ML20009E366

Monthly Operating Repts for June 1981

ML20009E366
Person / Time
Site:	Sequoyah
Issue date:	07/08/1981
From:	Ballentine J, Dupree D TENNESSEE VALLEY AUTHORITY
To:
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ML20009E361	List: ML20009E360 ML20009E366
References
NUDOCS 8107280086
Download: ML20009E366 (31)

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.O o

TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLYbPERAT'INGREPORT JUNE 1, 1981 -JUNE 30, 1981 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79

\\ \\

s Submitted By: i h. \\d RAL LLA Plang%perintendent 0$000hjy PDR

t e

TABLE OF CONTENTS Operations Summary.

1 PORV's and Safety Valves Summary.

1 Licensee Events and Special Reports,_..,,.

1-2 Offs!

'ose Calculation Manual Changes '.

3-5 Signiticant Operational Events.

5 Operating Data Unit 1 6-8 Unit 2 9-11 Plant Maintenance Summary 12 Outage Maintenance Summary.

12-14 Documentation for ODCM Changes.

15-28 g 9 y

.-. - --- w p-e e-M-u

-g v

-ww

s Operations Summary June, 1981 The following summary describes the significant operational activities for the month of June.

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

Unit I was critical for 430.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, produced 441,880 MWH (gross) with 3.86 percent station use, esulting in an average hourly Fross load of 1,072,568 KW during the month. The net heat rate for the month was 10,700 BTU /KWH.

There are 211.35 full power days estimated remaining until the end of cycle 1 fuel, With r. capacity factor of 85 percent the target EOC exposure would be reached May 22, 1982. The capacity factor for the month was 52.3 percent.

There was one scram during June.

. Unit 1

\\

At 001 hrs. on June 1 the reactor was in mode 3.

The reactor was taken critical at 2014 hrs. on June 4 and tied on line at 2218 hrs. At 2206 hrs.

on June 5 the reactor obtained 100% power producing 1132 mw(e).

At 2307 hrs.

on June 19 the load was dropped to 50% for the load rejection test (Start Up Test 9.3).

At 2339 hrs. a load reduction was started to bring the unit off line for outage maintenance items and preoperational test W-6.1F.

The turbine was tripped at 0057 hrs. June 20.nd the unit entereo mode 3 ac 0145 hrs. At 1620 hrs. on June 20 the reactor cred mo& 5.

Reactor heatup was begun on June 25 at 1745 hrs. The reactor was taken c ritical at 0858 hrs. on June 27, and was tied on the line at 0038.u-June 28.

One-hundred percent power w 3 obtained at 2150 hrs. on June 30, 0146 hrs., the reactor tripped (Reactor trip

1. 15) when main steam intercept val;_ 1-FCV-1-22 closed while the unit operator was attempting to open the valve by the hand switch on the control bench board.

The valve closing caused a Lo-Lo steam generator level in the #3 steam generator and the reactor trip. At 2359 hrs. on June 30 the reactor was in mode 3.

Unit 2 Pre-fuel loading preoperational testing continued during the month.

Unit 2 was issued at 5% power ^ operation license on June 26.

Preoperational test W-6.1F, Integrated Safety Injection Test, was performed during June.

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

Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during June, 1981, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission. -

s Licensee Events and Special Reports (Cont.)

f SQRO-50-327/80209 No post maintenance testing performed on 1-FCV-70-156.

SQR0-50-327/81054.

Chlorine analyzer 43-205A was declared in-operable twice after channel checks indicated electrolyte drip rate.

SQRO-50-327/81056

'A' train of ABGTS declared inoperable when fan bearing overheated.

SQR0-50-327/81057 Rad monitor 0-RM-90-0 2 declared inoperable when monitor failed to source check.

SQRO-50-327/81058 S/G Level Channel 1-L-3-38 Lo-Lo level histable setpoints,for reactor trq and safety features actuation'below limits.

SQRO-50-327/81059 ABGT declared. inoperable because railroad deor to cask loading area was open without personnel present to close door if necessary.

SQRO-50-327/81060

'A' condensate storage tank level transmitter 0-LT-2-230 inoperable due to broken compres-sion union.

SQR0-50-327/81061 RHR miniflow valve, 1-FCV-74-12, inoperable due to hypoid gear cocked on drive sleeve.

SQRO-50-327/81062 Turbine driven AFW PMP failed to deliver full flow due to speed control setpoint drift.

SQRO-50-327/81063 Containment hydrogen analyze-1-43-210 found out of tolerance due to reasent air misadjustment.

SQR0-50-327/81064 Lower containment rad monitor 1-RM-90-106 in-operable when sample pump breaker tripped.

SQRO-50-327/81065 Turbine building sump discharge rad monitor 0-RM-90-212 inoperable due to broken sample pump motor.

The following cpecial reports were sent during June 1981, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Pegulatory Commission.

Special Report Number Subject 81-4 Safety injection on May 31, 1981.

81-5 Fire door inoperable for more than 7 days.

s Offsite Dose Calculation Manual Changes Changes in the Sequoyah Nuclear Plant ODCM are described in this section in accordance with Sequoyah Technical Specification 6.1.14.

Changes 1 through 7 were officially approved by the RARC on June 11, 1981.

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

Change 1 Description of Change Section 2.3.2, Monthly Analysis, has been revised to reflect the use of 11 nuclides rather than 5 nuclides and a typographical error was corrected.

Analytt a or Evaluation Justifying Change

\\

ODCM as changed more accurately reflects nuclides being released from plant. Nuclides that were added had previously been evaluated on a quarterly basis rather than a monthly basis. Change is considered to be conservative as nuclides will be looked at more frequently.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations Accuracy of dose calculation on a monthly basis is improved by change.

Change 2 Description of Change Section 2.3.2.1, Water Ingestion, has been revised to reflect the use of 11 nuclides rather than 5.

Analysis or Evaluation Justifying Change See Change 1.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations See Change 1.

Change 3 Description of Change Section 2.3.2.2, Fish Ingestion, has been revised to reflect the use of 11 nuclides rather than 5.

f Analysis or Evaluation Justifying Change See Change 1.

l !

Offsite Dose Calculation Manual Changes (Cont.)

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations See Change 1.

Change 4~

Description of Change Added new column to Table 2.1, " Fish-Biological Half-Life (Days)".

Analysis or Evaluation Justifying Change Added data to table.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations Not applicable.

Change 5 Description of Change Section 1.2.1, Noble Gases, has been revised to reflect the addition of Xe-131m and Xe-135 and to change the fraction of assumed dose contribution.

Analysis or Evaluation Justifying Change ODCM as changed more accurately reficcts nuclides being released from plant.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations Accuracy of dose calculation is improved by change.

Change 6 Description of Change Section 1.2.2, Iodine and Particulates, has been changed to revise assumptions used and to clarify equations.

Analysis or Evaluation Justifying Change ODCM as changed more accurately reflects doses for Iodines and Particulates.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations See Change 5.

9 Offsite Dosa Calculation M:nual Changes (Cont.)

Change 7 Description of Change Liver added to Table 2.1 as an organ of interest.

Analysis or Evaluation Justifying Change Change reflects the consideration of the liver as a critical or8an for certain isotopes.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations Accuracy of dose calculations not affected.

Significant Operational Events N,

Unit 1 Date Time Event 06/01/81 0001 Reactor in mode 3.

06/04/81 2014 Reactor critical.

2218 Unit I tied on line.

06/05/81 2206 Reactor at 100% RTP, 1132 mw(e) 06/19/81 2307 50% load drop - Start-up test 9.3 06/20/81 3057 Turbine Tripped - Unit manually shutdown for outage items maintenance and Preoperational Test W-6.1F.

0145 Reactor in mode 3.

1620 Reactor in mode 5.

06/25/81 1745 Reactor in mode 4 - Heatup began.

06/27/81 0858 Reactor critical.

06/28/81 0038 Unit tied on line.

2150 Reactor at 100% RTP.

06/30/81 0146 Reactor Trip #15 - MSIV 1-FCV-1-22 closed creating a Lo-Lo steam generator level in #3 steam generator thus the reactor trip.

2359 Reactor in mode 3...

OPERATING DATA REPORT DOCKET NO.

50-327 DATE 7/8/81 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 OPERATING STATUS 1.

Unit Name:

Seouovah One Notes 2.

Reporting Period:

June 3.

Licensed Thermal Power (NWt):

3411 4.

Nameplate Rating (Gross MVe):

1220.58 5.

Design Electrical Rating (Net MWe):

1128 6.

Maximum Dependable Capacity (Gross' MWe):,_% 1128 1163 7.

Maximum Dependable Capacity (Net MWe):

8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

Unit derated due to turbine not meeting design specifications.

9.

Power Level To Which Re:tricted, If Any (Net NWe):

10.

Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative 11.

Hours in Reporting Period 720 4343 T11688 12.

Number of Hours Reactor Was Critical 430.7 2481.5 4020.1

13. -Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 412 2295.7 3129.7 15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1.323.863.5 6.976.933.5-8.648.963 17.

Gross Electrical Energy Generated (MWH)

~ 441,880 2,368,033 2,925,354 18.

Net Electrical Energy Generated (MWil) 424,818 2,260,947

_2,779,787 19.

Unit Service Factor 57.2 52.9 26.9 20.

Unit Availability Factor 57.2 52.9 26.9 21.

Unit Capacity Factor (Using MDC Net) 52.3 46.2 21.1 22.

Unit Capacity Factor (Using DER Net) 52.3 46.2 21.1 23.

Unit Forced Outage Rate 42.8 47.1 73.1 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

September, 1981 - Tech Spec required ice weighing 25.

If Shut Down At End Of Report Period, Estimated Date of Startup:

July 1, 1981

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 7/4/80 7/5/80 INITIAL ELECTRICITY 8/21/80 7/22/80 COMMERCIAL OPERATION 5/1/80 7/1/81 e

(9/77) i.

o AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-327 UNIT Sequoyah One DATE 7/8/81 COMPLETED BY David Dupree TELEPliONE (615) 842-0295 MONTH June N

DAY AVERAGE DAILY POWER LEVEL

" DAY AVERAGE DAILY-POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 1090 2

0 18 1081 3

0 19 1077 4

0 20 0

5 726 21 0

6 1115 22 0

7 1116 23 0

8 1116 24 0

9 1119 25 0

10 1108 26 0

11 1083 27 0

12 1069 28 1094 13 1112 29 1116 14 1103 30 0

15 1104 31 N/A 16 1093 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) l

_ 7_

t

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-327 UNIT NAME Sequoyah One DATE 7/8/81 COMPLETED BY David Dupree REPORT MONTl!

June TELEPHONE (615) 842-0295 1

oe3 Licensee Cause & Corrective em n

No.

Date "o

.0 e.C 8 Event E%

Action to S:

E l' $

Report #

$3 E.3 Prevent 2ncurrence a

H

$5 NE:

m A

zmg u

A 15 81/05/31 F

94.3" G

4 Radio interference caused transmitters to the pressurizer level to occillate causing the reactor to trip, (Reactor Trip #81-14).

4 16 81/06/20 S

1.83 B

5 Fifty percent load rejection test.

Manual reduction for integrated safety injection test.

16 81/06/21 S

191.5 B

1 Manual shutdown for integrated safety injection test.

17 81/06/30 F

22.2 A

3 A MSIV closed-which caused a Lo-Lo S/G level causing the Rx to trip (#81-15).

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Sce.!duled 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-Con t. 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

O OPERATING DATA REPORT DOCKET NO.

50-328 DATE 7/8/81 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 OPERATING STATUS 1.

Unit Name:

Sequoyah Two Notes 2.

Reporting Period:

June 3.

Licensed Thermal Power (MWt):

3411 4.

Nameplate Rating (Gross MWe):

1220.58 5.

Design Electrical Rating (Net MWe):

1148 6.

Maximum Dependable Capacity (Gross MWe):,*s 1148 1183 7.

Maximum Dependable Capacity (Net MWe):

8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9.

Power Level To Which Restricted, If Any (Net MWe): Five percent power 10.

Reasons For Restrictions, If Any:

Low power license (5%) granted by the NRC for start-up and low power testing.

This Month Yr-to-Date Cumulative 11.

Hours in Reporting Period N/A N/A N/A 12.

Number of Hours Reactor Was Critical N/A N/A N/A

13. -Reactor Reserve Shutdown Hours N/A N/A

___ N/A N/A 14.

Hours Generator On-Line N/A N/A 15.

Unit Reserve Shutdown Hours N/A N/A N/A 16.

Gross Thermal Energy Generated (MWH)

N/A N/A N/A 17.

Gross Electrical Energy Generated (MWH)

N/A N/A N/A 18.

Net Electrical Energy Generated (MWH)

N/A N/A N/A 19.

Unit Service Factor N/A N/A N/A 20.

Unit Availability Factor N/A

__ N/A N/A 21.

Unit Capacity Factor (Using MDC Net)

N/A N/A N/A 22.

Unit Capacity Factor (Using DER Net)

N/A N/A N/A 23.

Unit Forced Outage Rate N/A N/A N/A 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25.

If Shut Down At End Of Report Period, Estimated Date of Startup:

N/A 26.

Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 8/5/81 N/A INITIAL ELECTRICITY 9/5/81 N/A COMMERCIAL OPERATION 12/5/81 N/A (9/77) o 0

e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50/328 UNIT Sequoyah Two DATE 7/8/81 COMPLETED BY David Dupree TELEP110NE (615) 842-0295 MONTH June DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0-13 0

29 0

14 0

30 0

15 0

31 N/A 16 0

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.

50-328 UNIT NAME Sequoyah Two DATE 7/7/81 COMPLETED BY David Dupree REPORT MONTil June TELEPHONE (615) 842-0295 1

o eo 3 Licensee Cause & Corrective en m

No.

Date "o

.S &

.o.3 M Event 8"o Action to R

y@

g jty Report #

$3 8.3 Prevent Recurrence

$6 USc m"

0" a

o xmg a

N/A N/A N/A

.A N/A N/A N/A N/A N/A N/A I

Unit was given a 5% R.T.P. license on June 26, 1981.

l l

f'

/

e 1

2 3

4 F: Fcrced Reason:

1 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-Con t. of Existing 0161)

E-Opr'2 tor Training & License Examination Outage F-Admisistrative 5-Reduction G-Operational Error (Explain)

.9-Other 5

(9/77)

H-Other (Explain)

Exhibit I-Same Source

_~

i Plant' Maintenance Summary The following significant maintenance items were completed during the month of June, 1981:

Mechanical Maintenance 1.

Plugged five tubes in the Unit 1 excess letdown heat exchanger.

2.

Adjusted a loose stem nut on 1-PCV-62-73.

3.

Replaced the internals of 1-FCV-62-54.

4.

Staking the "C" component cooling water heat exchange was completed.

5.

Rebuilt the 2A-A and 2B-B centrifugal charging pumps.

6.

Rebuilt the "I" Glycol chiller compressor.

g Electrical Maintenance 1.

Inspected th-SMB-4 Limitorque operators for 4140 keys.

2.

The unit 2 polar crane trolley motor _ regulator was setup for proper trolley operation.

3.

Replaced the hand switch contact blocks on the main steam isolation valve 1-FCV-1-22.

4.

Adjusted the base adjuster follower on main generator voltage regulator.

1 Instrument Maintenance No instrument maintenance performed during the month.

Outage Maintenance Unit 1 i

1.

Modifications were completed on hangers H10-628, -687, and -328.

2.

Work continued to eliminate hanger problems per IE Bulletin 79-14.

Eighty-five repairs remain to be completed.

3.

Repairs were completed on letdown safety relief valve 1-RV-62-662.

4.

Modificaion was completed on hangers 1-CVCH-338, 1-CVCH-341, and 47A051-161.

5.

Environmentally qualified train B solenoids were installed on containment vacuum relief va1ves 1-FSV-30-46B, -47B, and -48B.

i

Outage Maintenance (Cont.)

Unit 2 1.

Completed the modifications to the fuel transfer system wafer valve.

2.

Completed the modifications of the purge air valves that allow the valves to operate at 50% travel instead of 90% travel.

3.

Installed inspection ports in the three CVCS letdown flow orifices.

4.

The preservice inspections of the 1/4, 1/2, and 1 inch snubbers are complete.

5.

Completed the installation of the pump on the reactor coolant drain tank 2A.

6.

Replaced the motor on the control r,od drive mechanism 2C-A.

N 7.

Completed various modifications to the manipulator crane.

8.

The following was completed in preparation for fuel loading:

A.

Replaced the hold down rings.

B.

Installed flange protector rings.

C.

NDT tested the reactor vessel nozzles.

D.

Cleaned the cavity and vessel.

E.

Radiographed welds on the CRDM housing at the RPV head.

F.

Flushed and borescoped the upper internals.

G.

Installed the drive rods.

H.

Repaired and tested the cold leg safety injection check valves.

Unit 0 or Items Affecting Unit I and 2 l

1.

Coating exposed surfaces of cable with flamastic in areas outside con-l tainment continued during the month.

2.

To satisfy footcandle level deficiencies additonal permanent yard security lighting fixtures were installed.

3.

Work continued to modify the Public Safety Services repeater system.

4.

Security access screens were installed on the exhaust fan housings of the auxiliary building and diesel generator building.

5.

Fire detectors have been installed above each ERCW pump.

e

O Outage Maintenance (Cont.)

+

6.

Repairs continue on ventilation dampers to reduce air inleakage.

7.

Overload heaters have been installed in the spare compartments on the safety related 480V boards.

8.

Work was completed to eliminate tube bundle vibration in the "C" com-ponent cooling heat exchanger.

9.

An isolation valve was installed in the 6" high pressure fire protection standpipe on elevation 714 AB to allow another section of the fire pro-tection system to be. changed out without affecting rest of the systems.

=

L i

9 o

e

• ?q APPENDIX A DOCUMENTATION FOR ODCM CHANGES

.sf For example, for 2 release points and minimum dilution flow this becomes, S

S b

( p x R ) -1

< 15,000 (2.10)

(g x R ) -1

+f f

2 y

y 2

2 1

2 ^. 2. 2 Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 2.1.1 were not exceeded.

A co' posite ' list of concentration (C ), by isotope, will be used m

g with the actual ' liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release.

The data will be substituted into Equation 2.3 to

- ~.

demonstrate compliance with the limits in Section 2.1.L This data and setpoints will be recorded in auditable records by plant personnel.

2.3 Dose 2.3.1 RETS Requirement Specification 3.11.~1.2 of the Radiological Effluent Technical Spe,cifi-cation (RETS) requires that the dose or dose commitment to an individual from radioactive materials in liquid effluents released to. unrestricted area,s from each. reactor (see Figure 2.2.1-1) sha.

be limited:

During any calendar quarter to < l.5 mrem to the total body and to i 5 a.

mrem to any organ, and b.

During any calendar year to 13 mrem to the total body and to-5,10 mrem to any organ.

To ensure compliance, cumulative dose calculations will be performed at 7

least once per month according to the following methodology.

2.3.2 Monthly Analysis 2

Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose.

If the projected dose exceeds the above 1.mits, the methodology in Section 2.3.3 will be implemented.

Re.

e

Calculated doses from liquid effluents (based upon historical release data) have been dominated by e.he Phosphoruc-32 (P-32) dose to the bone.

To further ensure accurate. dose assessment, ten additional nuclides are consiice.J. The 11 nuclides (listed below) contribute more than 95 per-cent of the dose to the total body and the two most critical organs (bone and gastro-intestinal tract (G.I. tract)) for both water and fish ingestion.

H-3 Co-58 Nb-95 P-32 Co-60 Xe-133 Mn-54 Sr-89 Cc-144 Rev.

Fe-55

.Sr-90 m

N.

A conservative calculation of the monthly dose will be donc according to the following procedure. First, the monthly operating report containing the release data will be obtained and 'the activities released of each of the a ove 11 radionuclides will be noted. This information will then be Ri ~

a used in the following cair.ulations.

2.3.2.1 Water Ingestion The dose to a.n individual from ingestion of water is described by the following equation.

yy 7

(DCF)1) x Ii, rem D) 0.95

(*

}

=

i=1 where:

D. = dose for the j organ from 11 radionuclides, rem.

l j = the organ of interest (bone, GI tract, or total body).

0.95 = conservative correction factor, considering only 11 radio-

gey, nuclides.

l e

i p e DCF

= adult ingestion dose commitment factor for the j organ ij from the i radionuclide, rem /pci, see attached as Table 2.1 th I = monthly activity ingested of the i radionuclide, pC1.

g I is described by g

I

=A V (30)

(*

}

f _ g C1 F d (7.34 x 10")

th A,= activity released of i radionuclide during the month, UCi.

g V = avergge rate of water consumption (730 ml/d per ICRP 23, p. 358) 30 = days per month F = average river flou at Cliickamauga Dam for the month (cubic feet per second) 0 u = fraction of river flow available for dilution (1/5) e 10 i

7.34 x 10

= conversion f rom cubic feet per second to milliliters per conth.

The dose equation then becomes

-3 11 1.57 x 10 (DCF) x A.;, mrem (2.13 )

D

=

i=1 1

considering the conversion factor from rem to mrem.

2.3.2.2 Fish Ingestion 3

1 The dose to an individual from the consumption of fish is described i

th by Equation 2.11.

In this case the activity ingested of the i _ radio-t n.aclide (I ) is described by g

^1 Di" j

T

, pCi (2.14)

=

F d (7.34 x 10'*)

where:

th A = activity released of i radionuclide during the month, pCi g

e 9

B = effective fish concentration factor of i radionuclido, g

uci/g pCi/ml, see attached as Table 2.1.

3 M = amount of fish eaten monthly (1.9x10 P F = average river flow at Chickamauga Dam for month (cubic feet per second) d = fraction of river flow available for dilution (1/5) to 7.34 x 10' = conversion from cubic feet per second to milliliters per month.

The dose equation then becomes 11

_=

y_m 1.36 x 10 A

D A xB x DCF

. mrem.

(2.15)

=

F g

i=1 considering the conversion factor from rem to mrem.

Rev If these calculated monthly doses exceed limits specified in Section 2.3.1 then a more accurate and complete calculation will be done as described in Section 2.3.3.

An annual check will 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, a new list of principal isotopes will be prepared.

2.3.3 Quarterly and Annual Analysis Acompletedoseanalysisutilizingthetotalestimatedliqu[dreleases for each calendar quarter will be performed and reported as required in Specifications 6.9.1.8 and 6.9.1.9.

This analysis will replace

. Rev.

previous estimates calculated in Section 2.3.2 and consists of the th following approach. The dose to the j organ from m radionuclides, D),

is described by h

D D

rem (2.16)

=

i=1 m

(DCF) x I, rem (2.17)

=

f i=1

'a

e where:

th D

= dose to the j organ from the i radionuclide, rem.

g j = the organ,of. interest (bone, GI tract, thyroid, liver, or 7

total body).

th (DCF)

= adult ingestion dose commitment factor for the j organ from the i radionuclide, rem /pci, see Table 2.1.

th I

= activity ingested of the i radionuclide, 4C1.

I for water i,ngestion is described by g

I

=A Vn (2.1,8) g f

Fd

~.. _

3 \\

for fish ingestion, I is described by' g

I

=A B M l

g 1 Ci

'(2.19)

F d where th A = activity released of i radim uclide during the period, g

pCi.

V = average water consumption (730 ml/d) n = number of days during the release period F = total river flow at location of interest for period (ml).

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

B = fish concentration factor (uC1/c, ) -

(pCi/ml)

M = amount of fish caten during period (= fraction of year x 50 lb/ year x 453.6 g/lb)

R At the end of the year an annual dose analysis will be performed by calculating the sum of the quarterly doses to the critical receptors.

2.4 Operability of Liquid Radwaste Equipment Specification 3.11.1.3 of the Radiological Effluent Technical Specifi-cations requires that the liquid radwaste system should be used to reduce e

e the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases to unrestricted areas (see Figure 2.1.1-1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.21 mrem to any organ.

Doses will be projected monthly to assure compliance.

O e

Od _..

w 0

a e

's 0

o

=

TABLE 2.'l INGESTION DOSE FACTORS AND FIS!! CONCENTRATION FACTORS s

NUCLICE

• • *** H ALF-LIFE (DAYSl * ** *** *~~~ *** NUMAN DOSE COMMITMENT F ACTORS " (REM /UCli *4 *

• • • • • • 8****

FISH ***********

CONCENIRAT10td BICLOGICAL RADioLO. BIOLOGICAL ErrECTlvE*-

BONE

'G1 TRACT ~ THYR 010 70TAL BODY ' LlvCR - ~ ~f FACTORS HALF-LIFE STABLE ErrECTlvE (DAYSI H-3 4.49Ee03 1.00E+01 9.98E*00 -* 9.77E-05 1.05E-04' l.05E-04' l.05E-04 1.05E-04 1.00E.00 1.00E+00 0.0 C-14 2 09E*06 1.00E*01 1.00E+0!

2.84E-03 5.68E-04 5.68E-04 5.68E-04 5.68E-04 4.55E*03 4.55E*03 0.0 NA-24 6 33E-01 1 10E*01' 5.99E-01 ~'~ 1.70E-03 1.70E-0 3 ' l.70E-03 t.70E-0 3 1.70E-03 1.00E*02 1.00E*02 0.0 P-32 1 43E+01 2.57E*02 1.35E*01 1.93E-01 2.17Z-02 7 47E-03 7.46E-03 1.20E-02 1.00E*05 1.00E*05 00 K-40 4.60E*ll ' 5.8 0E

• 01 5.80E*01 -

3.45E-02 ~ 0.0

~~3.45E-02 ~3.45E-02 ~3.45E-02~- 2.50E*03 2.50C+03 0.0 CR-51 2.78E*01 6.16E*02 2.66E+01 3.21E-06 6.69E-04 1 59E-06 2.66E-06 2.66E-06 2.00E*02 2.00E+02 0.0 MN-54 3 03E*02 1.70E*01 1.61E

• 01 -

8.83E-04 1.40E-02 8.83E-04' 8.72E-04 4.57E-03 4.00E*02 4.00E*02 0.0 NN-56 1 07E-01 1.70E*01 1.06E-01 2.04E-05 3.67E-G3 2.04E-05 2.04E-05 1.15E-04 4.00E*02 4.00E*02 0.0 FE-55 9.5CE*02 8.0 0 E + 0 2 ' 4.34E

• 0 2 "" " 2. 75E-0 3 1.09E-032.74E-04~ 4.43E-04 1.90E-03 1.00E+02 1.00E+02 0.0 FE-59 4.5eE*01 8.00E*02 4.31E*01 4.34E-03 3.40E-02 3.81E-03 3.91E-03 1.02E-02

't.00E*02 1.00E*02 0.0 C0-59 7.13E*01 9.5tE

• 00 ' 8.38E+ 00 "- 1.69E-0 3 "1.51E-n 2 ' t.69E-03 ' t.67E-03 ~ 7.45E-04 ~~ ' 5.0 0E*01 2.0SE*01 1 00E.02 CO-60 1 92E*03 9.50E*00 9.45E*00 4.73E-03 4.02E-02 4.73E-03 4.72E-03 2.14E-03 5.00E*01 4.75E*01 1.00E*02 t41-65 1 07E-01 6.67E*02 1.07E-01 5.2AE-04 1.74E-03 3 27E-05 3.13E-05 6.86E-05 1.00E*02 1.00E*02 1.0 Cu-04 5.31E-01 8.00E*01 5.27E-01 3.91E-05 7.10E-03 3 91E-05 3.91E-05 8.33E-05 5.00E*01 5.00E*01 0.0 7ti-65 2.45E*02 9.33E*02 1.94E

• 0 2 ~

4.84E-03 9.70E-03 7 13E-03 6.96E-03 1.54E-02 2.00E.03 1.42E*03 1.00E*02 24-699 5 75E-01 9.33E*02 5.75E-01 1.55E-04 2.91E-03 3.64E-05 3.64E-05 4.09E-04 2.00E*03 1.14E*01 1.00E*02 2N-69 3 96E-02 9 33E*02 3.96E-02 "- 1.03E-05 " 2.96E-06 ' "1 3 7E-06 ' t.37E-06 ' l.97E 2.0 0C 03 7.92E-01 1.00E*02 8R-92 1 4%E*00 8.00E*00 1.25E*00 2.26E-03 2.59E-03 2.26E-03 2.26E-03 2.26E-03 4.20E+02 4.20E*02 00 84-83 1 00E-01 8.00E*00 9.8SE 3.55E-05' 5.79E-05 3 55E-05 4.02E-05 4.02E-05 4.20E.02 4.20E*02 0.0 ER-84 2.21E-02 8.00E*00 2.20E-02 6.04E-05 4.09E-10 6 04E-05 5.21E-05,5.21E-05 4.20E.02 4.20E*02 0.0 ER-SS 2 00E-03 8.00E*00 2.0PE-03 ~' 5.17E-07 't.00E-21 5 17E-07 2.14E-06.2.14E-06 4.20E+02 4.20E*02 0.0

/3 KR-839 7.75E-02 1.00E*00 7.19E-02 0.0

'- 3.30E-03 00 *-"~ 0.0

'j ' 0. 0 - ' - ' ' - 1.00E*00 1.00E*00 0.0 1.46E-06 00 0.0 0.0 p.

FR-854 1 83E-01 1.00E*00 1.55E-01~~~ 0.0' 1.00E*r0 1.00E*00 0.0 I

KR-85 3.93E*03 1.00E*00 1.00E*00 0.0 4.62E-02 00 0.0 O.0 1.00E+00 1.00E 00 0.o RS-86 1 87E.01 4.50E* 01 ~ 1. 32E + 01 -- 9.83E-0 3 ^ 4.16E-03 ' 9.8 3E-0 3 ~ 9.8 3E-0 3 2.llE-02 2.00E+03 2.00E*03 0.0 RR-98 1 24E-02 4.50E*01 1.24E-02 3.34E-05 8.36E-16 3 34E-05 3.21E-05 6.05E-05 2.00E*03 2.00E+03 0.0 RB-89 1 07E-02 4.50E*01 1.07E-02

~ 2.86E-05* 2.33E-18 2.86E-05 2.82E-05 4.01E-05 2.00E+03 2.00E+03 0.0 SR-09 5.??E*01 1.30E*04 5.25E*01 3.08E-03 4.94E-02 9.22E-03 8.84E-03 8.84E-03 3.00E*01 1.04E*01 1.00E.02 50-93 1 01E.04 1.30E*04 5.68E+03 ~~ 7.58E*00 2.19E-01~ 1 76E+00'*l.86E*00 1.86E*00~~~3.00E*01 ~2.97E*01 1.COE*02 54-91 4.0 3E-01 1.30E.04 4.03E-01 5.67E-03 2.70E-02 1.92E-04 2.29E-04 2.29E-04 3.00E+01 1.20E-01 1.00E*02 50-92 1 13E-01 1.30E*04 1.13E-01~

2.15E-03 4.26E-02 6.69E-05 9.30E-05 9.30E-05 3.00E*01 3.39E-02 1.00E*02 SR-93 5.56E-03 1.30E*04 5.56E-03 6.39E-05 1.89E-03 8.90E-06 8.90E-06 8.90E-06 3.00E*01 1.67E-03 1.00E*02 Y-10 2 47E*00 1.40E*04 2.67E

• 0 0 * ' 9.62E-06 1.02E-01 2.57E-07 2.58E-07 2.58E-07 2.50E*01 2.53E*01 0.0 Y-914 3 5?E-02 1.40E*04 3.47E-02 9.09E-0A 2.67E-07 1.72E-09 3.52E-09 3.52E-09 2.50E*01 2.50E*01 0.0 Y-91 5.8PE*01 1.40E.04 5.86E*01 ~ 1.41E-04 ' 7.76E-02

• 3.66E-06 " 3.7 7E-0 6 3.77E-06 ~~ 2.50E+01 2.50E+PI 0.0 Y-92 1 47E-01 1.40E*04 1.47E-01

• 2.6et-06 8.50E-02 5.51E-08 '7.40E-08 7.40E-05 2.50E*01 2.50t 01 0.0 8.45E-07 1.4eE-02 2.47E-08 2.47E-05 2.47E-08 2.50E*01 2.5V

• 1 0.0 Y-93 4.29E-01 1.4eE*04 4.29E-01 2R-95 6.55E*01 4.50E*02 5.72E*01 3.04E-05 3.09E-02 6.38E-06 6.60E-06 9.75E-06 3.33E*00 3.33E*00 0.0 2R-97 7 09E-01 4.50E*02 7.07E-01

- 1.68E-06 1.05E-01 1 55E-07 1.55C-07 3.39E-07

.3.33E+00 3.33Ea00 0.0 t48-95%

3.750 00 7.60E+02 3.73E*00 5.86E-07 3.55E-02 2.8BE-07 2.88E-07 4.63E-07 3.00E+04 3.00Ev04 0.0 NO-95 3.50E*01 7.60E*07 3.35E*01 -"*6.22E-06 2.10E?02 1 83E-06 3.86E-06 3.46E-06 3.00E*04 3.00E*04 0.0

1. A-9 7 5 00E-02 7.60E+02 5.00E 4.90E-08 2.10E-03 4.60E-09 4.60E*09 1.27E-05 3.00E*04 3.00E.04 0.0 MO-99 2.7eE*00

%.00E*00 1.79E*00 8.47E-04 C.v9E-03 8.47E-04 8.20E-04 4.31E-03 1.00E*01 1.00E 01 0.0 1C-999 2.52E-01 1.00E*00 2.0lE-01 2.47E-07 4.13E-04 9 37E-06 8.89E-06 6.98E-07 1.50E*01 1.50E*01 0.0 1C-97 7.74t*07 1.00E*00 1.00E*00 1.27E-04 1.R9E-02 5.06E-65 5.06E-05 1.86C-04 1.50E*01 1.50E*01 0.0 TC-101 9.93C-03 1.00E*00 9.83E-03 2.54E-07 1.10E-18 3.60E-06 3.59E-06 3.66t-07

't.50E 01 1.50E*01 0.0 RU-103 3.96E.01 7.30E+00 6.16E*00 - *1.85E-04 2.16E-02 7.98E-05 7.95E-05 7.97E-05' l.00E*01 1.00E+01 0.0 RU-106 3.6eE.02 7 30E+00 7 16E*00 2.75E-01 1.78E-01 3.50E-04 3.48E-04 3.48E-04 1.00E*01 1.00E*01 0.0 RH103M 3.96F-02 7.30E*00 3.94E-02 1.67E-07 1.21E-04 4.99E-05 4.99E-08 7.21E*07 1.00E*01 1.00E*01 0.0 AG1104 2 53C.02 5.00E*00

.90E*00 1.60E-04 6.04E-02 8.78E-05 8.79E-05 1.48E-04 2.00E*00 2.00E*00 0.0

^

50-124 6.02E*01 3.80E*01 2.33E+01 2.80E-03 7.95E-02 6.79E-06 1.llE-03 5.30E-05 1.00E*00 1.00E*00 0.0 50-125 9.96E*02 3.90E*01 3.66E*01 1.79E-03 1.97E-02 1.A2E-06 4.26E-04 2.40E-05 1.000 00 1.00E*00 0.0

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.. e 1.2.1 Noble Cases

, Step 1 Doses will be calculated using the methodology described in this step.

If any limits are exceeded, step 2 will be performed.

Equations and assumptions for calculating doses from releases of noble gases are as follows:

Assumptions 1.

Doses to be calculated are gamma and beta air doses.

-g

~

2.

The highest annual-average X/Q based on licensing meterology for

. ground-level releases for any of fsite location will be used.

1 3.

No credit is taken for radioactive decay.

4.

For gamma doses, releases of Xe-131m, Xe-133, Xc-135, Ar-41, and i

Kr-88 are considered.

Rev 5.

For beta doses, releases o,f Xc-131m, Xe-133, Xe-135, Ar-41, and Kr-85 are considered.

6.. Dose factors are calculated using data from TVA's nuclide library.

7.

The calculations extrapolate doses assuming that only 90 percent of,,"

Rev.

total dose was contributed.

8.

A semi-infinite cloud model is used.

i 9.

Building wake effects on effluent dispersion are considered.

Equations Fcr determining the gamma dose to air:

= IX D

7 Q DFy (1.13)

Y 0.9 k.15x10 3

i i

where:

i

[#"%

D = gamma dose to air, mrad.

4 __

y

,,.,,n4 v-

.e nm,-

's i r

)(/Q = highest annual-average relative concentration, 5.13 x 10 '

~

3 s/m 10' = UCi/Ci.

0.9 = fraction of total gamma dose expected to be contributed by Rev.

these nuclides.

7 3.15x10 - s/yr.

Q = monthly release of radionuclide i, C1.

g

= gamm$-to-air dose factor for radionuclide 1, mrad /yr per DFyg 3

UCi/m -(Tabic 1.5).

This equation then reduces to

~7 D = 1.81 x 10 Q DFy (1,14)

~:-., Q

~

For determining the beta dose to air:

f I

=-(X/Q) 10' D

7 0 DF3 (1.15) g 0.9 3

N.15x10}

1 g

where:

i Dg = beta dose to air, mrad.

)(/Q = highest annual; average relative concentration, 5.13x10 '

~

10' =.uc$/Ci.

0.9 = fraction of total beta dose expected to be contributed by these

= s/yr. nuclides.

7 3.15x10 Q

= monthly release of radionuclide i, C1.

g DFB

= beta-to-air dose factor for radionuclide 1, mrad /yr per 3

UCi/m (Table 1.5).

l This equation then reduces to:

\\'

D = 1.81 x 10_7 B

Q DFS (1.16) g i

4

X

= air concentration of radionuclide i in sector n, DCL/m 3 DFy. = gamma-to-air dose f actor for radionuclide i, mrad /yr per 1

3

~

UCi/m (Table 1.5).

t = time period considered, yr For determining the beta dose to air:

D

=t X

DFS (1.25)

Bn m

ni i

where:

D

= beta dose to air for sector n, mrad.

6n

^

=

3 X

air concentration of radionuclide i in sector n, UCi/m DFS beta to air dose factor for radionuclide i, mrad /yr per

=

3 UCi/m time period considered, yr t

=

m The sector having the highest total dose'is then used to check.

compliance with specification 3,.11.2.2.

1.2.2 Iodines and Particulates Step 1 Doses will be calculated using the methodology described in this,"

step.

If any limits are exceeded, step 2 will be performed.

Equations and assumption's for calculating doses from releases of iodines and particulates are as follows:

Assumptions 1.

Doses are to be calculated for the infant thyroid from milk ingestion and for the child bone f rom vegetable ingestion.

gey, 2.

Ecal cow locations are considered for the milk pathway and nearest-resident locations with home-u'se gardens are considered for the vegetabic pathway.

mnn ~,

-,m c

-. - - - - -, ~

---

"~ww m'~

~

• ,o 3.

The highest annual-average D/Q's based on licensing meteorolor,y for o

ground-level releases will be used for I-131 and Sr-90 doses.

t..

Rev 4.

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

-5.

No credit is taken for radioactive decay.

6.

Releases of I-131 and C-14 are considered for the milk pathway. Sr-90 releases are considered for the vegetable pathway.

Rev The' calculations ' extrapolate doses assuming that only 90 percent of the

~

7.

e total dose'was contributed.

8.

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

's 9.

The cow is assumed to graze on pasture grass for the whole, year.

Equations For determining the thyroid dose from milk 'ngestion of I-131:

Q DF D/Q 131 131 x 10' DTH131 3.15x10' (1.26)

=

where:

DTH

= thyroid dose from I-131, mrem.

y37 Q

= m nthly release of I-131, C1.

131 DF

= I-131 milk ingestion dose factor to infant, mrem /yr per y31 2

pCi/m -s (Table 1.7)

Rev.

D/Q = relative deposition rate, 2.94x10 m 2, 7

3.15x10 = s/yr.

10' = pCi/Ci.

For determining the thyroid dose from milk ingestion of C-14:

014 14 xQ (1. 2 7)

DTH

=

14 3.15x10'

<-s i

k 4.-em$rc r.* - c.mcN n.... ten

.,.-v.-..

v.- -

e s

• O where:

thyroid dose f rom C-14, mrem.

DTli

=

g Qg = monthly release of C-14, Ci.

g C-14 milk ingestion dose factor, mrem /yr per pCi/cm

=

3 DF Re' (Table 1.7)

X/Q = relative dispersion factor, 1.76x10 ' s/m*.

7 s/yr.

315x10

=

For determining the total thyroid dose:

)

131 +

14 DTil =

(1.28) 0.9

~.

where:

DTH = thyroid dose, mrem.

1

= thyroid dose from release of I-131, mrem.

131 DTH

= thyroid dose from release of C-14,' mrem.

g 0.9 = fraction of total' thyroid dose expected to be contributed Res by these radion'uclides.

s

. For determining the bone dose from vegetable ingestion:

9 x 10' (1.39) s s

BC, =3.15x10'(0.9) where:

DBC, = bone dose to child from Sr-90, mrem.

Rev Q, = monthly release of Sr-90, C1.

DF, = Sr-90 vegetable ingestion dose factor to child, 12 1.62x10 mrem /yr per pCi/m*-s.

D/Q = relative deposition rate, 7.32x10 'm 2,

~

7 3.15x10 s/yr.

=

10' = pt,i/Ci.

1 0.9 =' fraction of total bc,ne dose cxpected to be contributed by Sr-90. mm __

. - - rt

b a*

o', o Step 2 j

This methodology is to be used if the calculations in step 1 yield doses that exceed applicable' limits.

Deses for releases o'f iodines and particulates shall be calculated

^using the methodology in Section 1.1.1, step 1, pa.-t B, with the following j

exceptions:

4 l.

All measured radionuclide releases will be tsad.

i 2.

Lase will be evaluated at real cow locations and will consider actual grr. zing information.

The receptor having the highest. total dose is then used to check

'N compliance with specification 3.11.2.3.'

4 d

e e

1 e

es i

j l

I l

l t

3lD s

j *

- ~ ~

-,-,,-a,--

~-

.