Text

Monthly Operating Repts for Jan 1983
	ML20071F214
Person / Time
Site:	Sequoyah
Issue date:	02/08/1983
From:	Eddings M, Mason C; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20071F213	List: ML20071F211; ML20071F214;
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	NUDOCS 8303150464
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT I

l MONTHLY OPERATING REPORT 4

JANUARY 1, 1983 - JANUARY 31, 1983 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 i

UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted By:

Power Plant Superintendent 8303150464 830214 DRADOCK05000g

TABLE OF CONTENTS Operations Summary...

1 Significant Operational Events.

1-7 PORV's and Safety Valves Summary.....................

7 Licensee Events and Special Reports 7-8 Offsite Dose Calculation Manual Changes 8

Operating Data Unit 1.

9-11 Unit 2 12-14 Plant Maintenance Summary 15-16

.-Appendix A 17-40 l'

1 i

L

4 Operations Summary January 1983 l

The following summary describes the significant operational activities for the month of January.

In support of this summary, a chronological log of significant events is included in this report.

Unit 1 e

Unit I was critical for 317.95 hours0.0011 days 0.0264 hours 1.570767e-4 weeks 3.61475e-5 months , produced 190,050 MWH (gross),

resulting in an average hourly gross load of 787,609 kW during the month.

There are 282.8 full power days estimated remaining until the end of cycle 2-fuel. With a capacity factor of 85 percent, the target E0C exposure would be reached December 29, 1983. The capacity factor for the month was 22.0 percent.

There were three reactor scrams, no-manual shutdowns, and no power reductions during January. The unit had nine turbine trips during the month.

i i

Unit 2 Unit 2 was critical for 731.22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months , produced 753,910 MWH (gross),

j resulting in an average hourly gross load of 1,082,633 kW during the month.

There are 154.97 full power days estimated' remaining until the end of cycle 1 i

fuel. With a capacity factor of 85 percent the target EOC exposure would be reached August 1, 1983. The capacity factor for the month was 87.1 percent.

There were three reactor scrams, one manual shutdown, and two power reductions during January.

Significant Operational Events 4

Unit 1 Date Time Event 01/01/83 0001 Reactor-in mode 5.

Preparation to enter mode 4 in progress.

1 2340 Reactor entered mode 4.

01/06/83 0350 Reactor entered mode 3.

01/09/83 2300 Due to high seal leakage on reactor coolant pump #1 began cooling down to mode 5 to make the necessary repairs.

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Significant Operational Events Unit 1 i

(Continued)

Date Time Event

-01/10/83 0607 Reactor entered mode 4.

1405 Reactor entered mode 5.

01/15/83 0325 Began heat-up.

1027 Reactor entered mode 4.

2030 Reactor entered mode 3.

01/17/83 2345 Reactor taken critical. Low power physic testing in progress.

01/19/83 1957 Reactor entered mode 1.

2202 Generator tied on-line.

2225-Turbine tripped due to feedwater regulator valve problems.

01/20/83 0032 Generator tied on-line.

0134 Turbine tripped due to feedwater regulator valve problems.

0242 Generator tied on line.

0337 Turbine tripped again due to the feedwater regulator valve problems.

1012 Generator tied on-line.

j 1132 The reactor tripped due to a_ steam flow /feedwater flow mismatch in loop 4.

1658 Reactor taken critical.

2020 Generator tied on-line.

2054 Turbine tripped. Turbine at E 210 MWe.

2058 Reactor tripped. The sense lines to 1-FT-3-35 were found to be con-nected in reverse. ;

Significant Operational Events Unit 1 (Continued)

Date Time Event 01/20/83 2359 Reactor taken critical.

01/21/83-0455 Generator tied on-line.

1245 Reactor at 30% power and holding for the turbine overspeed trip test.

2115' Turbine tripped during overspeed trip test.

01/22/83 0245 Began power ascension.

0530 Reactor at 30% power.

0700 Overspeed trip test complete.

0733 Generator tied on-line and slowly increasing power.

01/23/83 1755 Reactor at 75% power producing 880 MWe and holding for start-up testing and xenon equilibrium.

01/24/83 1210 Reactor at 75% power, 880 MWe, IM's were performing SI-90.1 -

Reactor Trip Instrumentation Monthly Functional Tests - and tripped a Lo-Lo level and a Hi level bi-stable. The unit operator switched to manual level control and as he did the feedwater regulator valve closed causing the level to drop. The reactor tripped on a Lo-Lo level in steam generator

2.

2200 Reactor taken critical.

2320 Reactor entered mode 1.

01/25/83 0013 Generator tied on-line.

0620 Reactor at 30% power, producing 300 MWe and holding for secondary chemistry to come into specifica-tion.

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k a

-Significant Operational Events Unit 1 (Continued)

Date Time Event 01/25/83 1435 Began power ascension.

01/26/83 0700 Reactor at 75% power, producing 880 MWe.

Incore/excore testing in progress.

01/28/83 2337 Began power ascension.

01/29/83 0340 Reactor at 87% power, producing 1020 MWe and' holding due to P250 computer problems.

0747 Began power ascension.

1215 Reactor at 100% power, producing 1170 MWe.

01/31/83 2359 Reactor at 100% power, producing 1170 MWe.

Unit 2 01/01/83 0001 Reactor in mode 1 at 30% power, producing 290 MWe and holding for feedwater chemistry to come into specification.

0800 Began power ascension.

1420 Reactor at 40% power producing 380 MWe and holding while investigating aH leak on the. generator.

2 2244 Began load reduction to repair the H leak on the generator.

2 01/02/83 0034 Unit taken off-line. Reactor in mode 2.

1118 H leak found and repaired.

2 01/03/83 0033 Reactor entered mode 1.

i.

0230 Generator tied on-line.

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Significant Operational Events Unit 2 (Continued)

Date Time Event 01/03/83 0340 Reactor at 29% power, producing 290 MWe when the turbine tripped when the #3 heater drain tank by pass valve failed to open causing the steam and feedwater flows to swing. The reactor tripped on a Lo-Lo level in #4 steam generator.

01/03/83 1107 Reactor taken critical.

1335 Reactor entered mode 1.

1522 Generator tied on-line.

1538 The turbine tripped when the feed-water pressure began to decrease and MFPT 2B didn't increase speed to maintain system pressure when all of a sudden MFPT 2B increased-to maxmum speed causing a Hi-Hi #3 steam generator level. 'The reactor was reduced to 2% power.

~

1613 Generator tied on-line.

1635 While increasing load, MFPT 2B regulator controller did not-respond to the increase when all' at once MFPT 2B did pick-up over-pressuring the feedwater system.

The turbine tripped on a Hi-Hi #3 steam generator level.

1637 Reactor tripped on a Lo-Lo #2 steam generator level.

2021 Reactor taken critical.

2050 Reactor entered mode 1.

Significant Operational Events Unit 2 (Continued).

Date Time Event 01/03/83 2152 Reactor at 22% power, producing 255 MWe. The feedwater had been isolated to #1 steam generator but the steam generator level continued to rise indicating the valves were leaking thru resulting i

in a Hi-Hi steam generator-level in loop #1 which tripped the turbine and MFPT.

2154 Reactor tripped due to Lo-Lo #2 steam generator level.

2330 Reactor taken critical.

01/04/83 0022 Reactor entered mode 1.

0200 Generator tied on-line.

0500 Reactor at 30% power, producing 280 MWe'and holding waiting for feedwater chemisty to come into specifications.

1315_

Began power ascension.

01/05/83 0512 Reactor at 98% power, producing 1150 MWe. Unable to obtain 100%

reactor power because #3 governor valve is closed.

01/07/83 1630 Began power reduction due to high steam generator chemistry.

2130 Reactor at 30% power, producing 290 MWe.

01/08/83 0315 Began power ascension.

1202 Reactor at 97% power, producing 1170 MWe with #3 governor valve closed.

01/13/83 0708 Reactor at 98% power.

Began to reduce power to 90% to perform SI-90.102. -

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Significant Operational Events t

-Unit 2 (Continued)

Date Time

~ Event l

01/13/83 0810

-Reactor at 90% power.

1012

-Began power ascension.

1240 Reactor at 98% power, producing 1160 MWe'.

01/27/83 0118 The turbine ran back to 70% due to the #3 heater drain tank pressure was swinging resulting from an erratic level controller j

on 2C heater.

0250 Began power ascension.

0700

- Reactor at 98% power, producing -

1160 MWe.

01/31/83 2359 Reactor in mode 1 at 98% power, producing 1163 MWe.

PORV's and Safety Valves Summary No-PORV's or safety valves were challenged during the month.

J 4

Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during January 1983,

. to the Assistant Director of Nuclear Power (Operations) for reporting to the

-Nuclear Regulatory Commission.

i Unit 1 LER SUBJECT i

SQR0-50-327/82143 The oxygen concentration in the waste gas decay tanks exceeded allowable limits.

SQRO-50-327/82144 The auxiliary building rad monitor RM-90-101 e

failed due to loss of flow.

i

~ SQRO-5-327/82145 ESF containment ventilation isolation failed due to the slave relay latch mechanisms not i

i latching. 1 4

f

I Licensee Events and Special Reports (Continued)

Unit 1 LER SUBJECT SQR0-50-327/83001 During the performance of SI-112, the pressurizer safety valve 68-565 failed to. lift within the setpoint limits.

Unit 2 SQRO-50-328/82142 Containment isolation valve 2-FCV-68-305 failed to open due to a ruptured diaphragm.

Special Reports There were two special reports transmitted during the month of January.

83-01 Diesel Generator Report 83-02 Inoperable Fire Damper for more than 7 days.

Offsite Dose Calculation Manual Changes Changes in the Sequoyah Nuclear Plant ODCM are described in this section in accordance with Sequoyah Technical Specification 6.14.2.

These changes were officially approved by RARC on October 21, 1982.

See Appendix _A at the end of this report for the approved ODCM changes.

1.--

i OPERATING DATA REPORT DOCKET NO. 50-327 DATE FEBRUARY 8, 1983 COMPLETED BY M G EDDINGS TELEPHONE (615) 751-0421 OPERATING STATUS 1.

UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1

NOTES:

2.

REPORT PERIOD: JANUARY 1983

3. LICENSED THERMAL POWER (MWT):

3411.0 4.

NAMEPLATE RATING (GROSS MWE):

1220.6

.5.

DESIGN ELECTRICAL RATING (NET MWE):

1148.0 a

6.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

1163.0

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1128.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:____________

_=--

9.

POWER LEVEL TO WHICH RESTRICTED.IF ANY(NET MWE):___--

10. REASONS FOR RESTRICTIONS,IF ANY:____________-_________-

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 744.00 13921.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 317.95 317.95 7853.65

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 241.30 241.30 7560.80

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 589085.17 589085.17 23871827.17

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 190050.00 190050.00 7947586.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 177017.00 177017.00 7613021.00

19. UNIT SERVICE FACTOR 32.43 32.43 54.31

20. UNIT AVAILABILITY FACTOR 32.43 32.43 54.31

21. UNIT CAPACITY FACTOR (USING MDC NET) 21.09 21.09 48.48 j

22. UNIT CAPACITY FACTOR (USING DER NET) 20.73 20.73 47.64 L

23. UNIT FORCED OUTAGE PATE 67.11 67.11 21.57

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

- _ = -

25. IF-S5UTDOWA 5T 5UD 5F REPORi PERI 35! EEiiREVEE 5EiE 5F EiEEIUPI~~~~

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NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-327 UNIT one DATE-February 8, 1983 COMPLETED BY M. Eddings TELEPHONE (615) 751-0343 MONTH January DAY AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 Unit Don Unit Down 17 2

Unit Don ig Unit Down 3

Unit Down 19 0

4 Unit Down 20 0

5 Unit Down 21 377 6

Unit Down 22 623 7

Unit Do" 23 649 8

Unit Dom 24 413 9

Unit Down 313 25 10 Unit Don 800 26 11 Unit Don 27 836 12 Unit Down 28 835 13 Unit Dow 29 1,041 14 Unit Don 30 1,130 15 Unit Don 31 1,132 16 Unit Down INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

(9/77)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-327 UNIT NAME Seauoyah one DATE January 1983 COMPLETED BY M. Eddings REPORT MONTH January 1983 TELEPHONE (615) 751-0341 S

W O

@g c ge tj Licensee y

Cause & Corrective No.

Date g,

Og 8

'g t g Event 8%

Action to y

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fy*

Report !

g'8 R~g Prevent Recurrence E"

$N$

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1 83/01/01 F

454 C*

4

Refueling Outage Exceeded Scheduled Time Limit TVA Changed This To A Forced Outage At 2400C 12/31/82.

2 83/01/19 F

0,8 A

9 Turbine Trip Hi-Hi Level on #1 S/G.

3 83/01/19 F

1.0 A

9 Turbine Trip Hi-Hi Level on #3 S/G.

I C

4 83/01/20 F

1.1 A

9 Turbine Trip Hi-Hi Level on #1 S/G.

i 5

83/01/20 F

6.6 A

9 Turbine Trip Hi-Hi Level on #2 S/G.

6 83/01/20 F

8.8 A

3

4 Loop Steam Flow /Feedwater Flow Mismatch.

7 83/01/20 F

8.0 A

3 Turbine Trip #1 S/G Hi Level Rx Trip 12 S/G Lo-Lo Level.

8 83/01/21 S

10.3 B

9 Turbine Overspeed Trip Test.

9 83/01/24 F

12.1 A

3 Lo-Lo Level #2 S/G, 1

2 3

4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5

(9/77)

H-Other (Explain)

Exhibit. I-Same Source i

OPERATING DATA REPORT DOCKET NO. 50-328 DATE FEBRUARY 8, 1983 COMPLETED BY D C DUPREE TELEPHONE (615) 751-0421 OPERATING STATUS 1.

UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2

NOTES:

2. REPORT PERIOD: JANUARY 1983 3.-LICENSED THERMAL POWER (MWT):

3411.0 4.

NAMEPLATE RATING (GROSS MWE):

1220.6

5. DESIGN ELECTRICAL RATING (NET MWE):

1148.0 6.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

1163.0 7.

MAXIMUM DEPENDABLE' CAPACITY (NET MWE):

1128.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:

_ _ _ _ _ _ _ _ _ _ =

=

9.

POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):________

i I

10. REASONS FOR' RESTRICTIONS,IF ANY:_______________________

THIS MONTH YR.-TO-DATE CUMULATIVE l

11. HOURS-IN REPORTING PERIOD 744.00 744.00 5881.00

-1:2. NUMBER OF HOURS REACTOR WAS CRITICAL 731.22 731.22 4619.92

13. REACTOR RESERVE SHUTDOWN HOURS.

0.00 0.00 0.00-

14. HOURS GENERATOR ON-LINE 696.40 696.40 4503.15

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 2203657.44 2203657.44 1435S248.24 17.. GROSS ELECTRICAL ENERGY GEN. (MWH) 753910.00 753910.00 4835760.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 725157.00 725157.00

~4651447.60

19. UNIT SERVICE FACTOR 93.60 93.60 76.57

20. UNIT AVAILABILITY FACTOR 93.60 93.60 76.57

21. UNIT CAPACITY FACTOR (USING MDC NET) 86.41 86.41 70.12

22. UNIT CAPACITY FACTOR (USING DER NET) 84.90 84.90 68.90

23. UNIT FORCED OUTAGE RATE 6.40 6.40 15.40

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

=.

= - _ _ _

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

NOTE'THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.

4 !

_~

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-328 UNIT Two DATE February 4, 1983 COMPLETED BY David Dupree" TELEPHONE (615) 751-0421 MONTH January DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 307 1,113 37 1,114 2

60 18 3

10 1,114 39 4

397 20

-1,026 5

1,092 21 959 1,114 6

1,104 22 7

969 23 1'I17 1,116 8

859 24 l'Il7 9

1,106 25 10 1,110 26 1,115 11 1,115 27 1,074 1, 16 12 1,114 28 1'119 13 1,097 29-1,121 14 1,112 30 1,122 15 1,112 31 16 1,110 INSTRUCTIONS On this format, list the average daily unit power 1cvel in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

(9/77) t

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-328 UNIT NAME Seanovah Two DATE January 1983 COMPLETED BY David Dupree REPORT MONTH January 1983 TELEPHONE (615) 751-0421 W

O

@g c gc tj Licensee tj Cause & Corrective No.

Date E

O$

'g O @

Event g%

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5y*

Report #

g'8 g'g Prevent Recurrence

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e 1

83/01/02 F

25.93 B

1 Manual shutdown. Repair hydrogen leak on the generator.

2 83/01/03 F

11.7 A

3 Turbine Trip: Hi-Hi #3 S/G Level. During Start-Up Rx Trip: Lo-Lo #4 S/G.

3 83/01/03 F

.58 A

9 Turbine Trip: Hi-Hi # S/G Level During Start-

{

Up.

Reduced reactor power to 2%.

4 83/01/03 F

9.42 A

3 Turbine Trip during startup, Hi-Hi #2 S/G 1evel. Rx Trip: Lo-Lo #2 S/G.

5 83/01/07 F

0 F

5 S/G Chemistry out of specification, reduce load to 30%.

6 83/01/27 F

0 A

5 Turbine run back to 70% due to the level swinging in #3 heater drain tank.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5

(9/77)

H-Other (Explain)

Exhibit I-Same Source 7

k Plant Maintenance Summary The following significant maintenance items were completed during the month of January 1983:

Mechanical Maintenance 1.

Boric acid evaporator pumps 1-PMP-65-165 and -168 were replaced.

. Reactor coolant pump 1-PMP-68-008 number 2 seal was replaced.

2.

3.

A new shaft was fabricated and installed on'ERCW valve 1-FCV-67-67.

Electrical Maintenance 1.

Installation of dimension 2000 telephone system continued.

-2.

Repaired the Unit I hydrogen recombiner.

Instrument Maintenance

~

There were no significant maintenance items.

3 Field Services Group ECN-5200--Post-Accident Sampling Facility Tubing and hanger work is in progress in the Unit 1 annulus. The core drilling for the installation of the heating ventilation and i

air conditioning duct is in progress in the auxiliary building.

The installation of sampling panels is in progress.

ECN 5608--Pressurizer Enclosure Manway All work is completed on Unit 1.

The fabrication of the manway for Unit 2 is completed and will be installed during a Unit 2 outage

- with a sufficient duration.

ECN 5009--ERCW Piping Changeout (Units 1 and 2)

Changeout of carbon steel piping to stainless steel piping for the ERCW system serving Unit I safety-injection pump oil cooler IA-A

- and the safety-injection pump room cooler IA is complete. Final hanger installation and system hydrostatic pressure testing has been completed. Prefabrication of piping is continuing for the Unit 2 penetration room coolers 2A2 and 2B2.

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Field Services Group

-(Continued) 4 ECN 5417--Diesel Generator Air Start System Dryers This modification adds air dryers between the air compressor and the air receiver tanks for each diesel generator engine air start system in order to remove water from the air being supplied to the air start motors.

Work is continuing to modify hangers for the air start system due to the need to install flex piping at the air receiver tanks. The flex hose installation should start late this month.

ECN 5451--Diesel Generator Engine Lube Oil System This modification to the diesel generator engine lube oil systems adds an auxiliary ac lube oil pump and a standby de motor driven lube oil pump in order to prevent bearing damage during multiple hot restarts.

Electrical connection of all de motor-driven lube oil pumps and

. associated pressure switches is nearing completion. Functional testing of these pumps and pressure switches will follow this work.

ECN 5580--Plant Emergency Evacuation System Sirens The installation of conduit, conduit hangers, sirens, and junction boxes has continued during this reporting period. Cable pulling has also started and the installation of transformer has ~also begun.

l-

APPENDIX A DOCUMENTATION FOR ODCM CIIANGES l

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APPENDIX A Change 1 I

Description of Change The following typographical changes were made. No model changes are

. reflected in-these changes, and therefore, no evaluations are necessary.

a.

Page 2, Wind speed class number.8 is added with a range of 8.3-10.9 (m/s).and a midpoint of 9.60 (m/s).

b.

Pages 11-15, Equation reference numbers are changed.

1 Change 2 Description of Change Page 7, The value of Aw is changed from Aw = 0.002 1 h-1 to 0.0023 h~1 for particulates and 0.0017 for iodines.

Analysis or Evaluation Justifying Change

. 0DCM changes reflect the revision in gaseous dose methodology to incorporate NUREG/CR-1004 environmental transfer parameters.

4 Evaluation of Accuracy of Dase Calculation or Setpoint Determination These changes will have no effect on dose calculations for noble gases.

For iodine / particulate dose calculations, the dose from I-131 will be approximately 20 percent lower and 'the dose from' Sr-90 will be approxi-mately 10 times' higher. However, because of the mix of nuclides, the changes'should' effectively cancel each other so that there will be little change in the total dose.

Set points will also be affected. For noble gases the set point will increase approximately 4 percent. For iodine and particulates, the-l set point will increase approximately 18 percent.

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APPENDIX A

~

(Co'ntinued)

Change 3-Description of Change Page 7, the value of Yv, agricultural yield, changed from 1.18 kg/m2 to 0.7 2

kg/m,,

Analysis or Evaluation Justifying Change

- ^

See Change 2.

Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 2.

Change 4

~ Description of Change-iPage 8, Equation (1.8).for determination of concentration of C-14 in vegetation has been omitted.

Analysis or Evaluation Justifying Change

'See Change 2.

Evaluation of Accuracy of Dose Calculation or Setpoint Determination i

See Change 2.

Change 5 Description of Change Page 9, Transport time of activity from feed to milk to receptor has-been changed from two days to one day.

l Analysis' or Evaluation Justifying Change

'See Change 2.

Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 2. '

APPENDIX A (Continued)

Change 6 Description of Change Page 14, The following statements were omitted along with the reference to C-14 in Statement 5.

4.

The highest annual'- average X/Q's based on licensing meterology for ground level releases will be used for C-14 doses.

~8.

Releases of C-14 are based on the design source term.

Analysis or Evaluation Justifying Change See Change 2.

Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 2.

Change 7 Description of Change Page15,Thedefinitionof"DF{31" is changed to read "DF

= I-131 milk ingestion dose factor to infan 7.24x10" mrem /yrperpd2fm-s(Table 1.7)".

2 A new constant 0.9 is the fraction of dose expected to be contributed by I-131. Equation 1.18 then reduces to DTHm$mfy=rper.1*Qpci/d0ls. (As per Regulatory 75 The constant 13 DF is given a new value of 1.36 x 10 Gu5de 1.109 and NUREG/CR-1004 methologies). Equation 1.19 then reduces to DBC = 3511.5 Q. The determination of the thyroid dose from milk ingestion of 6-14 and the, determination of the total thyroid dose are deleted.

Analysis or Evaluation Justifying Change See Change 2.

Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 2. /

APPENDIX A (Continued)

Change 8 Description of Change Table 1.4A reflects the 1982 land-use survey update.

Analysis or Evaluation Justifying Change See Change 2.

Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 2.

Change 9 Description of Change Tables 1.6 and 1.7 have been revised.

Analysis or Evaluation Justifying. Change See Change 2.-

Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 2.

1 v

)

4 5

h e.

APPENDIX A (Continued)

Change 10 Description of Change Pages 21 and 22, Equation 2.11, Factor Ii is replaced by Iij which is defined on page 22 as the monthly activity ingested of the ith radionuclide by the critical age group for the jth organ, pei. The new definition of DCFij is the critical ingestion dose commitment for the jth organ of adult or child from the ith radionuclide rem /pci.

In equation 2.12, factor Vi is replaced by Vij which is defined as the maxi-mum individual's water consumption rate corresponding to the age group selected for the critical DCFij above.

(Adult:

200 mL/d, Child:6y00mL/d; Regulatory Guide 1.109). Equation 2.13 then becmes Dj = 2.15x10 (V x DCF) ij x Ai, rem.

F l

fy Analysis or Evaluation Justifying Change The child age group is included because analysis of past releases indicates that this age group might be the critical age group. The difference in projected doses for the adult and child age group is not large. Doses to the teenager and infant age groups are less than those to the child and adult groups for the significant pathways.

Evaluation of Accuracy of Dose Calculation or Setpoint Determination These changes will serve to improve the accuracy of the calculations. They will also improve the documentation of both the methodology and parameters.

These changes will not affect set point determinations.

Change 11 Description of Change

^

Page 23, factor M in equation 2.14 is replaced by Mij defined as the amount of fish eaten monthly by maximum individual corresponding to age group selected for the critical DCFij above.

(Adult: _8{gg, Child: 575g; Regulatory 17 Guide 1.109). Equation 2.15 becomes Dj = 7.7x10 AiBi (M DCF)ij, mrem.

y F

g=1 Analysis or Evaluation Justifying Change See Change 10.

Evaluation of M.aracy of Dose Calculation or Setpoint Determination See Change 10..

APPENDIX A (Continued)

Change 12 Description of Change Pages 23-27, Section 2.3.3, " Quarterly and Annual Analysis" has been revised as follows:-

2.3.3 Quarterly and Annual Analysis A complete analysis utilizing the total estimated liquid releases for each calendar quarter will 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 will also include an approximation of population doses.

l' b

N f

G 2:3.3.1 Individual Doses th The dose to the the j organ of the maximum individual from m nuclides, D, is described by j

5 m

C D.=

J D.. k.,

rem (2.16)

IJ k=1 i= 1 m

2 5

[(IDCF)ij

=

xI ik] +

[(RDCF)ijk

b ik Tk 4]t (2.17' i=1 k=1 k=3 where:

th th D

=

ijk dose to tgg j organ from the i radionuclide, via thq k exposure pathway, rem.

j the organ of interest (bone, GI tract, thyroid, liver,

=

total body, and skin.)

k

=

exposure pathway of interest:

(1) water ingestion, (2) fish ingestion, (3) shoreline recreation, (4) above-water recreation, (5) in-water recreation.

(IDCF)IJ =inges[fondosecommitment factor for the j organ from th the i radionuclide, rem /pCi.

For the combination of pathways considered and the nuclide mix expected, the maximum exposed individual will be an adult or child.

Table 2.1 is a list of ingestion oose factors for the two age groups.

th lik = the activ{gy ingested of the i radionuclide, via the k exposure pathway, pCi.

1 11=CVgn (2.18)

For the fish pathway 1 12=CBM fg (2.19) th C.

=

concentration of the i radionuclide in the 1

Tennessee River, pCi/mL Cg = A /(F d)

(2.20) g g

A. = activity released of i th~ radionuclide during the 1

release period, pCi.

1 F

= total river flow at location f during period, mL.

g

-24

[

=

' s t = 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 total exposed population.

Table 2.4a gives the river location of public water supplies; tables 2.4b and 2.4c give the boundaries of the various reaches in which concentrations are calculated for the fish and recreation pathways.)

d = fraction of river flow available for dilution (1/5 above Chickamauga Dam, 1 below the dam).

V = average. rate of water consumption per Regulatory Guide

' l.109.

For maximum ~ individual:

Adult -

2000 mL/d Child -

1400 mL/d For average individual (population):

Adult -

1010 mL/d Child -

710 mL/d n

= number of days during the release period, day.

th B.

= bioaccumulation factor for the i radionuclide in 1

fish, pCi/g per pCi/mL, from table 2.2.

M

= amount of fish consumed during the period (fraction of year times the annual consumption rate per Regulatory Guide 1.109.)

For maximum individual:

Adult -

21 kg/yr Child -

6.9 kg/yr For average individual (population):

Adult -

6~.9 kg/yr Child -

2.2 kg/yr th (RDCF)ijk=recreationgsecommitment factor fgg the j organ t

from the i radionuclide via the k pathway; mrem /yr per concentration ((ik) in medium; from table 2.3.

th

'(

= the concentration of the i radigguclide in the environ-ik mental medium pertaining to the k pathway.

For above-water and in-water pathways (ik

I

=C (2.21 i5 1 $

woma.

so, s

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

m.

For the shoreline pathway, a 15-year buildup in the sediment of the lake is assumed (per Regulatory Guide 1.109 equation A-5).

W [1-exp (-A t)]

(2.22' (13 = 100 RHLtCf f

where 100 = transfer constant as defined in Regulatory Guide 1.109.

th RHL. = radiological half-life of the i isotope, days, 1

.from table 2.1.

W = shoreline width factor (0.3 for a lake shore, per table A-2 of Regulatory Guide 1.109.)

th A. = decay constant of the~i radionuclide 1 = 0.693/RHL.

f t = buildup time in sediment, assumed 15 years, per Regulatory Guide 1.109.

k=assumpgexposuretimeofmaximumindividualfor t

the k pathway

3) shoreline 500 h/yr

(~10 h/ week)

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. exposure for each quarter 1st Quarter Jan.-March 0.1 2nd Quarter April-June 0.3 3rd Quarter July-Sept.

0.4 4th Quarter Oct.-Dec.

0.2 2.3.3.2 Population Doses th The total dose from all 5 pathways to the j organ of the population, a,

d from m nuclides at n locations is described by n

5 m

A O

J ij kt (2.23) 2=1 k=1 i=1 n

5 m

D'ij kE P

(2.24)

=

kt A=1 k=1 i=1 where th ij kt dgge to the j organoftpgtotalpopulationfromthe A

=

i radionuclide via the k pathway at location 2. ~

2

~,%.

.. = _

D

=

dose to individual as described in section 2.3.3.1 ij kf at location f.

th l

P

=

kt number of people exposed via the k pathway at i

location 1, from table 2.4.a-c.

The population is assumed to consist of 71 percent adults and t

29 percent children (from Appendix D, Regulatory 1

Guide 1.109 - the value for children includes 1

teenagers).

1 i

f, Analysis or Evaluation Justifying Change The-description of the quarterly dose analysis procedures was modified to include the recreation pathway. Although the calculations have been done all along, the methodology had not been placed in the ODCM.

Dose factors and concentration factors are expanded and updated. This was done to improve both the accuracy and the documentation for the values.

i Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 10.

Change 13 l

Description of Change 1

Tables 2.1, 2.2, 2.3, and 2.4 a-c have been revised.

I Analysis or Evaluation Justifying Change See Change 12.

i Evaluation of Accuracy of Dose Calculation or Setpoint Determination See Change 10.

I i

4 _..,. _,_,,._....___.._ _, _,_

~

Table 1.4a REAL RECEPTOR LOCATIONS NEAREST HOME-USE MILCH" SECTOR RESIDENT (m)

CARDEN(m)

ANIMAL (m)

N 1344 1344 4219 NNE 2812 2812 4531 NE 3438 3438-5625 ENE 2187 2187 E

1812 2656 ESE 1812 2031 2344 SE 1719 2062 SSE 2250 2344

[

S 2375 2375 SSW 2250 2750 3594 SW 2969 3438 WSW 1469 2062

/

W 938 938 WNW 1812 1812 1875 NW 1188 1188 2031, 5781 (goat)

NNW 781 1875 2438 (goat) a.

All are real cow locations except where noted otherwise.

d

[

i l

l l

Revi,sion 5 l -

TABLE 1.6 NUCLIDE SPECIFIC TRANSFER DATA *

(f)

NUCLIDE HALF-LIFE RETENTION Bh(

)

FM 1

TRITIUM 4.49E+03 4.70E-01 4.80E+00 1.30E-02 2

C-14 2.09E+06 4.70E-01 5.50E+00 1.20E-02 3

N-13 6.94E-03 4.70E-01 7.50E+00 2.20E-02 4

0-19 3 36E-04 4.70E-01 1.60E+00 2.00E-02~'~

5 F-18 7.62E-02 4.70E-01 6.50E-04 1.40E-02 6

NA-24 6 33E-01 4.70E-01 5.20E-02 4.00E-02 7

P-32 1 43E+01 4.70E-01 1.10E+00 2.50E-02 8

AR-41 7.63E-02 4.70E-01 6.00E-01 2.00E-02 9

_ CR-51 2.78E+01 4.70E-01 2.50E-04 2.20E-03,

10 MN-54 3.03E+02 4.70E-01 2.90E-02 2.50E-04 11 MN-56 1.07E-01 4.70E-01 2.90E-02 2.50E-04 12 FE-59 4.50E+01 4.70E-01 6.60E-04 1.20E-03 13 CO-58 7.13E*01 4.70E-01 9.40E-03 1.00E-03 14 CO-60 1.92E*03 4.70E-01 9.40E-03 1.00E-03 15 ZN-69M 5.75E-01 4.70E-01 4.00E-01

_3.90E-02,_

16 ZN-69 3.96E-02 4.70E-01 4.00E-01 3.90E-02 17 BR-84 2 21E-02 4.70E-01 7.60E-01 5.00E-02 18 BR-85 2.08E-03 4.70E-01 7.60E-01 5.00E-02 19 KR-85M 1.83E-01 4.70E-01 3.00E+00 2.00E-02 20 KR-85 3.93E+03 4.70E-01 3.00E+00 2.00E-02 21 KR-87 5.28E-02 4.70E-01 3.00E+00 2.00E-02 22 KR-88 1 17E-01 4.70E-01 3.00E+00 2.00E-02' -

23 KR-89 2.21E-03 4.70E-01 3.00E+00 2.00E-02 24 RB-88 1 24E-02 4.70E-01 1.30E-01 3.00E-02 25 R8-89 1.07E-02 4.70E-01 1.30E-01 3.00E-02 26 SR-89 5.20E+01 4.70E-01 1.70E-02 1.40E-03 27 54-90 1.03E+04 4.70E-01 1.70E-02 1.40E-33 28 SR-91 4.03E-01 4.70E-01 1.70E-02 1.40E-03 -~

29 SR-92 1.13E-01 4.70E-01 1.70E-02 1.40E-03 30 SR-93 5.56E-03 4.70E-01 1.70E-02 1.40E-03 31 Y-90 2.67E+00 4.70E-01 2.60E-03 1.00E-05 32 Y-91M 3.47E-02 4.70E-01 2.60E-03 1.00E-05 33 Y-91 34 Y-92 5.A8E+01 4.70E-01 2.60E-03 1.00E-05_,

1.47E-01 4.70E-01 2.60E-03 1.00E-05 35 Y-93 4 29E-01 4.70E-01 2.60E-03 1.00E-05 36 ZR-95 6.50E+01 4.70E-01 1.70E-04 5.00E-06 37 NS-95M 3.75E+00 4.70E-01 9.40E-03 2.50E-03 38 N9-95 3 50E+01 4.70E-01 9.40E-03 2.50E-03 39 MO-99 2.79E+00 4.70E-01 1.20E-01 40

'TC-99M 2.50E-01 4.70E-01 2.50E-01

~ 7.50E-03 2.50E 41 TC-99 7 74E+07 4.70E-01 2.50E-01 2.50E-02 42 TC-104 1.25E-02 4.70E-01 2.50E-01 2.50E-02 43 RU-106 3 67E+02 4.70E-01 5.00E-02 1.00E-06 44 TE-132 3 24E+00 4.70E-01 1.30E+00 1.00E-03 45 '~ I-129

~~ 6 21E+09 4.70E-01 2.00E-02 1.20E-02 46 I-131 8 05E+00

'4.70E-01 2.00E-02

'1.20E-02 ~

47 MI-131 8 05E+00 4^.70E-01 2.00E-02 1.20E-02 48 I-132 9.58E-02 4.70E-01 2.00E-02 1.20E-02 49 MI-132 9.58E-02 4.70E-01 2.00E-02 1.20E-02 50 1-133 8.75E-01 4.70E-01 2.00E-02 1.20E-02 51 MI-133 8 75E-01 4.70E-01 2.00E-02

__,._,.1.20E-02_ _

52 I-134 3.61E-02 4.70E-01 2.00E-02 1.20E-02 53 MI-134 3.61E-02 4.70E-01 2.00E-02 1.20E-02 54 I-135 2.79E-01 4.70E-01 2.00E-02 1.2SE-02 55 MI-135 2.79E-01 4.70E-01 2.00E-02 1.2dE-02 56 XE-131M 1 18E+01 4.70E-01 1.00E+01 2.00E-02 57 XE-133M 2 26E+00 4.70E-01 1.00E+01 2.00E-02 58 XE-133 5 27E+00 4.70E-01 1.00E+01 2.00E-02 59 XE-135M 1.08E-02 4 70E-01 1.00E+01 2.00E-02 60 XE-135 3.83E-01 4.70E-01 1.00E+01 2.00E-02 61 XE-137 2.71E-03 4.70E-01 1.00E+01 2.00E-02 62 XE-138 1.18E-02 4.70E-01 1.00E+01 2.00E-02 63

.CS-134 7.48E+02 4.70E-01 1.00E-02.

8.00E-03 _._

64 CS-13S 1 10E+09 4.70E-01 1.0nE-02 8.00E-03 65 CS-136 1.30E+01 4.70E-01 1.00E-02 8.00E-03 66 CS-137 1.10E+04 4.70E-01 1.00E-02 8.00E-03 67 CS-138 2.24E-02 4.70E-01 1.00E-02 8.00E-03 68 BA-139 5.76E-02 4.70E-01 5.00E-03 4.00E-04 69 84-140 1.2SE+01 4.70E-01 5.00E-03 4.00E-04.._.

70 LA-140 1 68E+00 4.70E-01 2.50E-03 5.00E-06 71 CE-144 2.84E+02 4.70E-01 2.50E-03 1.00E-04 72 PR-143 1 36E+01 4.70E-01 2.50E-03 5.00E-06 73 PR-144 1 20E-02 4.70E-01 2.50E-03 5.00E-06 74 NP-239 2.35E+00 4.70E-01 2.50E-03 5.00E-06 Revision 5

Reference:

NUREG/CR-1004

TABLE 1.7 INTERNAL DOSE FACTORS 1 INFANT THYROID 2

Inhalation 1 Cow' Milk Ingestion 3'

2 cm

' mrem m

-s'

' mrem - iTCT; yr pCi.

Radionuclide yr H-3 6.47 (+8) 3.53 (+9)*

Te-132 2.79 (+8) 3.50 (+7) 1-131 1.48 (+13) 7.24 (+11) 1-133 3.56 (+12) 1.52 (+10)

Unit for H-3 is mrem /yr per pCi/cm".

1.

Bas d on Regulatory Guide 1.109 methodology with an infant breathing 3

i rate of 1400 m /yr..

2.

Based on Regulatory Guide 1.109 and NUREG/CR-1004 dose methodologies.

i

/

l Revision 5 i

~ _ _.,

p e

s u

e t

e j

g e

f g

u dem n N D N 4 R N 4 n n N4 4 NF 4 W 4 4 C o c oN 4 4 N o 4 4 DM hNw N

kN4cemnm tedmCN o c o c o n o o c o o o o o o o o o o o o o o o o o o c c o c o o o o @o o o o @o @o o @o o o o o o o o c @o o o o o o C OU&O I I I I I 6 O S 9 9 0 0 0 0 I e8 I I I I I.* * + t I 8 0 + I t B 1 8 t i l 8 1 8 0 0 0 3 8 I I t 1 0 0 t l B I S UWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWk U>RNooCONdommc@

Uno 4 4 T C @ o n*@ m W N C o 4 C n m b b @ mc o oN @E 7 m m n m ome N o c cc o N N a @ N o=J n nmm @n N n n e mm 4 @ mm cN e em>

mN n o C a C n o m@ c N e @ N n N W @ n 4 N n om@ 4@ 4 UJ e e e e e e o e e e e o e e e e e e e e e o e e e e e e e e e e o e o e e e e e eo e e e o e. e e o e e e e o e e e U

N N m e n e m n @ N N m m N N N n @ N o m m @ o c o c a nn 4 @ n m *= m n N m e.d = 4 m @ m N N m N n N n n N a g U

i U>

I 1

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U C o c o c c o c o c c c. n N N 4 4 n @ d f 4 4 4 c c c N 4 4 N c 4 4 @ V. e N N O N t > @ N P a @ 4 m R N 4 % > 4 p f f o c c o c c o c c c o c o c c c o c c o c o o c. c o o c e c o c c c o c o c c o c c o o c c c UCI I e9 4 0 0 4 5 t t 4 8 6 4 6 l'8 t i l l t++ + + 9 6 lt e t B B I I I S 4 I I I I e3 4 I I I I 6 0 0 0 0 0 6 8 U

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3 8

U 4PNRh<nmRF e n k k 4 4 Fed + V 4 4 4.C C C h 4 4 W C 44 V C N k V M 4 h h W P N V!

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-UTnNaoO'4Wa@no=@ nNTN@o@mTNcocNN4Nm fNom@n9NC@4mN& mom 4 CComom@me W

T U b o4 N C m@ @ @ C n m @ m WN 4 N D @ 4 N @ mo o omn oN M o @ m s n omN @ Nm C mN a OO n 4 W R @ C @ Na e UUI o e o e e e e e e o e e e e e o e e o e o e eo e e o e o e e e e o e e o e e e e e o e e o et e e e e e o e e e e e UNNNamn4NNammmmmmmNmN4-m@cco4-mn4&n~=mmnNr@NNnn*MNNm=~4NNmnh U

j i

U t

=0 0

1 9

U k 4 n N n N 4 m N n N n N N n N N M M N N c c o'4 M N n @ @ N m N m -N'4 m m N m N N n m N n n N N m W N @ m N N N A e

UU o oo c c o o oo o o o o o c o cc o co c co c oc o cc o c c o oo o oc o c o n o c o o o c c c c c oo oc c 04 4 0 0 0 t t t 4 8 8 I t t 4 6 4 l* s s t + +

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NhmGcnvNC m

U o 4 n @ N N @ C m N W.o @ @@m4@@NocC*n@nnC=Nnkmo4ch<@C445 = N C T N" @ N 4 N N F E 4 h O

Um o e e e e e o e o e e e e e e o e e e e o e e e e e e e e e o e o e e e e e e e o e e e o e

e. e e e e e e e o e e e D

U C N N e m N e @ 4 m N 4,m N m N ~ C n n @ c o c e n 4 4 @ mmNwmmeNmeNmmNmNmn~=4m@ =>>44@@

\\

U e

i 4 N N n = @ n @ N N 4'n N -n 4 N # 4 m 4 4 ccCN44.

1 I

Z U

?

s W

U o c c c c o c c o c o c c c c c o c o c c o @c c c o c o c'o m N n m 4 W C m 4 @ m h m N n 4 N 4 W N r W O C 4 W 4 R 2

U occoccccccocooccocccccccccccc UWI I I I I I I G I 3 18 8 1 4 I I I S I I S I O + + + 0 I I + + 8 0 0 0: 1 0 8 t I I I I I 1 8 t t i 1 0 0 0 0 0 0 0 m

U P W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W W WW W W W W WW W W W W W's 9

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ULONOKN@C@m@@mWRN4nn@ 4h@mCCCmncRN4CnomtomQN@m4 mNn4*C4NCPCNN 0

U e e o e e o e e e e e e e e e e e o e o e o e e e e e e o e e e e e e e e e e o e e e o e e e e o e e o e e o e e

U Nmm m g m N h m m n @ m mN m m4 N 4 me@ c o o4 m em m N @ 4 c n n emc Nm m nn 4 @ N D e 4 m N ew mN N m

i E

t l

I l

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O 4

4 4 Nn N@ n dn N 4 4 m nf @ NT 4 mWW < o c CNm mn o d ? N @

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c c occcccccccccccccocc 6

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4 mm m m mN 4 mm m N N N @ C % ~~ N 4 4 m N o o cN D 4 @ m N 4 N r n N N @ n n 4 m 4 4 4 @ h @ n N n N n m N 4 V H

H 4>

N Z

CC44Nnn44f4RennnWVr

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c c c c c c c c oc o co c c o c c o c c c o c o c c c c c c c c c o c o o oc C y

O 4c8 9 8 3 0 3 3 I I I e4 0 I I e I I I I I I I + + + I I I I + I t t I I et e e 1 8 I I S I S I I I I I S 8 e I I I g

U 4

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(
Tcbla 2.2 F15H CONCENTRATION FACTOW',"
~ NUCLICE ~ ~
NUCLIDE nuc(!Og
~ *'*- * ~ ~ ~
H-3 9.00E-01 TC-499 1.50E 01 CE-144 1.00r.00 C-14
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8-32 J.00E*03 RH1034 1.00E.01 NO-147 2.SiE*01 CR-51 2 00E*02 RM-105 1.00E*01 Pu-147 2.56r.at MN-54 4.00E+02 RHl051 1.00F+0!
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' ~ ' ~
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'l.00E*01 CE-141 1.00E*00 CM-243 2.50E*01 TC-99 1 50E+01 CE-143 1.00E*00 CH-244 2.50E*01
-
The source for the fish concentration factors, given in order of preference is:
NUREG/CR-1336, "The Bioaccumulation Factor for Phosphorus-32 in Edible 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 Eleinents 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. Ng et al.; Lawrence Livermore Laboratory, May 1968.
Regulatory Guide 1.109, Draft, March 1976.
TVA generated numbers for noble gases.
Revision 5 -
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5H0REL INE ******************
5wIMH ING ******************
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(MREM / YEAR PER UCI/SQU4RE CENTIMETERI NUCLIOE BONE GI THYA010 TB LIVER SK!u RONE GI
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.._.TE-131._.. 6.79E+06_ 4.21Et06__4.37E,06__4.99E+06._4.13E+06. 6.llE+06.
6.49E+05._3.94E*05.__4.16C+05_ 4.71E+05._3.09E+05. 5.78E+05._.
TE1319 2.06E+07 1.53E+07 1.39E+07 1 70E*07 1 4SE+07 2 12E+07 1.84E+06 1.35E+06 1.23E*06 1 51F+06 1.2AE+06 1.89E*06 TE-132 4.27E+06 1.92E+06 2.54E+06 2.68E+06 2.04E+06 3.32F+06 4.55E+05 1.9AE+05 2.6eE+05 2.03E*05 2.12E+05 3.60E+05 1-129 2.25E+05 4.84E+04 1.19E+05 1.15E+05 4.75E+04 2.49F 05 5.02E+04 1.07E+04 2.67E+04 2.57F+04 1.05E+04 5.70E+04 1-130 3.09E+07 2.33E+07.2.00E+07_ 2.50E+07 2.14F+07 3.0AE+07 2.88E+06 2.17E+06.1.06E+06.2.32E*06 1.99E+06.2.86E+06 1-131 6.22E+06 3.93E+06 3.92E+06 4.54E+06 3.77E+06 5.47E+06 6.16E+05 3.87F+05.3.8AE*05 4.49r+05 3.72E+05 5.41E+05
._ I-132 __3.23Et07._2.45E!0Z__2.16Et07.__2.69E+07__2.29E+07 3 32F+07
.2.91E*06~ 2.20E+06__1 93Et06. 2 41E+06._2.06E+0$
2-99E+06 I-133 8.96E+06 6.00E+06 5.89E+06 7.18E+06 6.16E+06 n.69F+06 n.44E+05 6.49E+05 5.54E+05 6.75E+05 5.79E+05 8.17E+05 I-134 3.67E+07 2.84E+07_ 2 49E+07. 3.llE+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
d, I-135 2.19E+07 1.95E+07 1.75E+07 1.96E+07 1.67E+07 2 33E+07 1 7AE+06 1.57E+06 1.4tE+06 1 5HE+06 1.3SE+06 1.89E*06 as XE1334 6.05E*05 2.3PE*05_ 3.55E+05. 3.71E+05 2.61E+05 5.270+05 8.09E+04 2.81E+04 4.65E+04 4 77E+04 3.05E+04 7.71E+04 8
XE-133 8.52E+05 2.53E+05 4.84E+05 4.24E+05 2.74E+05 5.73E+05 1.llE+05 3.17E+04 6.2AE+04 5.57E+04 3.39E+04 8.27E+04
._.XE1359... 6.4tEt06 _4.9.4E*06__3.lSE?06__5,04Et06._4.33E+06 6 0RE+06
.6.21Et05._4.75E+05 __4.01E*05_.4.87f+05. 4.17Et05__5.90E+05.._
XE-135 4.54E+06 2.2BE+06 2.76E*06 3.02E+06 2.40E+06 3.63F +06 4.59E+05 2.29E+05 2.79E+05 3 04r+05 2.41E 05 3.67E+05 C5-134 2.22E+07 1.67E+07. 1 43E+07..l.81E+07 1 55E+07 2 26E+07 2.04E+06 1.54E+06 1.32E+06 1 67E+06.l.43E+06 2.08E+06 C5-135 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 00F+00 0.00E+00 0.00E+00 C5-136 3.10E+07 2.26E+07_ 2.03E+07 2 55E+07 2.15E+07 3.21E+e7 2.77E+06 2.00E+06 1.81E+06 2 26F+06 1.91E+06 2.85E+06 C5-137 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 0.00F+00 0.00E+00
._ C5-138.. 3.29E+07._3.03E+07__2.86E+nI__2.98E+07__2.56E+07 3 46E+07
.2.62E+06.. 2.37E+06 2.23E+06__2.33E+06__2.02E*06. 2.74E+06...
BA1379 8.56E*06 6.45E+06 5.48E+06 6.92E+06 5.93E+06 8.59E+06 8.01E+05 6.02E+05 5.l?E+05 6.47E+05 5.54E+05 8.04E*05 BA-139 7.49E+05
'3.44E+05. 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 5.62E+04 BA-140 2.29E+06 1.60E+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 8.90E*06._S.96E+06 _l.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+06 BA-142 1.51E*07 1.11E+07 1.02E+07 1 24E+07 1.04E+07 1 54E+07 1.34E+06 9.36E+05 9.03E+05 1 10E*06 9.17E+05 1 36E+06
. LA-140._ 3.20E+07.._2.91E*07__2.73Et07__2,FRE+07.. 2,46E+07_.3.3tr+07 _ 2.60E+06 _2.32Et06___2.lPE?O6_ R.32F+06._1.9dE.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*06 2.73E+06 2.64E+06 2 53E+06 2.52E 06 3.00E+06 CE-141 1.59E+06 5.94E+05 9.70E+05 9.01E+05 6.75E+05 1.04F+06 1.69E+05 6.20E+04 1.0?E+05 9.52E+04 7.07E+04 1.16E+05 CE-143 4.54E+06 2.64E+06 2.79E+06 3.22E 06 2.60E+06 4.00F+06 4.66E+05 2.6tE+05 2.83E+05 3.24F+05 2.57E+05 4.07E+05 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 2.7AE+04. 2 50E+04 1.76E+04 3.18E+04 PR-143 1.26E-01 9.3AE-02 8.00E-02 1 03E-01 8.83E-02 1 30E-01 1.15E-02 8.60E-03 7.33C-03 9.45E-03 8.09E-03 1.19E-02
__PR-144.___4.40f+05_ 4.24E+05_ 3.7.4E+05_ 3*97Et05 3.50E+05_.4.75E*05
. 3.46E+04 3.24E+04 _2.97Et04__3 10E+04.2.TRE+04._3.71E+04. __
PR1444 1.42E+05 3.32E+04 7.19E+04 6.95E+04 3.23E+04 1 2SF+05 2.28E+04 5.33E*03 1.15E+04 1 12E+04 5.17E+03 2.06E+04 N
ND-147 2.33E+06 1.34E+06. 1.44E+06 1.57E+06 _1.25F+06 1 93E+06 2.47E*05 1.35E+05 1.50E+05 1.62F+05 1.27E.05 2.03E+05 Q
PM-147 7.86E+01 2.76E*01 4.92E+0!
4.26E+01 3.23E+01 4.9AE*01 8.17E+00 2.92E+00 5.11E*00 4.43F+00 3.36E+00 5.17E+00 pu PM-149 1.98E+05 1.12E+05 1.23E+05 1.39E+05 1.13E+05 1 69E+05 1.9eE+04 1.llE+04 1.22E+04.l.3BE+04 1.12E+04 1.67E+04 yL SM-147 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00F+00 0.00E+00 0.00E+00 0.0nE+00 0.00r+00 0.00E+00 0.00E+00
.._ SM-151 _.1.69Etol_ 2.20E+00 _5.6DE+00__1.33E+01_1.61E+00 6.7BE+01 -
7.60E+00-.l.04r+00 2.56C+00._6.24E+00 7.22E-01 _3.55E*01 D
SM-153 1.25E*06 3.89E+05 7.21E+05 6.31E+05 4.25E+05 8.0HC+05 1.57E+05 4.71E+04 n.79E+04 7.83E+04 5.07E+04 1.04E+05 o
to EU-155 1.35E+06 4.28E+05 7.98E*05 6.81E+05 4.78E+05 8.21E+05 1.54E+05 4.82E+04 8.9PE+04 7.73E+04 5.35F+04 9.49E+04 TA-182 2.42E+05 1.90E+05 1.80E+05 2.04E+06 1.68E+05 2.44E+05 1.94E+06 1.41E+06 1.45E*06 1 63F+06 1.35r+06 1.96E+06 W-187 7.25E*06 5.00E+06_4.57E+06. 5 55E+06 4.60E+06 6.81E+06 6.99E+05 4.84E+05 4.30E?05__5 30E+05 4.45E+05 6.52E+05
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Table 2.4.e Public Water Supply Information*
2020 TRM POPULATION WATER SUPPLY 4 64.5
- SE000YAH NUCLEAR PLANT 473.0 2000 ICI AMERICA, INC. (VAAD) 473.0 900 C. F.
INDUSTRIES, INC.
470.5 4000 E.
I. DUPONT, COMPANY' 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 00ARD 392.0 BELLEFONTE NUCLEAR PLANT 385.8 38700 SCOTTSBORO 382.1 18600 SAND MOUNTAIN WATER AUTHORITY 368.2 125 CHRISTIAN YOUTH CAMP 358.0 14900 GUNTERSVILLE 334.5 4500 N;E.t10RGAN CO., WATER AND FIRE 334.2 168600 HUNTSVILLE 330.2 1000) REDSTONE ARSENAL 324.2 REDSTONE ARSENAL 306.0 84600 DECATUR 294.0 BROWNS FERRY NUCLEAR PLANT 283.0 500 U.S. PLYWOOD-CHAMPION PAPER 274.9 50 WHEELER DAM 259.6 14100 MUSCLE SHOALS 259.5 2700 TVA-NFOC 254.3 21100 SHEFFIELD 245.0 520 COLBERT STEAM PLANT 239.3 3900 CHEROKEE 238.7 350 U.S.' STEEL AGRI-CHEMICALS, INC.
217.4 1 YELLOW CREEK NUCLEAR PLANT 206.8 2400 HARDIN CO. WATER DISTRICT 193.5 1900 TRI-COUNTY UTILITY DISTRICT 158.0 1100 CLIFTON 101.9 170 FOOTE MINERAL Co.
100.5 6100 NEW JOHNSONVILLE 100.4 13300 CAMOEM 100.0 375 JOHNSONVILLE STEAM PLANT 98.5 900 E.
I. DUPONT COMPANY 95.5 700 CONSOLIDATED ALUMINUM CORPORATION 94.5 250 INLAND CONTAINER CORPORATION 79.5 120 BASS BAY RESORT 39.3 4300 JONATHAN CREEK WATER OISTRICT 28.5 9100 NORTH MARSHALL WATER OISTRICT 23.6 650 GRAND RIVERS 17.8 600
8. F. GOODRICH CHEMICAL Co.
17.4 106 AIRCO CARRIDE 16.8 592 AIRCO ALLOYS 16.7 510 AIR PRODUCTS AND CHEMICALS 1.1 69800 PADUCAH Revision 5
From TVA Water Quality Branch, updated December 1979 -
Ttbla 2.4.b Fish Harvest Data RIVER SPAN FISH HARVEST (LBS/YR)
(TRM)
NAME OF REACH SPORT
COMMERCIAL
5 5
484.5 - 471.0 Chickamauga Lake below SQN 5.4x10 2.0x10 471.0 - 452.0 Nickajack Lake (Part 1 of 2) 1.2x10 4.6x10" 5
5 5
452.0 - 424.7 Nickajack Lake (Part 2 of 2) 2.9x10 1.1x10 5
9.5x10" 424.7 - 417.5 Guntersville Lake (Part 1 of 4) 2.6x10 5
5 417.5 - 392.0 Guntersville Lake above BLN 5.2x10 1.9x10 392.0 - 373.0 Guntersv111e Lake below BLN 7.8x10s 2.9x10 5 373.0 - 349.0 Guntersville Lake (Part 4 of 4) 1.0x10 3.8x10s 6
5 349.0 - 294.0 Wheeler Lake above BFN 1.0x10' 3.8x10 294.0 - 274.9 Wheeler Lake below BFN 1.5x10 5.7x10s 5
5 5
274.9 - 259.4 Wilson Lake 5.9x10 2.2x10 259.4 - 217.4 Pickwick Lake above YCN 1.3x10' 4.9x10 5 5
5 217.4 - 206.7 Pickwick Lake below YCN 3.3x10 1.2x10 5
5
,206.7 - 165.0 Kentucky Lake (Part 1 of 4) 6.1x10 2.3x10 165.0 - 121.0 Kentucky Lake (Part 2 of 4) 6.1x10 2.3x10s 5
121.0 - 76.0 Kentucky Lake (Part 3 of 4) 1.8x10 6.8x10s 8
76.0 - 22.4 Kentucky Lake (Part 4 of 4) 3.1x10 1.1x10' 5
CDerived from " Situation Assessment and Planning Assumptions," Division of Forestry, Fisheries, and Wildlife, TVA, December 1978.
i l
Derived from " Estimated Commercial Fish and Mussel Harvest from the Tennessee Valley,"
l Fisheries and Aquatic Ecology Branch, TVA, 1980.
l Revision 5 i
I I
Table 2.4.c Recreation Usage Data
RIVER SPAN HOURS OF USAGE PER YEAR (TR'O NAME OF REACH SHORELINE ABOVE-WATER IN-WATER 8
5 5
484.5 - 471.0 Chickamauga Lake below SQN 5.5x10 1.0x10 4.9x10 471.0 - 452.0 Nickajack Lake (Part 1 of 2) 1.2x10 2.5x10" 1.1x10 5
5 452.0 - 424.7 Nickajack Lake (Part 2 of 2) 2.0x10 4.0x10" 1.8x10s 5
424.7 - 417.5 Guntersville Lake (Part 1 of 4) 7.0x10" 1.5x10" 6.0x10" 5
5 417.5 - 392.0 Guntersville Lake above BLN 5.2x10 1.0x10s 4.7x10 6
5 5
392.0 - 373.0 Guntersville Lake below BLN 4.7x10 8.9x10 4.2x10 373.0 - 349.0 Guntersville Lake (Part 4 of 4) 1.1x10 2.1x10 9.8x10' 7
8 5
8 349.0 - 294.0 Wheeler Lake above BFN 4.0x10' 7.6::10 3.6x10 294.0 - 274.9 Wheeler Lake below BFN 5.2x10 1.0x10 4.7x10" 5
8 5
274.9 - 259.4 Wilson Lake 3.9x10' 7.4x10s 3.5x10 8
5 259.4 - 217.4 Pickwick Lake above YCN 2.0x10 3.5x10s 2.0x10 217.4 - 206.7 Pickwick Lake below YCN 2.0x10 4.0x10 1.8x10' 5
5 206.7 - 165.0 Kentucky Lake (Part 1 of a) 6.0x10s 1.2x10 5.4x10 5
5 5
5 165.0 - 121.0 Kentucky Lake (Part 2 of 4) 1.2x10 2.3x10 1.1x10' 121.0 - 76.0 Kentucky Lake (Part 3 of 4) 2.4x10 4.7x10s 2.2x10' 5
7 8
7 76.0 - 22.4 Kentucky Lake (Part 4 of 4) 2.6x10 4.9x10 2.3x10 s
(I ased on " Extent of Recreation Development and Use of TVA Lake Frontage Property;"
B (unpublished data from 1974 Annual Recreation Survey); and Observations of Recreation Use of TVA Reservoirs, Division of Reservoir Properties, Recreation Resources Branch, TVA, 1975.
Revision 5 J
'

ML20071F214

Text

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