6.94E.00 1.68E+04 1.47E-01 3.16E+03 2.71E.01 2.98E.01 5.96E.00 1.44E.02 1.26E-01 2.71E+03 Fe-59 1.64E.07 1.38E.07 1.23E+07 1.45E+07 1.23E+07 1.76E+07 1.36E+C6 1.15E.06 1.02E.06 1.20E+06 1.02E+C6 1.46E*06 Co-57 2.71E.06 9.80E.05 1.69E 06 1.48E+C6 1.13E.06 1.75E+06 2.82E+05 1.02E.05 1.76E+05 1.55E.05 1.17E.05 1.94E.05 Co-58 1.3aE.07 1.03E*07 8.7&E+06 1.13E.07 9.68E+06 1.43E.07 1.25E 06 9.36E+03 8.00E+05 1.03E.06 8.82E 05 1.30E+06 Co40 3.46E+07 3.02E.07 2.73E+07 3.11E 07 2.62E 07 3.67E.07 2.83E.06 2.46E.06 2.23E+06 2.54E.06 2.14E.06 3.00E.06 Ni43 0.00E+00 0.00E.0c 0.00E+00 0.00E.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E.00 0.00E.00 Ni45 7.65E.06 6.86E 05 6.50E.06 6.94E+06 5.84E+06 7.93E+06 6.18E.05 5.52E+05 5.22E 05 5.60E+05 4.71E.05 6.41E.05 Cu44 2.83E*06 2.20E.06 1.85E.06 2.23E 06 1.92E+06 2.67E+06 2.11E 05 2.11E.05 1.78E+05 2.14E+05 1.84E.05 2.59E+05 Za45 7.99E.06 6.49E+06 5.58E.06 6.96E.06 5.90E.06 8.67E.06 6.75E.05 5.48E.05 4.71E+05 5.88E.95 4.98E.05 7.40E.05 2n49 9.55E.01 6.49E.01 6.09E 01 7.12E+01 6.00E.01 8.51E.01 9.40E 00 6.39E 00 6.00F+00 7.01E.00 5.90E 00 8.38E+00 As-74 1.70E.05 1.30E*05 1.40E.05 1.40E.05 1.10E+05 1.60E+05 1.36E.06 1.10E.06 1.!6E+C6 1.12E.06 9.40E.05 1.33E.06 As-76 8.31E+04 6.68E*04 7.04E.04 6.83E+04 5.73E+04 8.12f.04 6.82E.05 5.48E.05 5.7AE+03 5.60E.05 4.70E 05 6.66E 05 I: Br-83 1.12E.05 8.64E.04 7.24E.04 8.81E+04 7.59E.04 1.06E.05 1.07E.04 8.29E.03 6.95E.03 8.45E.03 7.28E.03 1.02E+04 m.o u2 i Br-84 2.46E.07 2.42E.07 2.59E.07 2.2SE.07 2.03Ee07 2.69E.07 1.80E 06 1.73E+06 1.79E.06 1.65E.06 1.46E+06 1.96E.06 E$$ Br-85 2.86E.05 2.;1E+05 1.81E 05 2.39E.05 2.04E+05 3.07E+05 2.55E.04 1.88E.04 1.61E+04 2.13E+04 1.82E.04 2.74E.04 E*o Kr-43m 5.24E.02 1.22E*02 1.22E.02 9.46E.02 3.71E.01 1.13E 04 4.33E.02 1.18E.02 5.97E.01 9.66E.02 1.12E 01 1.23E.04 788 Kr45m 3.21E.06 1.36E,06 1.97E+06 1.93E.06 1.50E+06 2.30E.06 3.30E.05 1.39E.05 2.02E.05 1.99E+05 1.54E.05 2.39Fe05 3 o i Kr-85 3.34E*04 2.59E.04 2.17E+04 2.62E.04 2.26E 04 3.14E 04 3.22E.03 2.49E.03 2.09E+03 2.53E.03 2.18E+03 3.03E 03 ( RS-46 1.29E.06 1.04E 06 L 73E+05 1.12E.06 9.50E.05 1.42E.06 1.10E.05 8.79E.04 7.40E+04 9.50E +')4 8.06E 04 1.20E.05 C l Rb-88 4.99E+C6 9.16E.06 8.10E.06 8.32E+06 7.33E,06 9.90E+06 6.77E.05 6.82E.05 5.97E+05 6.24E+05 5.49E*05 7.46E+05 U Rd-89 2.89E.07 2.67E.07 2.41E+07 2.61E.07 2.27E.07 3.17E+07 2.27E.06 2.06E+06 1.85E+06 2.04E.06 !.77E+06 2.49E.06 U Br-89 1.88E,03 1.41E.03 1.18E.03 1.58E.03 1.35E.03 2.05E 03 1.66E+02 1.24E.02 1.04E.02 1.40E.02 1.19E.02 1.81E+02 $r-90 0.00E 00 0.00E.00 0.0CE.00 0.00E+00 0.00E+00 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E+00 0.00E.00 l ir-91 9.71E.06 7.32E+06 6.32E.06 8.17E.06 6.96E.06 1.04E*07 8.56E+05 6.43E 05 5.56E+05 7.19E.05 6.13E.05 9.13E 05 $r-92 1.86E.07 1.68E.07 1.59E 07 1.70E+07 1.43E+07 1.93E 07 1.50E.05 1.35E+06 1.28E 06 1.37E.06 1,15E*06 1.55E.06 Y-90 1.10E+00 2.90E-01 0.11E-01 1.32E+00 2.77E-02 1.06E+01 7.97E-01 2.17E-01 7.68E-02 9.65E-01 1.91E-02 7.87E+00 T-91 4.93E.04 8.25E+04 3.77E.04 4.43E.04 3.75E+04 5.33E 04 4.12E+03 3.51E.03 3.11E.03 3.66E.03 3.10E.03 4.41E.03
s
E lier a
TABLE 2.3 (2 of 4) y RECREATIGN COLE FACIORS g. NUCt1DE SWIMMIM 5HOREtIt.E g (SEM/ TEAR PER UCI/ML) (MEM/YEr2 PER UCI/5QUARE CENTIMETER) SGhE 01 TRACT THYR 010 18 LIVER SKIN BOtaE GI TRACT THYR 0!D TB LIVER SKIN Y-91M 7.83E.06 6.02E.M 5.06E 06 6.21E.06 5.34E.06 7.53E+06 7.48E 05 5.74E.05 4.83E.05 5.93E+05 5.10E+05 7.20E+05 S Y-92 3.51E.06 2.80E.06 2.49E.06 3.02E.06 2.57E.06 3.72E+C6 3.02E 05 2.39E 05 2.12E.05 2.5'fE.05 2.20E.05 3.19E.05 E Y.93 1.30E.M 1.10E 00 9.91E.05 1.10E.06 9.42E.05 1.33E 06 1.10E.05 8.91E.04 8.170+04 9.13E.04 7.77E.04 1.10E+05 Zr-95 1.04E.07 7.78E.06 6.64E.06 8.5EE.06 7.32E.06 1.08E+07 9.56~+05 7.13E 05 6.08E*05 7.84E+05 6.71E+05 9.68E*05 Zr-97 2.57E.06 2.04E 06 1.87E.06 2.18E*06 1.86E+06 2.62E+06 2.23E+05 1.74E 03 1.60E.05 1.88E 05 1.60E+05 2.27E,05 E95 1.OnE 07 8.01E.06 6.8 ".E.06 S.87E+06 7.59E 06 1.12E 07 9.82E.05 7.31E+05 6.24E+05 8.09E+05 6.92E.05 1.02E+06 E 95m 1.11t 06 5.59E+05 7.04E.05 7.59E.05 5.90E.05 9.51E.05 1.22E+05 5.66E.04 7.17E.04 8.05E+04 5.98E+04 1.23E+05 h97 9.40E.06 7.11E.06 6.03E.M I.61E+06 6.52E.06 9.43E.06 8.77E.05 6.63E+05 5.62E+05 7.10E+05 6.08E+05 8.79E+05 E 97m 1.03E.07 7.67E.06 6.54E.06 8.44E-06 7.22E 06 1.06E.07 9.42E.05 7.03E.05 5.99E+05 7.73E+05 6.(.1E+05 9.74E+05 h 99 2.41E.06 3.63E.06 1.52E.06 1.87E+06 1.57E.06 2.34E+06 2.27E.05 1.51E.05 1.43E+05 1.75E.05 1.47E+05 2.21E+05 Tc-99 0.0CE 00 0.00E.00 0.00Es00 0.0CE.00 0.00t.03 0.00E 00 0.00E,00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 2.74E.06 1.03E.06 1.69E.06 1.55E.M 1.18E+06 1.83E+06 2.83E+05 1.07E.05 1.74E 05 1.60E.05 1.21E.05 1.93E+05 Ra-103 7.C5E.06 5.44E.06 4.57E.06 5.51E.06 4.75E.06 6.60E+06 6.81E.05 5.2SE.05 4.41E+05 5.32E.05 4.58E+05 6.37E+05 Tc-99 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E 00 0.00E.00 0.00E.00 0.00E+00 0.00E+00 0.00E+00 0.00E.00 0.00E+00 Tc-99e 2.74E.06 1.03E.06 1.69E.M 1.55E.06 1.18E.06 1.83E.06 2.83E+05 1.07E+05 1.74E+05 1.60E.06 1.21E.05 1.93E+05 Re-103 7.05E.06 5.44E.06 4.57E.06 5.51E.06 4.75E.06 6.60E.06 6.81E.05 5.25E.05 4.41E+05 5.32E 05 4.58E+05 6.37E+05 l Ra-105 1.15E.07 8.32E.06 7 34E.M 9.16E*M 7.79E.M 1.14E.07 1.08E.06 7.76E.05 6.88E+05 8.57E.05 7.29E.05 1.06Ee06 l Ra-105 0.00E.00 0.00E.00 0.00E.00 0.00E.00 0.00E+00 0.00E+00 0.00E.00 0.00E+00 0.00E+00 0.00E+00 0.00E 00 0.00E+00 Rh103n 3.73E.03 4.88E.C2 1.27E+03 2.82E*03 3.92E.02 1.27E+04 1.74E.03 2.10E+02 5.66E.02 1.36E.03 1.63E.02 6.42E+03 h 105 1.35E.06 7.56E.05 8.33E.05 9.39E.05 7.64E.05 1.12E+06 1.36E 05 7.59E.04 8.41E+04 9.43E.04 7.67E.04 1.13E+05 8-Rn105m 6.12E.05 2.18E.05 3.75E.05 3.42E.05 2.51E.05 4.51E+05 7.05E*04 2.30E.04 4.10E+04
4. llE.04 2.66E*04 7.39E*04 g*
N 106 2.99E.06 2.30E.06 1.96E 06 2.41E.06 2.07E*06 2.93E.06 2.81E.05 2.16E.05 1.84E+05 2.25E.05 1.94E405 2.74E.05 m m to Ag110m 3.87E.07 2.97E.07 2.58E+07 3.28E.07 2.79E.07 4.03E+07 3.41E 06 2.61E+06 2.35E+06 2.88E.06 2.45E+06 3.55E,06 S 8 J-111 4.03E.05 2.32E.05 2.51E.05 2.6 L OS 2.31E+05 3.39E+05 4.03E+04 2.32E.04 2.51E.04 2.83E*04 2.3tE+04 3.39E.04 m o ) W 122 8.06E.04 6.27E.04 6.58E.04 6.31Ee04 5.26E+04 7.73E+04 6.83E+05 5.31E*05 5.57E.05 5.35E+05 4.46E.05 6.54E+05 oEE W 124 2.61E.07 2.2SE.07 2.67E+07 2.29E.07 1.98E,07 2.71E.07 2.18E 06 1.86E.06 1.69E.06 1.90E.06 1.64Ee% 2.25E+06 o W127 1.01E.07 7.39E.06 6.47E 06 8.03E.M 6.85E+06 9.91E.06 9.52E.05 6.94E+05 6.09E+05 7.55E 05 6.43E,05 9.31E+05 o Te125m 2.47E.05 2.93E.04 1.24E.05 1.35Ee05 4.71E.04 3.39E.05 4.60E.04 9.08E*03 2.32E.04 2.50E.04 8.75E+03 6.29E.04 C Te-127 7.84E.04 5.17E.04 4.98E.04 5.77E.04 4.83E+04 6.8 b 04 7.74E+03.5.10E+03 4.92E+03 5.69E.03 4.77E+03 6.80E+03 C Te127m t.91E.04 1.33E.04 3.45E.04 3.S2E.04 1.2SE.04 9.89E,04 1.31E*04 2.54E.03 6.60E+03 7.21. 03 2.44E.03 1.86E.04 U Te.129 8.68E.05 6.12E.05 5.58E.05 6.69E 05 5.60E+05 8.33E.05 8.52E+04 5.87E*04 5.43E+04 6.50E.C4 5.37E+04 8.28Ee04 Te129m 4.73E.05 3.23E.05 2.94E.05 3.71E*05 3.02E+05 5.03E+05 4.89E+04 3.09E404 2.98Ee04 3.71E+04 2.88E 04 5.38E*04 Te-131 6.7 L 06 4.21E.06 4.37E.06 4.9 L 06 4.13E.06 6.llE.06 6.49E*05 3.94E.05 4.16E+05 4.71E.05 3.68E+05 5.78E+05 Te131m 2.06E.07 1.53E.07 1.39E.07 1.70E.07 1.4 L O7 2.12E.07 1.84E+06 1.35E.06 1.23E+06 1.51E.05 1.28E.06 1.89E+06 Te-132 4.27E.06 1.92E.06 2.54E.06 2.6SE.06 2.04E 06 3.32E+06 4.55E 05 1.98E+05 2.68E+05 2.83E.05 2.12E+05 3.60E 05 I-129 2.25E.05 4.84E.04 1.19E.05 1.15E.05. 75E+04 2.4 L OS 5.02E+04 1.0 L O4 2.6 L O4 2.57E,04 1.05E 04 5.70E.04
m (m a ti .si TABt E 2.3 (3 of 4) .s RECREAI!ON DOSE FAC10R5 I h NUCLIE*_ 5' frMING SHORELINE 4 (PREM/ YEAR PER UCI/ML) (MREM / YEAR PER UCl/ SQUARE CENilMETER) S 80bE GI TRACT THYROID 18 LIVER SKIN B0tJE G1 TRACT THYR 010 T8 LIVER SKIN o I-130 3.09E.07 2.34E+07 2.00E*07 2.50E+07 2.14E+07 3.08E+07 2.88E.06 2.17E*06 1.865 06 2.32E 06 1.99E+06 2.86E+06 3 I-131 6.22E +M 3.93E+06 3.92E.06 4.54E.06 3.77E*06 5.47E+06 6.16E+05 3.87E+05 3.88E+05 4.49E.05 3.72E+05 5.41E+05 I-132 3.23E 07 2.45E+07 2.16E 07 2.68E+07 2.29E 07 3.32E+07 2.91E.06 2.20E+06 1.93E.06 2.41E.06 2.06E+06 2.99E*06 I-133 8.96E+06 6.90E 06 5.89E+06 7.18E+06 6.16E+06 8.69E+06 8.44E.05 6.49E 05 5.54E+05 6.75E+05 5.79E 05 8.17E*05 j I-134 3.67E.07 2.84E.07 2.49E.07
3. IIE+07 2.65E+07 3.89E*07 3.22E.06 2.46E+06 2.16E+06 2.71E+06 2.32E 06 3.40E+06 4
I-135 2.19E.07 1.95E+07 1.75E 07 1.96E.07 1.67E+07 2.33E+07 1.78E+06 1.57E+06 1.41E+06 1.58E +M 1.35E+06 1.89E+06 Re133m 6.0$E+05 2.38E.05 3.55E 05 3.71E+05 2.61E+05 5.27E+05 8.09E.04 2.810 04 4.65E+04 4.77E*04 3.05E+04 7.71E*04 Ie-133 8.52E.05 2.53E 05 4.84E*05 4.24E.05 2.74E.05 5.73E+05 1.11E+05 3.17E+04 6.28E+04 5.57E 04 3.39E+04 8.27E+04 Xel25m 6.41E 06 4.94E.06 4.15E 06 5.04E+06 4.33E+M 6.08E+06 6.21E 05 4.75E.05 4.01E.05 4.87E.05 4.17E+05 5.90E+05 j xel35 4.54E.M 2.28E+06 2.76E.06 3.0ZE.C6 2.40E+06 3.63E+06 4.59E+05 2.29E.05 2.79E+05 3.04E+05 2.41E+05 3.67E+05 Cs-134 2.22E+07 1.67E.07 1.43E+07 1.81E.07 1.55E.07 2.26E+07 2.04E*06 1.54E+06 1.32E+06 1.67E+06 1.43E+06 2.08E+06 Cs-135 0.00E.00 0.00E+00 0.00E.00 0.00E 00 0.00E.00 0.00E*00 0.00E+00 0.00E+00 0.00E 00 0.00E+00 0.00E+00 0.00E+00 Cs-136 3.10E.07 2.26E.07 2.03E*07 2.55E+07 2.15E+07 3.21E+07 2.77E+06 2.00E+06 1.81E 06 2.26E+06 1.91E+06 2.85E+06 Cs-137 0.00E 00 0.00E+00 0.00E.00 0.0CE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E.00 0.00E+00 0.00E+00 Cs-138 3.29E.07 3.03E.07 2.86E.07 2.98E*C7 2.56E.07 3.46E+07 2.62E+06 2.37E+0b 2.23E.06 2.35E+06 2.02E+06 2.74E+06 Bal37m 8.56E.06 6.45E.06 5.4SE+06 6.92E+M 5.93E+06 8.59E+06 8.01E+05 6.02E+05 5.12E+05 6.47E 05 5.54E+05 8.04E+05 8a-139 7.49E.05 3.44E+45 4.73E*05 4.66E+05 3.60E.05 5.55E+05 7.61E+04 3.38E+04 4.75E+04 4.67E.04 3.57E+04 5.52E+04 8a-140 2.29E.06 M 3E.06 1.46E 06 1.73E.06 1.46E+06 2.10E+06 2.29E+05 1.56E+05 1.46E+05 1.71E+05 1.42E+05 2.13E+05 Ba-141 1.31E.07 3.90E.06 8.96E.06 1.02E+07 8.49E.06 1.22E+07 1.21E*06 7.97E+05 8.15E+05 9.26E+05 7.70E.05 1.12E*M Ba-142 1.51E.07 1.11E+07 1.02E.07 1.24E.07 1.04E+07 1.54E+07 1.34E*06 9.38E+05 9.03E+05 1.10E+06 9.17E+05 1.36E 4 { La-140 3.20E+07 2.91E.07 2.73E+07 2.68E*07 2.46E+07 3.31E.07 2.60E+06 2.32E 4 2.18E+06 2.32E 06 1.98E.06 2.67E+06 La-142 3.74E.07 3.80E+07 3.72E 07 3.47E.07 3.10E 07 4.10E.07 2.75E*M 2.73E+06 2.64E+06 2.53E+06 2.52E+06 3.00E 06 72$ Ce-141 1.59E.06 5.94E 05 9.70E+05 9.01E+05 6.75E+05 1.09E*06 1.69E*05 6.20E.04 1.02E 05 9.52E+04 7.07E+04 1.16E+05 .1 % 2 Cc-143 4.54E.05 2.64E+06 2.79E 06 3.22E+06 2.60E*06 4.00E*06 4.E6E+05 2.61E*05 2.83E+05 3.24E+05 2.57E 4 4.07E+05 La-142 3.74E 07 3.80E+07 3.72E 07 3.47E 07 3.10E*07 4.10E 07 2.75E+06 2.73E+06 2.64E+06 2.53E,06 2.52E+C6 3.00E+06 @"Q Cc-141 1.59E 06 5.94E.05 9.70E.05 9.0!E.05 6.75E+05 1.07E*06 1.69E,05 6.20E.04 1.02E.05 9.52E*04 7.07E+04 1.16E+05 uQ Ce-143 4.54E 05 2.64E*06 2.79E.06 3.22E+06 2.6CE+06 4.00E+06 4.66E+05 2.61E+05 2.83E+05 3.24E 05 2.57E.05 4.07E+05 0 Ce-144 4.18E+05 1.42E.05 2.51E.05 2.26E+05 1.63E+05 2.81E 05 4.64E+04 1.55E+04 2.76E.04 2.50E.04 1.76E+04 3.18E+04 'j Pr-143 1.26E-01 9.30E-02 8.00E-02 1.03E-01 8.83E-02 1.30E-01 1.15E-02 8.60E-03 7.33E-03 9.45E.03 8.09E-03 1.19E-02 U Pr-144 4.40E-05 4.24E+05 3.74E 05 3.97E+05 3.50E+05 4.75E,05 3.46E+04 3.24E+04 2.87E.04 3.10E+04 2.72E+04 3.11E+04
f PrI44M 1.42E+05 3.32E 04 7.19E.04 6.95E+04 3.23E+04 1.25E+05 2.23E.04 5.33E+03 1.15E+04 1.12E+04 5.lTE.03 2.06E+04 4 147 2.33E.06 1.34E.06 1.44E+M 1.57E+06 1.25E+06 1.93E 06 2.47E+05 1.35E 05 1.50E.05 1.62E+05 1.27E+05 2.03E+05 4 147 7.86E.01 2.76E.01 4.92E 01 4.26E.01 3.23E+01 4.93E+01 8.17E.00 2.92E 00 5.11E 00 4.43E+00 3.36E.00 5.17E 00 4 149 1.93E.05 1.12E.05 1.23E 05 1.39E+05 1.13E*05 1.69E.05 1.98E*04 1.11E+04 1.22E+04 1.38E+04 1.12E.04 1.67E*04 5m.147 0.00E.00 0.00E.00 0.00E.00 0.00E*00 0.00E 00 0.00E do 0.00E+00 0.00E.00 0.00E.00 0.00E+00 0.00E.00 0.00E 00 i
5 s.151 1.69E.01 2.20E+00 5.68E+00 1.33E+01 1.61E.00 6.78E+01 7.60E+00 1.04E.00 2.56E+00 6.24E.00 7.22E-01 3.55E+01 l
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N ubering change only 1157c l
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SQH ODCM Page 97 of 117 Revision 20 e Table 2.4 PUBLIC WATER SUPPLY INFORMATION* 2020 153 F_0_PULATION WATER SUPPLY 484.5 Sequoyah Nuclear Plant 473.0 2000 ICI America Inc. 473.0 900 C. F. Industries q 470.5 4000 E. I. duPont, Co. 465.3 610700 Chattanooga 418.0 4400 South Pittsburg 413.6 3400 Bridgeport 407.6 500 Widows Creek Steam Plant 405.2 500 Mead Paper Board 392.0 Bellefonte Nuclear Plant 385.8 96700 Scottsboro 382.1 18600 Sand Mountain Water Authority i 36A.2 125 Christian Youth Camp 358.0 14900 Guntersville 334.5 4500 NE Morgan County Water and Fire 334.2 168600 Huntsville 330.2 10000 Redstone Arsenal ) 324.2 Redstone Arsenal j 306.0 84600 Decatur 294.0 Browns Ferry Nuclear Plant i 253.0 500 U. S. Plywood-Champion Paper k 274.9 50 Wheeler Das ] 259.6 14,100 Muscle Shoals i 259.5 2,700 TVA-NFDC ) 254.3 21.100 Sheffield 245.0 $20 Colbert steam Plant 239.3 3,900 Cherokee 238.7 350 U.S. Steet Agri-Chemicals, Inco l l 217.4 1 Yellow Creek Nuclear Plant ) 206.8 2,400 Hardin Co. Water District l 193.5 1,900 Tri-County Utility District l 158.0 1,100 Clif.on 101.9 170 Foote Mineral Co. ) 100.5 6,100 New Johnsonville [ j 100.4 13,300 Camden 1 100.0 375 Johnsonville Steam Plant ] 98.5 900 E. I. Dupont Company 95.5 700 Consolidated Aluminum Corporation l 2 94.5 250 Inland Container Corporation j 79.5 120 Bass Bay Resort j 39.3 4,300 Jonathan Creek Water District ] 28.5 9,100 North Marshall Water District 1 23.6 650 Grand Rivers 17.8 600 B. F. Goodrich Chemical Co. t 17.4 lof Airco Carbide E6.8 592 Airco A11oya i 16.7 510 Air Products and Chemicals 1.1 69,800 Paducah i I l
From TVA Tater Quality Branch, updated December 1979 I
4 i 8Hxnbering chance only 1157c F
SQN ODCM Page 98 of 117 -- Revision 20 Table 2.5 TISH HARVEST DATA RIVER SPAN NAME OF REACH _f_IJJLJIARVEST (LBS/YR) (TRM) _ SPORT
G.QMMERCI AL*

484.5 - 471.0 Chickamauga Lake below SQN 5.4E+05 2.0E+05 471.0 - 452.0 Nickajack Lake (Part 1 of 2) 1.2E+05 4.6E+04 452.0 - 424.7 Nickajack Lake (Part 2 of 2) 2.9E+05 1.1E+05 424.7 - 417.5 Guntersville Lake (Part 1 of 4) 2.6E+05 9.5E+04 417.5 - 392.0 Guntersville Lake above BLN 5.2E+05 1.9E+05 392.0 - 373.0 Guntersville Lakebelow BLN 7.8E+05 2.9E+05 373.0 - 349.0 Guntersville Lake (Part 4 of 4) 1.0Et06 3.8E+05 349.0 - 294.0 Wheeler Lake above BTN 1.0E+06 3.8E+05 294.0 - 274.9 Wheeler Lake below BTN 1.5E+06 5.7E+05 274.9 - 259.4 Wilson Lake 5.9E+05 2.2E+05 259.4 - 217.4 Pickwick Lake above YCN 1.3E+06 4.9E+05 217.4 - 206.7 Pickwick Lake below YCN 3.3E+05 1.2E+05 206.7 - 165.0 Kentucky Lake (Part 1 of 4) 6.1E+05 2.3E+05 165.0 - 121.0 Kentucky Lake (Part 2 of 4) 6.1E+05 2.3E+05 121.0 - 76.0 Kentucky Lake (Part 3 of 4) 1.8E+06 6.8E+05 76.0 - 22.4 Kentucky Lake (Part 4 of 4) 3.1E+06 1.1E+06 l

Derived from "Situation Assessment and Planning Assumptions," Division of Forestry, Fisheries, and Wildlife TVA, December 1978.
Derived from "Estimated Commercial Fish and Mussel Harvest from the Tennessee Valley," Tisherier and Aquatic Eaology Branch, TVA, 1980.
1 i i l a i a i l i l ) l a I I i
Numbering change only 1157c
SQN ODCM Page 99 of 117 - Revision 20 l Table 2.6 RECREATION USAGE DATA
i RIVER SPAN NAME OF REACH HOU_RS OF USAGE PER YEAR I
(TRM) EHORELINE - __ ABOVE-WATfJL, IN WATER 484.5 - 471.0 Chickamauga Lake below SQN 5.$E+06 1.0E+06 4.9E+06 i i 471.0 - 452.0 Nickajack Lake (Part 1 of 2) 1.2E+05 2.5E+04 1.1E+05 l 452.0 - 424.7 Nickajack Lake (Part 2 of 2) 2.0E+05 4.0E+04 1.8E+05 i s 424.7 - 417.5 Guntersville Lake (Part 1 of 4) 7.0E+04 1.5E+04 6.0E+04 1 417.5 - 392.0 Guntersville Lake above BLN 5.2E+05 1.0E+05 4.7E+05 l 392.0 - 373.0 Guntersville Lake below BLN 4.7E+06 8.9E+05 4.2E+06 i 2 373.0 - 349.0 Guntersville Lake (Part 4 of 4) 1.1E+07 2.1E+06 9.8E+06 { 349.0 294.C Wheeler Lake above BPN 4.0E+06 7.6E+05 3.6E+06 1 294.0 - 274.9 Wheeler Lake below BPN 5.2E+06 1.0E+06 4.7E+04 l il 274.9 - 259.4 Wilson Lake 3.9E+06 7.4E+05 3.5E+06 l 259.4 - 217.4 Pickwick Lake above YCN 2.0E+06 3.5E+05 2.0E+06 4 217.4 - 206.7 Pickwick Lake below YCN 2.0E+06 4.0E+05 1.8E+06 1 206.7 - 165.0 Kentucky Lake (Part 1 of 4) 6.0E+05 1.2E+05 5.4E+05 ( j 165.0 - 121.0 Kentucky Lake (Part 2 of 4) 1.2E+06 2.3E+05 1.1E+06 } l 121.0 - 76.0 Kentucky Lake (Part 3 of 4) 2.4E+06 4.7E+05 2.2E+06 l l 76.0 - 22.4 Kentucky Lake (Part 4 of 4) 2.6E+07 4.9E+06 2.3E+07 I i, t
Based on "Extent of Recreation Development and Use of WA Lake Frontage i
i Preporty;" (unpublished data fro:t 1974 Annual Recreation Survey); and l l Observations of Recreatien Use of TVA Reservoirs, Division of Reservoir I Properties, Recreation Resources Branch, TVA, 1975. t i a i l l i i i i 4 i I l 1 l i 1 l i i l 1 l 1 l l ( 5 1 h j
Numbering change only 1157c l
l I f
- - - - - ~ ~ fI l I I oz fier TABLE 3.1 (5heet 1 of 4) sg RA010t0GICAL Eantla0NMENTAL MONITORING PROGRAM Emposure Pattway Sampling and Type and Frequency i a and/or Sasqole 5mple tocations* Collection frequency of Analysis
1. AIR 00RNE

a. Particulates 4 s g les from locations Continuous sampler Analyre for gross beta (in different secters) at operation with sample radioactivity > 24 hours M
M o near the site boundary collection once per following filter change. l l (LM 2, 3, 4, and 5) 7 days (more frequently Perform gansma isotopic if required by dust analysis on each sample loading) if gross beta > 10 times yearly mean of control s g le. Composite at least s,nce per 31 drja (by location for gassna scan) < sanpies f;1mm connunities approximately 5-10 miles distance from the plant i I (en 2, 3, s, and 9) l 4 samples from control locations greater than 10 miler from the plant l (RM 1 i 3, and 4)
b. Radiolodine Sarples from same locations Continuous sampler a s al at least once per as air particulates operation with filter 7 days collection once per i
l 7 days l I* b
c. Soil Sa gles from same locations Once per year Gasuna scan. * *5r esir 45 air particulates once each year so.o vi l
e se o
2. DIRECT M DIATION 2 or more enimeters placed Once per 92 days Ganna dose at least 1$
4t 11 of the air particulate Ace per 92 days "y@
sampling stations (LA3, LM-4, o o en LM.S. PS2, Pm3, P4 8, PN 9, 2o2 M.1, AR-2, Am3, and art-4) uo om 2 or more dosimeters placed at each of at least 30 other locations. g (figures 3.1, 3.2, and 3.3) w O
5 ample locations are listed in Tables 3.2 and 3.3 and shown on Figures 3.1, 3.2, and 3.3.
l is ,i .-----_--_---~.-__-_.--,---.----n..,----.----,...---w,- ---.n.
l N e 8 TABLE 3.1 (Sheet 2 of 4) i { E RADIOt0GICAL INVIRONMENTAL MONITORING PROGR M i Esposure Pathway Sarpilog and Type and Freguency g and/or Sanple Sarvle tocations* se Collection Frequency of Analysis i e
3. WATEk80RNE i
n3
a. Surface im 497.0 sequential y automatic Collected b Canna scan of each i
i g" TRM 483.4 type sm pler** composite sample. j 1 2 473.2 alth corrposite sar:ples Compos.te for tritium collected over a period analysis at least of 1 32 days once per 92 days
b. Ground 1 sanple adjacent to At least once per 92 Gross beta, gamma scan plant (location W-6) days and tritium analysis at least once per 92 days I sample from 1,round
?, water source upgradient i J
c. Drinking I smote at the first Collected by automatic Cross beta and gasuna j
potable surface water sequential-type sm pler** scan of each composite supply downstrem from with corposite smpit sample. esite for the plant (T M 473.0) collected over a period tritium,
r W at least of < 31 days once per 92 days i
i I sciple at the next 2 Crab sample once per 31 q do nstrem potable surface days l water suppiters (greater than 10 miles dawnstrem) I (TM 470.5 and 4e5.3) 2 sapp 10s at control 5 apples collected by 8 locations (T M 497.0 automatic sevent'al-( c. and im 503.8) t}pe sappler with composite s q 1e collected over a y7y period of i 31 days <a
c

d. Sediment im 4%.5 At least once per 184 Canns scan of each
--0 Tm 483.4 days sample yoQ y T m 48G.9 TM 412.8 o" % o W 0
smple locations are listed in Tables 3.2 and J.3 and shc.sn on ilgures 3.1, 3.2 and 3.3.
O i
Samples shall be collected by colletting an aliquot at intervals not exceeding E h3urs.
ww O i '-r ~
~f Sz l! I TABLE 3.1 (Sheet 3 of 4) RAD 1010GICAL ENVIR0esMENTAL MON!TORING PROGRAM Esposure Pathway Sanpling and Type and frequency n tr and/or 5 g le Sarple tocations' Collection Frequency of Analysis 5 es
e. Shoreline TRM 485 At least once per 184 G41sna scan of each Sediment 1RM 478 days sample i
o Tiel 4FF u E
4. INGEST!'JII
(
a. Milk i sanple from allk producing At least once per 15 days Gamma isotopic and l
animals in each of 1-3 areas anal analysis of each I indicated by the cow census sample. * *5r. So5r once l where doses are calculated per quarter to be highest. If sapples are not available from a milk animal location, doses ^ to that area m.11 he estimated by projecting the doses from concentrations detected in ellk from other i sectors or by s g ling vegetation where milk is not available (Table 3.1, 4.d) At least I sgle from a control location,
b. Fish 1sgleeachforWictajack, At least once per 184 Ganuma scan on edible i
Chickamauga, and idetts Bar days. One sanple of portica Reservoirs each of the following species: I f. Channel Catfish t Crapple Smallmouth Suffato E2E < so z e o = sample locations are listed in Tables 3.2 and 3.3 sad shown on Figures 3.1, 3.2, and 3.2. pgg awz uo O% W 4 w O 4..
= -. - _.. - - --. ~. ~.... . -... = - _ _ = - -. - ,j l \\ \\v/ O 5 Sea IABLE 3.1 (Sheet 4 of 4) na RADIOLOGICAL EWWIA04=fNTAL MONITORING PROGRAM p I! Exposure Pathway Sanpli and Type and Frequency and/or Sanple sanple locations
Collection requeng of Analysis n
E C. Invertebrates TRM 4%.5 At ' east once per Ganna scan on edible (Asiatic Class) TRM 483.4 184 days. portion 1HM 480.8
d. Food Products 1 sample each of principal At least once per 365 Cama scan on edible food products grown at days at time of portion private gardens and/or harvest. The types farvas in the lasnediate of foods available vicinity of the plent.
for sappling will vary. Following is a list of L typical foods which may be available: Cabbage and/or Lettuce ? Corn Creen Seans Potatoes Tomatoes
e. Vegetation Sanples from the nearby At least once per 31 days I-131 and gauna scan at milk producing farins (Farms least once per 31 days.
J. Hw, H, [M, and Br) and
*5r and

05r from the local air monitor-analysis at least i
ing stations (t N -3, once per 92 days -4, and -5. l Control samples from one rt'iote air monitor (RRA) and one control dairy l 3 farin (Faria 5). ??E l
5 ample locations are IIsted in Tables 3.2 and 3.3 and shown on Figur.s 3.1, 3.2, and 3.3.
15
o o
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SQN ODCM Page 104 of 117 -" Revision 20 <~s '- / TABLE 3.2 (1 of 2) SE000YAi! NUCLEAR PLANT I Environmental Radiological Monitoring Program Sampling Locations 1 f Map Approximate Indicator (I) Location Distance or Samples ] . Number A Station Sector (Miles) Control (C) Gallecte_db r 2 LM-2 N 0.8 I AP, CF, S V 1 3 LM-3 SSW 1.2 I AP, CF, S, V 4 LM-4 NE 1.5 I AP, CF, S, V 5 LM-5 NUL 1.8 I AP, CP, S, V 7 FM-2 SW 3.8 I AP, CF, S 8 FM-3 W 5.6 I AP, CT, S j 9 FM-8 SSW 8.7 I AP, CF, S 10 FM-9 WSW 2.6 I AP, CF, S 11 RM-1 SW 16.7 C AP, CF, S 12 RM-2 NNE 17.8 C AP, CF, S l 13 RM-3 ESE 11.3 C AP, CF, S I j 14 RM-4 '4 N 18.9 C AP, CT, S, V 7 d 15 Tarm B NE 43.0 C M l 16 Farm C NE 16.0 C M j l 11 Tarm S NNE 12.0 C M, V r 18 Tarm J WNW 1.1 I M. V I 3 19 Tarm NW IN 1.2 I M, V, WC 20 Tarm EM N 2.6 I Y 1 21 Tarm Br SSW 2.2 I V 7, 24 Well No. 6 NNE 0.15 I W J 31 TRMd 473.0 11.58 I FW j l (C.F. Industries) i 32 TRM 410.5 14.0e g pg (E.I. DuPont) l 33 TRM 465.3 19.2' I PW (Chattanooga) 12.58 Cf SW l 34 TRM 497.0 35 TRM 503.8 19.38 C PW (Dayton) l 36 TRM 496.5 12.08 C CL, SD 37 TRM 485.0 0.5' C SS i 38 TRM 483.4 1.le I CL, SD, SW 39 TRM 480.8 3.7' I CL,.SD j 40 TRM 477.0 7.58 I SS 41 TRM 473.2 11.38 I SW i 11.7' I SD 42 TRM 472.8 i 44 TRM 478.8 6.5' I SS 1! l 5 i
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. _. -.~ 1 SQN ODCM Page 105 of 117 -+ Revision 20 i f TABLE 3.2 (2 of 2) SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Samplina Locations Map Approximate Indicator (I) Location Distance or Samples Number & Station Sector (Miles) Control (C),, Collectedb i 45 TRM 425-471 7 I (Nickajack Reservoir) 1 46 TRM 471-530 I I (Chickamauga Reservoir) 47 TRM 530-602 C F (Watts Bar Reservoir) f 48 Farm H NE 4.2 I MV
I i
t a. See figures 3.1, 3.2, and 3.3 i b. Sample Codes AP = Air particulate filter CT = Charcoal filter CL = Class F = Tish l M = Milk l PW = Public water i R = Rainwater i S = Soil j SD = Sediment SS = Shoreline sediment SW = Surface water { V = Vegetation j W = Well water i c. A control for well vater. I d. TRM = Tennessee River Mile, e. Distance from plant discharge (TRM 484.5) f. Surface water sample also used as a control for public water.
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SQN ODCM i Page 106 of 117 Revision 20 a l Table 3.3 (1 of 2) SEQUOYAH !NCLEAR PLANT Thermoluminescent Dosimeter Locations i Map Approximate. Onsite (On) i Location Distanew or i Number Eta 11gn terior __(Miles) __ Offsite (Offl [ 3 SSW-1A SSW 1.2 On 4 NE-1A NE 1.5 On 5 NNE-1 NNE 1.8 On i i 7 SW-2 SW 3.4 Off 8 W-3 W 5.6 0ff 9 SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off I 11 SW-3 SW 16.7 off i 12 NNE-4 !CE 17.8 Off j 13 ESE-3 ESE 11.3 Off i 14 WNV-3 WNW 18.9 Off I 49 N-1 N 0.6 On i 50 N-2 N 2.1 Off 1 51 N-3 N 5.2 Off i 52 N-4 N 10.0 Off 53 !CE-2 NNE 4.5 0ff f i 54 NNE-3 NNE 32.1 0ff I 4 55 NE-1 NE 2.4 Off 1 56 NE-2 NE 4.1 Off f j 57 ENE-1 ENE 0.4 On ( { 58 ENE-2 ens 5.1 off 4 59 E-1 E 1.2 On 60 E-2 E 5.2 Off i 61 ESE-A ESE 0.4 On l l 62 ESE-1 ESE 1.2 On l 63 ESE-2 ESE 4.9 Off l l 64 SE-A SE 0,4 On 65 SE-B SE 0.4 On i 66 SE-1 SE 1.4 On L 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off 69 SSE-1 $$E 1.6 On i 70 SSE-2 SSE 4.6 Off l 71 S-1 S 1.5 On i I 72 S-2 3 4.7 off l 73 SSW-1 SSW 0.6 On j 74 SSW-2 SSW 4.0 Off j i i I
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i l SQN ODCM Page 107 of 117 ) Revicion 20 -w ? l Table 3.3 (2 of 2) l SEQUOYAH !WCLEAR PLANT l Thermoluminescent Dostmeter Locations l l j Map Approximate-Onsite (On)a l Location Distance or l 1 _Hmbn, Station Eff,1gI __(Miles L Offsite (Off) l 75 SW-1 SW 0.9 On j 76 WSW-1 WSW 0.9 On 77 WSW-2 WSW 2.5 off 78 WSW-3 WSW 5.7 Off 79 WSW-4 WSW 7.8 Off i 80 WSW-5 WSW 10.1 off j 81 W-1 W 0.8 0n i 82 W-2 W 4.3 Off j 83 h7N-1 h7N 0.4 On 84 WIN-2 h7N 5.3 Off 1 85 !N-1 !N 0.4 On i 86 IN-2 FN 5.2 off j 87 NTN-1 N!N 0.6 On i 88 h7N-2 N!N 1.7 On 89 NtN-3 N?N 5.3 off l t j a. TLDs designated onsite are those located two miles or less from the plant. TLDs designated offsite are those located more than two miles from the plant. t
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1 l SQN ODCM Page 108 of 117 Revision 20 -e Table 3.4 (1 of 2) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,c Airborne Particulate Analysis Water or Cas Fish Milk Food Products Sediment (pC1/L) (pC1/L) (pC1/m3) (pC1/kg, vet) (p41/L) (pC1/ks, vet) (pci/kg.d ry) gross beta 4 1 X 10-2 N.A. N.A. N.A. N.A. H-3 2000 N.A. N.A. N.A. N.A. N.A. Mn-54 15 N.A. 130 N.A. N.A. N.A. Fe-59 30 N.A. 260 N.A. 3.A, N.A. Cc-58,60 15 N.A. 130 N.A. N.A. N.A. 2n-65 30 N.A. 260 N.A. N.A. N.A. Zr-95 30 N.A. N.A. N.A. N 4. N.A. Nb-95 15 N.A. N.A. N.A. N.A. N.A. I-131 lb 7 X 10-2 N.A. 1 60 N.A. Cs-134 15 5 X 10-2 130 15 60 150 Cs-137 18 6 X 10-2 15o 13 go ign Ba-140 60 N.A. M.A. 60 N.A. N.A. La-140 15 N.A. N.A. 15 N.A. N.A. TABLE NOTATION a The LLD is the smallest concentratien of radioactive ma,terial in a sample that will be detected with 95% probability with 51 probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiechemical separation): LLD r 4.66_sb-E V 2.22 Y exp(-14t)
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SQN ODCM Page 109 of 117 Revision 20 (% / ) \\m_ / Table 3.4 (1 of 2) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTIO!I (LLD)a,e TABLE NOTATION (continued) Where LLD is the "a priori" lower limit of detection as defined above (picoeurie per unit mass or volume), e is the standard deviation of the background counting rate or of the s counting rate of a blank sample as appropriate (counts per minute), E is the counting efficiency (counts par transfor=ation), V is the sample size (units of mass or volume), 2.22 is the number of transformations per minute per picoeurie, 4 Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the porticular radionuclide, and 4 1 at le the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not ] ( plant effluent samples). The value of ab used in the calculation of the ILD for a detection system shall be based on the actual observed varitt.ce of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted l variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally presuat in the samples (e.g., potassium-4C in milk samples). Typical valbes of 3 V, Y, and at shall be used in the calculations. D The LLD for analysis of drinking water and surface water eamples shall be performed by garta spectroscopy at approximately 15 pC1/L If levels greater than 15 pC1/L are identified in surface water samples downstream i from the plant, or in the event of an unanticipated release of I-131, drinking vater steples will be analyzed at a LLD of 1.0 pC1/L for I-131. l c Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be ider.tified and reported. l t \\s_ / l
Numbering change only 1157c
SQN ODCM Page 110 of 117 Revision 20 w l Figure 1.1 j SQN LAND SITE BOUNDARY s. I .dhady C i \\. t '.tr. ) %- \\,-l/. i 6 J i y% r ~*. '.j,', 'JNy ' W j.- i l yn ,~ i I l i .':. rew, ce b e. .l[y. t&* i ,..p /
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Page added 1157:
e-4 4 l 3 I SQN ODCM Page 111 of 117 l i Revision 20 i s Tigure 1.2 ~- ) CASE 003 RADVASTE TREATMENT SYSTEM i t CYC5 VCT l j -- Unit t i t2 g V3 CVCS VCT \\ f j Unit 2 / I l CVCSHT) i WCS RCOT I' i _ynit i / .I ] l WCS RCOT Unit 2 [ l ,j Waste Con i Compressor Plont j j Package w ne i j C.CS EVAPS\\ (typlcol of 2) Units 1&2/ I cvessr) f ,_ Hl ( i I l ~M1 M g i l d b i r% e-m e m i Waste Cos Weste Ces Weste ces i Cecoy Tank Cecoy Tonk Decoy Tonk i x, ~) <s, m> i 1 (W W 7) i w* w s w s ) l l l I 4 l 1
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SQN ODCM Page 112 of 117 - Revision 20 Figure 1.3 PLUME DEPLETION EFFECT (CR CROUND LEVEL RELEASES (All Stability Classes) iu. 1.0 i o N f um m ] N t o.s N N l "A oe N 4, 5 l ' N g s t g l k a 07 \\ i h \\ I i os I \\ { g N 4 w N a 0.5 1 5 i N i U o.4 \\ f I o.2 4 i i i ) 0.2 d 'f I o.1 6 1 1 i s' sea me ma PLLMet TRAVEL DISTANC4 (El4 OtNTERG [ f r I r ? I r 1 l 1 i i i i
Entire page changed and rentnbered 1157:
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SQN ODCM Page 113 of 117 Revision 20 kw/ Figure 1.4 Vertical Standard Deviation of Material in a Plu:ne i 1000 .1 l 1 J I I A / / / / ( l / / l l / 2 r / / Y Y a' A r ,r r / / / / / / l f / / y A / / / / ,y i l j j / a ; s / / ~- / y i / ,r r j i / / / / / / ( n_ i / ? / J f l h / / / Of/ f f s -l,l>/ / E,/ / / 1 i e /// // ef / 10 / [ 3>' 1 1 / / s / / / F ^/ / / I / / / / _ / / / \\ 1 / / j / 7 / \\ / 4 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) Vertical Standard Deviation of Material in a Plume (Lettm denote Paequill Stability Claest u O) 1 <V i
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M l SQN ODCM Page 114 or 117 Revision 20 O Figure 1.5 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Clasces) 104 i 1 104 N g ~ i' k y H '% g 5 T< S h w \\ Q z N $ 10-5 G
_x 61 X_
g X 0 N h w a N H N 5 N i 104 ._a 10-7 0.1 1.0 10,0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Entire page changed and renumbered 1157c a....
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SQN ODCM -R slo 20 0\\ Tigure 3.1 Environmental Radiological Sampling Locations Within 1 Milo of Plant 348.75 N i i.2 5 326. 5 33.75 N 2 NE -r 303.7 40 /, 56.25 WNW ENE 281.25 / 78.75 ]YE ) / ) 'N EQUOYAH h,l 7,,, - I W-N R -E g s_ l L\\ 25s.15 / 5 101.25 76 / 64 i WSW M q' I,f[ ESE $5 \\ 2 3 6.2 5' q / 73 4e*g@ 0 s Se Sw 0 4 0 213.75 i 146.25 SS T-SSE i t e 8.7 5 191.25 S 0 ._-__ _._. scale
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SQN ODCM Page 116 of 117 Revision 20 V Figure 3.2 Environmental Radiological Sampling Locations 4 From 1 to 5 Miles From The Plant j 1 r I a 34a.7s N 11.2s i NNW b NNE I [ 33 16 326 25 h l NW p. NE /, 303,75 j 20 48 .$p p/q 56 1 WNW 6L e55 ENE a %v .1 ast as dg p* ',, ra.rs l 82 1 '. /f' O [J oo igg [f W- ,$g -E 10 2 L 26475 77' '.d6 101.26 [ /- 'g 69 7 WSW 0 / ESE s. 23625 g#ej 123.76 l I f7 ,g SW r SE 0h / e70 7,
13.75
.I 72 !?e 25 ) SSW U ~ SSE . g,., 10128 3 104.76 SCALE ./h 0 1 2 uus l i aNu=besitt ehenge only 1157c / .i 1 '^
SQN ODCM Page 117 of 117 - Revision 20 Tigure 3.3 Environmental Radiological Sampling Locations Greater Than 5 Miles From The Plant l ,4 s r*, a 4 ti rs ... p us, ~~ a u / q,.y q" g ww.este 303 IS ! ,t 4 29 4 ...a.y i l / I j h;p's I(./r.s I l .a y >l i)vrY ). i c i i / Y,,a A 1 aur Vi g / l ..i n [ b" s g, N 4 / /j l \\'/. N \\ j n/ \\ 7 ,/ ,n.s j { / u j 'M / K.',,, w isi n p in ts l -- sr m i l 1 j eNu:nbering change only 1157c si ,. _ - ~. _ _ _ _ - -. - -
C0!!CURREllCE S!!EET N DOCUMEtiT fiAMEt,_SIQU.QYA]LJBJCLEAR PLAffT (SON) 0FFSITE DOSE _CALGULATI0tf BAfiUAL _ (ODCM) - REVISIO?i 20 ORIGI!iATIttG ORGAli!ZATIO!is Radiological PrettC_tiCILBunch DOCUMEtiT PREPARED BY: R. M, flicoll ACCESSIO!! !i0. : 141_1101A3_8 39 DATE: C0!!CURREllCES tiame gnature - Comment Date ~ R. M. titco11 7 6th r/wr c c nea-# i i j O i r i I i Ill31ENSTIQii31 1 1. Af ter each individual concurs, check a or b 1
a. forvard to next individual l
b contact this person ext. 2. When concurrences are cceplete, forward to extension 3. Other instructions. A l i i Ak :
.i I O l I I j l l l THIS PAGE INTENTIONALLY LEFT Bl.ANK O 6 l l
y b\\
TENNEGOEE VALLEY AUTHORITY r Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 s b September 13, 1988 a I Nuclear Regulatory Consalssion Office of Management Information and Program control Washington, DC 20555 l Centlement I j Enclosed is the August 1988 Monthly Operating Report to WRC for Sequoyah j Nuclear Plant. l Very truly yours, i TENNESSEE VA!.tEY AUTHORITY h t F. J. Smith j Plant Manager i j 4 Enclosure ec (Enclosura): j Director, Region 11 INPO Records Center Wuclear Regulatory Cottseission Suite 1500 Office of Inspaction and Enforcement 1100 circle 75 Parkway 4 Suite 3100 Atlanta, Georgia 30339 (1 copy) l Atlanta, Georgia 30323 (1 copy) Mr. K. M. Jenison 101 Marietta Street ] i Resident WRC Inspector Deputy Executive Director (4PS-2, Sequoyan Wuclear Plant for Regional Operations ] Wuclear Regulatory Comission Washington, DC 20555 (1 copy) l Director Office of Special Projects j 4350 East West Highway, EW 322 lethesda, Maryland 10814 (1 copy) Mr. T. Marston Electric Power Research Institute P. O. Box 104!2 1 Palo Alto, California 94304 (1 copy) i un t i l l i An Equat Opportunity Employer .}}

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