Text

Combined 2002 Annual Radioactive Effluent Release Report, Attachment 1, Table 1A Through Off Dose Calculation Manual, Revision 23
	ML031290160
Person / Time
Site:	Crane
Issue date:	04/30/2003
From:	George Gellrich; AmerGen Energy Co
To:	; Document Control Desk, NRC/FSME
References
	-RFPFR, 5928-03-20051
	Download: ML031290160 (117)
	v • d • e

a 2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Summary of Radioactive Liquid and Gaseous Effluents Released from TMI during 2002

TABLE IA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES TMI-1 I

I 2002 1

2002 1

2002 rEST. TOTALl I UNITS 11STQUARTER I 2NDQUARTER 3RD QUARTER 14TH QUARTERI ERROR % l A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE Ci 2.22E-03 8.44E-03 5.82E-03 4.35E-03 1

25%

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec 2.85E-04 1.07E-03 7.32E-04 5.47E-04 1

3. PERCENT OF TECH SPEC LIMIT B. IODINES

1. TOTAL IODINE 1-131

[

Ci

]

6.37E-08 5.87E-08 1.11 E-07 1.02E-07 1

25%

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec 8.19E-09 1

7.46E-09 1.40E-08 1.29E-08

3. PERCENT OF TECH SPEC LIMIT

%I 1

C. PARTICULATES

1. PARTICULATES WITH HALF-LIVES > 8 DAYS Ci

<1.E-04

<1.E-04 25%

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec NA NA NA NA

3. PERCENT OF TECH SPEC LIMIT E-E

4. GROSS ALPHA RADIOACTIVITY ci

<1.E-11

<1.E-_1

<1.E-1 1 D. TRITIUM

11. TOTAL RELEASE

[

Ci 4.85E+01 1.44E+01 3.86E+01 1

2.21E+01 25%

12. AVERAGE RELEASE RATE FOR PERIOD

13. PERCENT OF TECH SPEC LIMIT uCi/sec I

6.24E+00 I

1.84E+00 I

4.86E+00 2.79E+00

6.

'4 4

4 I

I I

% ODCM LIMITS: LISTED ON DOSE

SUMMARY

TABLE NOTE: ALL LESS THAN (<) VALUES ARE IN uCi/mI

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

GASEOUS EFFLUENTS - GROUND LEVEL RELEASES TMI-1 I

CONTINUOUS BATCH I

CONTINUOUS BATCH lNUCLIDES RELEASEDl UNIT lQUARTER I QUARTER 2 QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4lQUARTER 3 QUARTER 41

1. FISSION GASES AR 41 Ci

<3 E-07

<3 E-07 3.85E-03

<3 E-07

<3 E-07 KR 85M Ci

<5 E-08

<5 E-08 KR 85 Ci

<2 E-05

<2 E-05 KR 87 Ci

<1 E-07

<1 E-07 KR 88 Ci

<2 E-07

<2 E-07 XE131M Ci

<1E-6

<1E-6 XE 133 Ci

<2 E-07

<2 E-07 2.22E-03 4.59E-03

<2 E-07

<2 E-07 5.82E-03 4.35E-03 XE133M Ci

<3 E-7

<3 E-7 XE 135M Ci

<5 E-07

<5 E-07 XE 135 Ci

<5 E-08

<5 E-08 XE 138 Ci

<5 E-07

<5 E-07 TOTAL FOR PERIOD Ci NA NA 2.22E-03 8.44E-03 NA NA 5.82E-03 4.35E-03

2. IODINES l

I 131_

I ci_1_6.37E-08 1 4.87E-08 1 <1 E-08 I 9.95E-09 1 1.11E-07 l 1.02E-07

<1 E-08 I

<1 E-08 1

I I 133 Ci..

I C

<1 E-08 7.68E-07

<1 E-08 I

<1 E-08 I 1.33E-06 1 9.46E-07

<1 E-08

<1 E-08 lTOTAL FOR PERIOD I Ci 6.37E-08 I 8.17E-07 I NA I 9.95E-09 I 1.44E-06 I 1.05E-06 I NA NA

3. PARTICULATES C058 C;

I <1 E-11 I <1 E-11 I <1 E-08 I <1 E-08 I <1 E-11 I <1 E-11 I <1 E-08 I <1 E-08 CS 137 Ci

<1 E-1I

<1 E-08

<1 E-11I

<1E-11

<1 E-08 IE-08 NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/mI

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES TMI-1 2002 2002 l

2002

[

2002 1 EST. TOTAL I I UNITS I 1ST QUARTER 12ND QUARTER I3RD QUARTER I 4TH QUARTER I ERROR % I A. FISSION AND ACTIVATION PRODUCTS

__I__

_A___

_A

IIor, 04CI i.T OTAL RELEASES (NOT INCLUDING TRITIUM, GASES, APA

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD

3. PERCENT OF APPLICABLE LIMIT r',

I I 771F--lA I

-1 85E1-041L lnvrt-U4 I

I. I U"-Ue I

-I I

I a.I I I_

I I

.4 1

AA

_1.1 I

,._1 1iCilmi 3.25E-1 1 Z1. ftt-1 I Z-.3Ut-I I I

I. I UL-I I InI I

1/0 I

__£I B. TRITIUM

, C.

l x

znn I

9 R1.Lfln1 I

r nflrn1 I

A R5F+01 1

25%1 1 TOTAL RELEASE

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD

3. PERCENT OF APPLICABLE LIMIT I 1 n M:)CTUU v.V I WTU I

w...,,..V r;n f

l 7--nR I

7 Q'F.fnR I 7 495-06 I

.1 ;. m I

MUU V.Vt -

VV t

. VV

-vv i""

1 1

v-v I

1 I

°/n I

lr

_I I _

C. DISSOLVED AND ENTRAINED GASES I

r; I

-4C nA 1

1 R1F nl I

<1i F-rd I

<I-E-04 l

25%1

1. TOTAL RELEASE

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD

3. PERCENT OF APPLICABLE LIMIT Sl c--u MA -

li Ir NA N A

"/m1.11 I-IR_1 NAN 11111 INI

~-I U~l~l,,;\\_,___._

1

%I SI

_II D. GROSS ALPHA ACTIVITY

1. TOTAL RELEASE I

Ci I

<1.E-07 I

<1.E-07 1

<1.E-07

<1.E-07 1

25%

[E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) l liters r 8.89E+06 I

7.66E+06 I 1.04E+07 I

6.83E+06 I

10%l IF. VOLUME OF DILUTION WATER USED I liters 5.45E+09 6.71E+09 7.56E+09 I

6.48E+09 I

10%l

% ODCM LIMITS: LISTED ON DOSE

SUMMARY

TABLE NOTE: ALL LESS THAN (<) VALUES ARE IN uCi/mI

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

LIQUID EFFLUENTS TMI-1 1

I r'.nNTINUOUS1 l BATCH CONTINUOUS BAICHN NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 CR 51 Ci

<5 E-07

<5.E-07

<5.E-07 MN 54 Ci

<5 E-07

<5.E-07

<5.E-07 FE 59 Ci

<5 E-07

<5.E-07

<5.E-07 CO 58 Ci

<5 E-07

<5 E-07 1.12E-05

<5 E-07

<5 E-07 7.31 E-06

<5.E-07 CO 60 Ci

<5 E-07

<5 E-07 3.08E-06

<5.E-07 ZN 65 Ci

<5 E-07

<5.E-07

<5.E-07 SR 89 Ci

<5 E-08

<5 E-08 SR 90 Ci

<5 E-08

<5 E-08 2.27E-06

<5 E-08

<5 E-08 2.51 E-06

<5 E-08 ZR 95 Ci

<5 E-07

<5 E-07 NB 95 Ci

<5 E-07

<5 E-07 MO 99 Ci

<5 E-07

<5 E-07 TC 99M Ci

<5 E-07

<5 E-07 1 131 Ci

<1 E-06

<1 E-06 CS 134 Cc

<5 E-07

<5 E-07 CS 137 Ci 1.49E-04 1.63E-04 1.74E-05 2.05E-05 1.18E-04 4.43E-05 5.86E-05 6.58E-05 BA 140 Ci

<5 E-07

<5 E-07 LA 140 Ci

<5 E-07

<5 E-07 CE 141 Ci

<5 E-07

<5 E-07 FE 55 Ci

<1 E-06

<1 E-06 TOTAL FOR PERIOD Ci 1.49E-04 1.63E-04 2.86E-05 2.28E-05 1.18E-04 4.43E-05 7.15E-05 6.58E-05 XE 133 Ci

<1.E-04

<1.E-04 1.81 E-05

<1.E-04

<1.E-04 1.84E-06

<1.E-04 XE 135 Ci

<1.E-04

<1.E-04 1.63E-06

< 1.E-04 NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/mI

SUPPLEMENTAL INFORMATION FACILITY:

TMI UNIT I LICENSE:

DPR 50-289

1. REGULATORY LIMITS - - - REFER TO TMI OFFSITE DOSE CALCULATION MANUAL A. FISSION AND ACTIVATION GASES:

B. IODINES:

C. PARTICULATES, HALF-LIVES > 8 DAYS:

D. LIQUID EFFLUENTS:

2. MAXIMUM EFFLUENT CONCENTRATIONS - - - TEN TIMES 10 CFR 20, APPENDIX B TABLE 2 PROVIDE THE MAXIMUM EFFLUENT CONCENTRATIONS USED IN DETERMINING ALLOWABLE RELEASE RATES OR CONCENTRATIONS.

A. FISSION AND ACTIVATION GASES:

B IODINES:

C. PARTICULATES, HALF-LIVES > 8 DAYS:

D. LIQUID EFFLUENTS:

3. AVERAGE ENERGY PROVIDE THE AVERAGE ENERGY (E-BAR) OF THE RADIONUCLIDE MIXTURE IN RELEASES OF FISSION AND ACTIVATION GASES, IF APPLICABLE E-BAR BETA =

E-BAR GAMMA =

E-BAR BETA AND GAMMA =

1.69E-01 MeV 2.74E-01 MeV 4.42E-01 MeV

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY PROVIDE THE METHODS USED TO MEASURE OR APPROXIMATE THE TOTAL RADIOACTIVITY IN EFFLUENTS AND THE METHODS USED TO DETERMINE RADIONUCLIDE COMPOSITION:

A. FISSION AND ACTIVATION GASES: HPGE SPECTROMETRY, LIQUID SCINTILLATION B. IODINES:

HPGE SPECTROMETRY C PARTICULATES HPGE SPECTROMETRY, GAS FLOW PROPORTIONAL, BETA SPECTROMETRY D. LIQUID EFFLUENTS:

HPGE SPECTROMETRY, LIQUID SCINTILLATION

5. BATCH RELEASES PROVIDE THE FOLLOWING INFORMATION RELATING TO BATCH RELEASES OF RADIOACTIVITY MATERIALS IN LIQUID AND GASEOUS EFFLUENTS.

A. LIQUID (ALL TIMES IN MINUTES)

QUARTER I QUARTER 2 QUARTER 3 QUARTER 4

1. NUMBER OF BATCH RELEASES:

7 3

17 7

3. MAL TIME PERIOD FORA BATCH RELEASE:

1796 83 5

4407 1797

3. MAXIMUM TIME PERIOD FOR A BATCH RELEASE:

276 300 285 325

4. AVERAGE TIME PERIOD FOR BATCH RELEASES:

256 278 259 256

5. MINIMUM TIME PERIOD FOR A BATCH RELEASE:

205 255 230 160

6. AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF EFFLUENT INTO A FLOWING STREAM: (CFM)

I 1.75E+06 3.16E+06 3.62E+05 1.99E+06 B. GASEOUS (ALL TIMES IN MINUTES)

1. NUMBER OF BATCH RELEASES:

3 6

4 3

2. TOTAL TIME PERIOD FOR BATCH RELEASES:

2370 2983 2830 2225

3. MAXIMUM TIME PERIOD FOR A BATCH RELEASE:

830 763 745 780

4. AVERAGE TIME PERIOD FOR BATCH RELEASES:

790 497 707 741

5. MINIMUM TIME PERIOD FOR A BATCH RELEASE:

750 7

680 720

6. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES: 2. TOTAL ACTIVITY RELEASED: (CURIES)

N/A N/A N/A N/A B. GASEOUS

1. NUMBER OF RELEASES: 2. TOTAL ACTIVITY RELEASED: (CURIES)

N/A N/A N/A N/A

TABLE IA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES TMI-2 11 2002 1

2002 2002 1

2002 IEST. TOTALl I UNITS liST QUARTERI 2ND QUARTER I 3RD QUARTER 14TH QUARTE ERROR% I A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE Ci

<LLD

<LLD 25%

I

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec N/A N/A N/A N/A

3. PERCENT OF TECH SPEC LIMIT B. IODINES NOT APPLICABLE FOR TMI-2 C. PARTICULATES

1. PARTICULATES WITH HALF-LIVES> 8 DAYS ci

<LLD

<LLD 25%

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec N/A

<N/A

3. PERCENT OF TECH SPEC LIMIT

I

4. GROSS ALPHA RADIOACTIVITY Ci

<LLD

< <LLD

<LLD D. TRITIUM U

_Y sljAN t=4lcccn I So

11. TOTAL RELEASE C, I Z. -

I

4. t-I I

12. AVERAG RELEASE RATE FOR PERIOD

[3. PERCENT OF TECH SPEC LIMIT I

uci/sec I

3.8E5-Uz 5.51 t-Uz I

1.ojt-UZ I

I.Uat-U3 I -

I 4

.1 I

I I

.1 1

1 i

1# BATCH RELEASES I

0 1

% ODCM LIMITS: LISTED ON DOSE

SUMMARY

TABLE NOTE: ALL LESS THAN (<) VALUES ARE IN uCi/mI

I TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES TMI12 2002 I

CONTINUOUS MODE I

BATCH MODE I

CONTINUOUS MODE I

BATCH MODE (NUCLIDES RELEASED UNIT 11ST QUARTERI 2ND QUARTER 11ST QUARTERPND QUARTE 3RD QUARTER14TH QUARTER13RD QUARTERT4TH QUARTER

1. FISSION GASES KRYPTON-85 Cl

<8.OOE-6

<8.00E-6 1<8.O0E-6 KRYPTON-85M Ci

<5.OOE-8

<5.OOE-8 KRYPTON-87 Ci

<8.OOE-8

<8.00E-8

<8.OOE-8

<8.OOE-8 KRYPTON-88 Cl

<1.OOE-7

<1.OOE-7 XENON-133 Ci

<8.OOE-8

<8.00E-8

<8.OOE-8

<8.OOE-8 XENON-135 Ci

<5.OOE-8

<5.O0E-8

<5.OOE-8

<5.OOE-8 XENON-135M Ci

<5.OOE-7

<5.OOE-7 C5.00E-7

<5.OOE-7

<5.OOE-7 XENON-138 Ci

<3.OOE-7

<3.OOE-7 AR-41 Cl

<1.OOE-4

<1.OOE-4 TOTAL FOR PERIOD Cl N/A N/A N/A N/A N/A N/A N/A N/A

2. IODINES NOT APPLICABLE TO TMI-2

3. PARTICULATES STRONTIUM-90 Ci

<1.OOE-11

<1.OOE-11 N/A N/A

<1.OOE-11

<1.OOE-11 N/A N/A COBALT 60 Ci

<1.OOE-10

<1.OOE-10 N/A N/A

<1.OOE-10

<1.OOE-10 N/A N/A ANTIMONY 125 Ci

<1.OOE-10

<1.OOE-10 N/A N/A

<1.00E-10

<1.OOE-10 N/A N/A CESIUM-134 Ci

<1.OOE-10

<1.OOE-10 N/A N/A

<1.OOE-10

<1.OOE-10 N/A N/A CESIUM-137 Ci

<1.OOE-10

<1.OOE-10 N/A N/A

<1.OOE-10

<1.OOE-10 N/A N/A TOTAL FOR PERIOD Ci N/A N/A N/A N/A N/A N/A N/A N/A

4. TRITIUM lTRITIUM ClI 2.95E-01 I

4.33E-01

<1.OOE-6

<1.00E-6 1.22E-01 5.59E-02

<1.OOE-6

<1.0OE-6 NOTE: ALL LESS THAN (<) VALUES ARE IN uCi/ml

6' TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES TMI-2 I

2002 l

2002 1

2002 l EST. TOTAL I UNITS JISTQUARTER12NDQUARTERI3RDQUARTER14THQUARTERI ERROR%

l A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASES (NOT INCLUDING TRITIUM, GASES, ALPHA) ci

<LLD

<LLD J9.79E-06

<LLD

]25%1

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/mI N/A N/A J1.28E-12 N/A

3. PERCENT OF APPLICABLE LIMIT

/

l E

B. TRITIUM

1. TOTAL RELEA SE C

i

<LLD 1.42E-05 5.13E-04

<LLD 25%

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ml N/A 2.12E-12 6.71E-11 N/A 3.PERCENT OF APPLICABLELIMIT C. DISSOLVED AND ENTRAINED GASES

1. TO TAL RELEASE ci

<LD

<LLD

<LD

<LLD 25%1

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uc/Am N/A N/A T N/A N/A

3. PERCENT OF APPLICABLE LIMIT l

D. GROSS ALPHA ACTIVITY

1. TOTAL RELEASE Ci

<LLD

<LLD 25%

E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

F. VOLUME OF DILUTION WATER USED liters I NONE I

2.63E+03 I

1.96E+04 I

1.35E+05 I

1 0%

l liters I

5.45E+09 l

6.71 E+09 I

7.64E+09 I

6.48E+09 I

1 0%l INUMBER OF BATCH RELEASES I

0 l

1 l

4 l

1 l

% ODCM LIMITS: LISTED ON DOSE

SUMMARY

TABLE NOTE: ALL LESS THAN (<) VALUES ARE IN uCi/mI

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS TMI-2 2002 CONTINUOUS MODE BATCH MODE CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 1ST QUARTER 2ND QUARTER 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER 3RD QUARTER 4TH QUARTER CO 60 Ci

<5.OOE-7

<5.00E-7

<5.OOE-7

<5.OOE-7 SR 90 Ci

<5.OOE-8

<5.00E-8

<5.OOE-8

<5.OOE-8 1.08E-06

<5.OOE-8 SB 125 Ci

<5.00E-7

<5.OOE-7

<5.OOE-7 CS 134 Ci

<5.00E-7

<5.OOE-7

<5.00E-7 CS 137 Ci

<5.00E-7

<5.OOE-7

<5.00E-7

<5.OOE-7 8.71 E-06

<5.OOE-7 H-3 Ci

<1.OOE-5

<1.OOE-5 1.42E-05

<1.OOE-5

<1.OOE-5 5.13E-04

<1.OOE-5 TOTAL FOR PERIOD Cl 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-05 0.OOE+00 0.OOE+00 5 22E-04 0.OOE+00 NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/ml 2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Solid Waste Shipped Offsite during 2002

TMI-1 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste UNIT 12 month EST. Total period Error %

a. Spent resins, filter sludges, m3 56.5 m3 25%

Evaporator bottoms, etc.

Ci 1.58 Ci

b. Dry compressible waste, m

373.9 m3 25%

contaminated equipment, etc.

Ci

.9 Ci

c. Irradiated components, control ml N/A N/A rods, etc.

Ci

d. Other (describe): Mixed Waste m

2.75 m3 25%

Ci

.031 Ci

2. Estimate of major nuclide composition (by type of waste)

a. H3 28.9%

Co58 21.8%

Ni63 20.3%

Cs137 23.8%

b. Co58 44.1%

Ni63 9.5%

Cs137 40%

c. N/A d Co58 44.1%

Ni63 9.5%

Cs137 40%

3. Solid Waste Disposition Mode of Transportation Destination Number of Shipments See attached for this information l

B. Irradiated Fuel Shipments (Dispositi on)

Number of Shipments Mode of Transportation Destination N/A

Ir WASTE SHIPPED AS FOLLOWS A.1.a Four (4) - Poly Liners @ 150 ft3 each - Evaporator Bottoms Nineteen(19) - Steel Boxes @ 80 ft3 each-Dewatered Powdex Resin A.1.b Eleven (11) - Steel Cargo Containers @ 1040 ft3 each-noncompacted DAW Fifteen (15) - Steel Boxes @ 92 ft3 each - Metal/noncompacted DAW Twelve (12) Steel Drums @ 7.0 ft3 each - noncompacted DAW Five (5) - Steel Boxes @ 60ft3 each - noncompacted DAW A.1.c No Shipments of material in this category for this report period A-1-d Thirteen (13) Steel drums at 7.0 ft3 each - Mixed Waste Three (3) Steel Drums @ 2.0 ft3 each - Mixed Waste

e 3

A.3.a Four Shipments Kindrick Trucking/ Cask Duratek -Oak Ridge,TN A.3.b Four Shipments Three Shipments Two Shipments Two Shipments One Shipment One Shipment Hittman Transport/Flatbed TSMT/Flatbed Kindrick/Flatbed Kindrick Trucking/Flatbed R&R Trucking/Flatbed Kindrick Trucking/Flatbed Duratek-Oak Ridge,TN Duratek-Oak Ridge,TN U.S.Ecology-Oak Ridge,TN.

RACE,LLC-Memphis,TN RACE LLC - Memphis,TN.

ALARON-Wampum. Pa A.3.c No Shipments of material in this category for this report period A.3.d One Shipment Kindrick/ Closed Van Perma-Fix-Gainesville,FL.

ALL SHIPMENT WERE TYPE A-LSA-11

7 TMI-2 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS I

I I

A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste UNIT 12 month EST. Total period Error %

a. Spent resins, filter sludges, m3 N/A N/A Evaporator bottoms, etc.

Ci

b. Dry compressible waste, m3 64.9 m3 25%

contaminated equipment, etc.

Ci

.02 Ci

c. Irradiated components, control mJ N/A N/A rods, etc.

Ci

d. Other (describe): N/A m

N/A N/A Ci

2. Estimate of major nuclide composition (by type of waste)

a. N/A b.Cs137 70.4%

Sr9O 27.7%

Ni63 1.39%

c. N/A d.

3. Solid Waste Disposition Mode of Transportation Destination Number of Shipments See attached for this information B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A

WASTE SHIPPED AS FOLLOWS A.1.a No Shipment of spent resin. filter sludges, or evaporator bottoms A.1.b Two(2) Steel Cargo Containerss @ 1040 ft3 each-noncompactable DAW One(l) Steel box @ 92 ft3 - Metal One(1) Steel Liner @ 120 ft3-Metal A.1.c No Shipments of material in this category for this report period A-1-d No Shipments of material in this category for this report period

.1 J

A.3.a No Shipments of material in this category for this report period A.3.b Two Shipments R& R Trucking/Flatbed RACE LLC-Memphis,Tn A.3.c No Shipments of material in this category for this report period A.3.d No Shipments of material in this category for this report period

ALL SHIPMENT WERE TYPE A-LSA-11 2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Summary of Unplanned Releases from the TMI Site During 2002 There were no unplanned releases to unrestricted areas from either the TMI-1 or TMI-2 site during 2002.

2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Changes to the Process Control Program and the Offsite Dose Calculation Manual during 2002, And a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census

1.

Changes to the Process Control Program The Process Control Program for Radioactive Waste is implemented in accordance with Procedure RW-AA-1 00. This procedure provides the boundaries and parameters for the preparation of procedures for processing, sampling, analysis, packaging, storage and shipment of solid radwaste. It also provides the local, state, federal, and burial site requirements.

Revision 2 of RW-AA-1 00 became effective on January 11, 2002. The changes associated with revision 2 are editorial in nature. The changes provide clarification to ensure compliance with the applicable regulations for preparation of Radioactive Waste for transportation. These changes do not change the intent of the previous revision.

7

2.

Changes to the Offsite Dose Calculation Manual during 2002 The Offsite Dose Calculation Manual (ODCM) was modified once during 2002. These changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations. The level of effluent controls-required by 10 CFR 20.1301, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 was not reduced and the accuracy or reliability of effluent, dose or setpoint calculations was not adversely impacted for the reasons stated below.

Revision 23 of the ODCM was issued on March 19, 2002. Revision 23 made the following changes to the ODCM:

Added a note to make clear the LLD needed for noble gas in liquid effluent.

Correct the table of context Change ventilation indicator from pen to point due to changing from a chart recorder to a digital recorder.

To make clear when the 30 day clock applies when the Unit 2 effluent ventilation flow rate is out of service.

3.

A listing of new locations for dose calculations and/or environmental monitoring identified by the land use census Based on the results of the 2002 land use census, no changes to the radiological environmental monitoring program or the dose model are required.

2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Instrumentation not returned to Operable status within 30 days during 2002 There was no instrumentation not returned to operable status within 30 days per the TMI ODCM Part 1, Sections 2.1.1.b and 2.1.2.b and Part 2, Section 2.1.2.b during 2002.

2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Annual Summary of Hourly Meteorological Data for 2002

THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS: A WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 2

11 10 23 16 31 50 41 11 3

3 3

4 5

6 4

4-7 22 59 45 24 12 47 104 103 23 6

5 8

12 15 12 16 8-12 13-18 19-24

>24 TOTAL HRS 11 36 28 4

4 34 45 25 13 1

2 1

1 7

5 2

1 10 3

3 5

13 8

9 1

0 0

4 0

0 36 116 87 54 38 126 209 178 48 10 10 12 17 31 23 22 TOTAL HRS 223 513 219 57 5

0 1017

THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS:

B WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 2

1 6

2 4

5 5

7 0

0 2

3 4

3 7

2 4-7 10 17 9

4 6

14 26 2 0 5

2 1

4 6

6 3

5 8-12 13-18 19-24

>24 TOTAL HRS 10 16 10 2

5 16 25 10 1

0 0

0 4

3 3

0 1

5 1

1 3

9 12 7

0 0

23 39 26 9

21 48 76 44 6

2 3

7 14 12 13 7

TOTAL HRS 53 138 105 39 15 0

350

THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS:

C WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 0

1 3

2 1

0 2

2 1

1 0

2 2

0 1

1 4-7 6

7 5

2 5

11 17 8

6 4

2 2

5 5

2 2

8-12 13-18 19-24

>24 TOTAL HRS 5

4 5

3 7

14 11 5

1 0

0 0

2 3

2 1

0 5

1 0

4 7

10 3

1 0

0 0

11 17 14 7

17 37 46 18 9

5 2

4 9

8 5

4 TOTAL HRS 19 89 63 31 10 1

213

C THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS:

D WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 11 8

14 8

15 7

22 31 13 4

12 15 17 19 11 14 4-7 26 48 31 32 60 85 82 64 44 34 52 41 75 32 34 27 8-12 13-18 19-24

>24 TOTAL HRS 40 43 27 14 111 164 121 36 14 5

4 12 52 80 33 24 14 14 5

5 53 110 106 27 1

0 0

0 3

2 3

0 0

2 0

0 2

2 0 34 2

0 0

91 115 77 59 241 389 371 160 72 43 68 68 147 133 81 65 TOTAL HRS 221 767 780 343 60 9

2180

THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS: E WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 20 32 49 37 51 58 52 61 45 36 47 49 37 38 33 24 4-7 109 104 130 97 136 116 84 90 82 44 36 60 84 55 49 83 8-12 13-18 19-24

>24 TOTAL HRS 79 86 39 18 75 94 84 20 8

2 1

5 36 51 29 13 13 13 2

2 15 29 35 6

0 0

1 1

0 1

223 236 220 154 277 302 257 177 135 82 84 114 158 145 111 121 TOTAL HRS 669 1359 640 118 9

1 2796

z I

THREE MILE ISLAND METEROLOGICAL, DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS: F WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 32 37 63 52 72 67 62 69 28 19 25 18 38 35 21 18 4-7 16 57 36 36 37 10 20 68 29 12 10 13 20 9

6 9

8-12 13-18 19-24

>24 TOTAL HRS 55 100 104 91 110 81 84 139 58 31 35 31 58 44 27 27 TOTAL HRS 656 388 30 1

0 0

1075

THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS: G WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 33 28 34 39 28 28 23 30 12 14 13 28 34 48 31 25 4-7 14 33 13 12 12 8

8 16 11 2

0 3

9 6

2 3

8-12 13-18 19-24

>24 TOTAL HRS 47 61 47 52 40 36 35 46 23 16 13 31 43 54 33 28 TOTAL HRS 448 152 5

0 0

0 605

r i^

THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES HOURS (HRS) AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1, 2002 TO DECEMBER 31, 2002 STABILITY CLASS: ALL WIND SPEED (MPH)

SECTOR WINDS TO FROM N

S NNE SSW NE SW ENE WSW E

W ESE WNW SE NW SSE NNW S

N SSW NNE SW NE WSW ENE W

E WNW ESE NW SE NNW SSE 1-3 100 118 179 163 187 196 216 241 110 77 102 118 136 148 110 88 4-7 203 325 269 207 268 291 341 369 200 104 106 131 211 128 108 145 8-12 152 191 114 45 203 325 292 98 38 8

7 18 95 144 72 40 13-18 19-24

>24 TOTAL HRS 29 47 12 11 80 169 171 52 3

0 0

0 4

7 3

1 2

3 1

0 6

34 51 2

0 0

486 684 575 426 744 1019 1078 762 351 189 215 267 446 427 293 274 TOTAL HRS 2289 3406 1842 589 99 11 8236 HRS OF MISSING/INVALID DATA: 524

i At t

2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Assessment of Radiation Doses Due to Radioactive Liquid and Gaseous Effluents Released from TMI during 2002 TMI-1 The attached table presents the maximum hypothetical doses to an individual and the general population resulting from 2002 TMI-1 releases of gaseous and liquid effluents.

Provided below is a brief explanation of the table.

A.

Liquid (Individual)

Calculations were performed on the four age groups and seven organs recommended in Regulatory Guide 1.109. The pathways considered for TMI-1 were the consumption of drinking water and fish and standing on the shoreline influenced by TMI-1 effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The "critical receptor" or Receptor I was that individual who 1) consumed Susquehanna River water from the nearest downstream drinking water supplier (Wrightsville Water Supply), 2) consumed fish residing in the vicinity of the TMI-1 liquid discharge outfall and 3) occupied an area of shoreline influenced by the TMI-1 liquid discharge.

For 2002, the calculated maximum whole body (or total body) dose from TMI-1 liquid effluents was 1.77E-2 mrem to an adult (line 1). The maximum organ dose was 2.53E-2 mrem to the liver of a teen (line 2).

B.

Gaseous (Individual)

There were six major pathways considered in the dose calculations for TMI-1 gaseous effluents. These were: (1) plume exposure (2) inhalation, consumption of; (3) cow milk, (4) vegetables and fruits, (5) meat, and (6) standing on contaminated ground. Real-time meteorology was used in all dose calculations for gaseous effluents.

Lines 3 and 4 present the maximum plume exposure at or beyond the site boundary. The notation of "air dose" is interpreted to mean that these doses are not to an individual, but are considered to be the maximum doses that would have occurred at or beyond the site boundary. The table presents the distance in meters to the location in the affected sector (compass point) where the theoretical maximum plume exposures occurred. The calculated maximum plume exposures were 1.36E-5 mrad and 5.71 E-6 mrad for gamma and beta, respectively.

The maximum organ dose due to the release of iodines, particulates and tritium from TMI-1 in 2001 was 9.63E-3 mrem to the thyroid of an child residing 2150 meters from the site in the NNE sector (line 5). This dose again reflects the maximum exposed organ for the appropriate age group.

For 2002, TMI-1 liquid and gaseous effluents resulted in maximum hypothetical doses that were a small fraction of the quarterly and yearly ODCM dose limits.

I.0 TMI-1

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-1 FROM January 1. 2002 through December 31. 2002 Estimated Location

% of Applicable Dose Age Dist Dir ODCM ODCM Dose Effluent Organ (mrem)

Group (m)

(to)

Dose Limit Limit (mrem)

Quarter Annual Quarter Annual (1) Liquid Total Body 1.77E-2 Adult Receptor I 1.18E+0 5.90E-1 1.5 3

(2) Liquid Liver 2.53E-2 Teen Receptor 1 3.54E-1 2.53E-1 5

10 (3) Noble Air Dose 1.36E-5 4000 ESE 2.72E-4 1.36E-4 5

10 Gas (gamma-mrad)

Air Dose 5.71 E-6 4000 ESE 5.71 E-5 2.86E-5 10 20 (4) Noble (beta-mrad)

Gas (5) Iodine, Thyroid 9.63e-3 Child 2150 NNE 1.28E-1 6.42E-2 7.5 15 Tritium &

Particulates

I

'N ;

TMI-2 The attached table presents the maximum hypothetical doses to an individual and the general population resulting from 2002 TMI-2 releases of gaseous and liquid effluents.

Provided below is a brief explanation of the table.

A.

Liquid (Individual)

Calculations were performed on the four age groups and seven organs recommended in Regulatory Guide 1.109. The pathways considered for TMI-2 were the consumption of drinking water and fish and standing on the shoreline influenced by TMI-2 effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The "critical receptor" or Receptor 1 was that individual who 1) consumed Susquehanna River water from the nearest downstream drinking water supplier (Wrightsville Water Supply), 2) consumed fish residing in the vicinity of the TMI-2 liquid discharge outfall and 3) occupied an area of shoreline influenced by the TMI-2 liquid discharge.

For 2002, the calculated maximum whole body (or total body) dose from TMI-2 liquid effluents was 1.71 E-4 mrem to an adult (line 1). The maximum organ dose was 2.72E-4 mrem to the bone of a child (line 2).

B.

Gaseous (Individual)

There were six major pathways considered in the dose calculations for TMI-2 gaseous effluents. These were: (1) plume exposure (2) inhalation, consumption of; (3) cow milk, (4) vegetables and fruits, (5) meat, and (6) standing on contaminated ground. Real-time meteorology was used in all dose calculations for gaseous effluents.

Since there were no noble gases released from TMI-2 during 2002, the gamma and beta air doses (lines 3 and 4, respectively) were zero.

The maximum organ dose due to the release of particulates and tritium from TMI-2 in 2002 was 3.85E-5 mrem to the liver, total body, thyroid, kidney, lung and GI tract of a child residing 2150 meters from the site in the NNE sector (line 5).

For 2002, TMI-2 liquid and gaseous effluents resulted in maximum hypothetical doses that were a small fraction of the quarterly and yearly ODCM dose limits.

TMI-2

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-2 FROM January 1. 2002 through December 31, 2002 Location

% of Estimated Age Dist Dir ODCM Dose ODCM Dose Effluent Applicable Organ Dose (mrem)

Group (m)

(to)

Limit Limit (mrem)

Quarter Annual Quarter Annual (1) Liquid Total Body 1.71E-4 Adult Receptor 1 1.14E-2 5.70E-3 1.5 3

(2) Liquid Bone 2.72E-4 Child Receptor I 5.44E-3 2.72E-3 5

10 (3) Noble Gas Air Dose 0

0 0

5 10 (gamma-mrad)

(4) Noble Gas Air Dose 0

0 0

10 20 (beta-mrad)

(5) Tritium &

Liver, Total Body, 3.85E-5 Child 2150 NNE 5.13E-4 2.57E-4 7.5 15 Particulate Thyroid, Kidney, Lung &

Gl Tract 2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Assessment of Radiation Doses from Liquid and Gaseous Effluents Releases to Members of the Public within the TMI Site Boundaries during 2002 The Offsite Dose Calculation Manual requires an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary during the reporting period.

The following are the assumptions made in this assessment:

1. A member of the public stays in the owner controlled area for 3000 hours0.0347 days 0.833 hours 0.00496 weeks 0.00114 months . The 3000 hours0.0347 days 0.833 hours 0.00496 weeks 0.00114 months is based upon the State Police or National Guard personnel who is stationed at the site at the directive of the Governor. This time selected is conservative, as it is higher than full time employment with consideration for substantial overtime.

2. The highest dose individual is standing next to a radiologically controlled area for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , where the dose rate is 0.5 mR/hr. In areas where the dose rate is greater than 0.5 mR/hr, the area would be posted as a TLD or RWP required area. This is a conservative assumption, as any person would normally be moving around the island during their visit and would not spend it next to a restricted area posting. This calculation would also bound all personnel that visited the site or spent time in areas of lower dose rate for longer periods of time. The members of longest times on the site were the National Guard or State Police. They normally spent their time at the north gate or along the perimeter of the island with the exception for breaks/snack/lunch in the cafeteria.

3. Direct radiation to the north gate is best represented by the environmental TLD located at the North Bridge

4. Liquid effluents are not a pathway to the individual on site.

5. The estimated airborne dose is based on the annual dose to the boundary for year 2002. To correct for any period of time within the boundary, a 10% factor was used or 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months would be spend with the maximum dispersion factor and the average discharge rate for the year.

6. Highest dispersion factor for gaseous effluents to personnel outside restricted area is 4.99e-5 sec/mi3. This is the value used in FSAR section 2.5.4.2.1 Containment release to Yard intake for a 4 day to 30 day period. This intake is very close to the protected area and is very close to where the Reactor Building (Containment) would

Et release. This is calculated in the FSAR for postulated accident conditions and is a very conservative dispersion factor to be used for this calculation. This would be very conservative as the members of the public spend most of their time along the site boundary fence line and rarely near the protected area boundary.

The maximum total body dose to an individual is 11 mrem.

t 2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Assessment of Radiation Dose to Most Likely Exposed Real Individual per 40 CFR 190 Dose calculations were performed to demonstrate compliance with 40 CFR 190 (ODCM Part IV Section 2.10). Gaseous and liquid effluents released from TMI-1 and TMI-2 in 2002 resulted in maximum individual doses (regardless of age group) of 0.01 mrem to the thyroid and 0.04 mrem to any other organ including the whole (total) body. The direct radiation component was determined using the highest quarterly fence-line exposure rate as measured by an environmental TLD, and subtracting from it, the lowest quarterly environmental TLD exposure rate.

Based on the maximum exposure rate of 5.4 mR/standard month, a person residing at the fence-line for 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months (shoreline exposure from Reg. Guide 1.109) received an exposure of 0.50 mR. Based on the lowest exposure rate of 3.4 mR/standard month and converting it by the same method yielded a background exposure of 0.31 mR.

Therefore, the net exposure from direct radiation from TMINS was 0.19 mR. Combining the direct radiation exposure (assumed to be equal to dose) with the maximum organ doses from liquid and gaseous releases, the maximum potential (total) doses were 0.20 mrem to the thyroid and 0.23 mrem to any other organ. Both doses were well below the limits specified in 40 CFR 190.

0I

e o 0 2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Deviation from the ODCM Sampling and Analysis Regime during 2002 There was one deviation from the effluent sampling and analysis regime specified in the TMI Offsite Dose Calculation Manual during 2002.

The deviation was not obtaining a grab sample on a sump prior to discharging that sump. A condition report (TMl's corrective action system) was submitted as a result of the missed sample.

The average concentration value for the same type of water that was obtained during the month of release was used to account for the activity discharged. The dose and activity of this discharge is an insignificant value when compared to the plant's annual effluent.

2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 TMI Offsite Dose Calculation Manual, Revision 23 6610-PLN-4200.01 (Revision 23 was issued on March 19, 2002)

AmerGen]

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 Applicability/Scope USAGE LEVEL Effective Date TMI Division 3

03/19/02 This document is within QA plan scope [X Yes No 50.59 Applicable I X I Yes No List of Effective Pages Page 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Revision 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 Page 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 Revision 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 Paae 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 Revision 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 Pace 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 151 152 153 154 155 156 157 158 159 160 Revision 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 1

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLNj4200.01_

Title Revision No Offsite Dose Calculation Manual (ODCM) 23R List of Effective Pages Paae 161 162 163 164 165 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 181 182 183 184 185 186 187 188 189 190 191 192 193 194 195 196 Revision Paae Revision Page Revision Page Revision 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 2

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLNo 4200.01 e

Dl nRevision No.

Offsite Dose Calculation Manual (ODCM) 23 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the Three Mile Island Nuclear Station (TMI) Unit 1 and Unit 2 PDMS Technical Specifications and implements TMI radiological effluent controls.

The ODCM contains the controls, bases, and surveillance requirements for liquid and gaseous radiological effluents.

In addition, the ODCM describes the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm/trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also included.

The ODCM also is used to define the requirements for the TMI radiological environmental monitoring program (REMP) and contains a list and graphical description of the specific sample locations used in the REMP.

The ODCM is maintained at the Three Mile Island (TMI) site for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. Changes to the ODCM will be implemented in accordance with the TMI-1 and TMI-2 PDMS Technical Specifications.

The ODCM follows the methodology and models suggested by NUREG-0133, and Regulatory Guide 1.109, Revision 1 for calculation of off-site doses due to plant effluent releases. Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements.

TMI implements the TMI Radiological Effluent Controls Program and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative effluent doses.

3

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 15 Table 1-1, Frequency Notation 19 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 21 2.1 Radioactive Effluent Instrumentation 21 2.1.1 Radioactive Liquid Effluent Instrumentation 21 Table 2.1-1, Radioactive Liquid Effluent Instrumentation 22 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 23 Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 24 2.2 Radiological Effluent Controls 30 2.2.1 Liquid Effluent Controls 30 2.2.2 Gaseous Effluent Controls 33 2.2.3 Total Radioactive Effluent Controls 39 3 0 SURVEILLANCES 41 3.1 Radioactive Effluent Instrumentation 41 3.1.1 Radioactive Liquid Effluent Instrumentation 41 Table 3.1-1, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 42 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 44 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 45 Surveillance Requirements 3.2 Radiological Effluents 49 3.2.1 Liquid Effluents 49 Table 3 2-1. Radioactive Liquid Waste Sampling and Analysis Program 50 4

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page 3.2.2 Gaseous Effluents 53 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 55 3.2.3 Total Radioactive Effluents 59 4.0 PART I REFERENCES 60 5

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01_

Title Revision No Mffite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 62 Table 1.1, Frequency Notation 64 2.0 CONTROLS AND BASES 65 2.1 Radioactive Effluent Instrumentation 65 2.1.1 Radioactive Liquid Effluent Instrumentation 65 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 65 Table 2.1.2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 67 2.2 Radioactive Effluent Controls 68 2.2.1 Liquid Effluent Controls 68 2.2.2 Gaseous Effluent Controls 71 2.2.3 Total Radioactive Effluent Controls 76 3 0 SURVEILLANCES 78 3.1 Radioactive Effluent Instrumentation 78 3.1.1 Radioactive Liquid Effluent Instrumentation 78 3.1.2 Radioactive Gaseous Process and Effluents Monitoring Instrumentation 78 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 79 Surveillance Requirements 3.2 Radiological Effluents 80 3.2.1 Liquid Effluents 80 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 81 3.2.2 Gaseous Effluents 82 Table 3 2-2, Radioactive Gaseous Waste Sampling and Analysis Program 83 3.2.3 Total Radioactive Effluents 86 6

Number TMI - Unit I I

Radiological Controls Procedure RevisionNo 4200_

fitle DRavasManDN2 Mffite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

TMI-2 RADIOLOGICAL EFFLUENT CONTROLS PART 11 Section 4.0 1

Paae 87 PART 11 REFERENCES 7

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART IlIl EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Paqe 1.0 LIQUID EFFLUENT MONITORS 89 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points 89 1.2 TMI Liquid Release Points and Liquid Radiation Monitor Data 90 1.3 Control of Liquid Releases 91 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 97 2.1 Liquid Effluents -10 CFR 50 Appendix I 97 2.2 TMI Liquid Radwaste System Dose Calcs Once per Month 98 2.3 Alternative Dose Calculational Methodology 99 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEM 104 3.1 TMI-1 Liquid Effluent Waste Treatment System 104 3.2 Operability of TM I-1 Liquid Effluent Waste Treatment System 105 3.3 TMI-2 Liquid Effluent Waste Treatment System 105 4.0 GASEOUS EFFLUENT MONITORS 108 4.1 TMI-1 Noble Gas Monitor Set Points 108 4.2 TMI-1 Particulate and Radioiodine Monitor Set Points 110 4.3 TMI-2 Gaseous Radiation Monitor Set Points 111 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 112 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 114 4.6 Control of Gaseous Effluent Releases 115 8

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN4200.01 Tite DeveMsion No Mffite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Pa9e 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 127 5.1 Gaseous Effluents - Instantaneous Release Limits 127 5.1.1 Noble Gases 127 5.1.1.1 Total Body 127 5.1.1.2 Skin 128 5.1.2 lodines and Particulates 129 5.2 Gaseous Effluents - 10 CFR 50 Appendix 1 130 5.2.1 Noble Gases 130 5.2.2 lodines and Particulates 131 5.3 Gaseous Radioactive System Dose Calculations Once per Month 133 5.4 Alternative Dose Calculational Methodologies 134 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 156 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 156 6.2 Operability of the TMI-1 Gaseous Radwaste Treatment System 156 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 158 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 159 8.1 Monitoring Program Requirements 159 8.2 Land Use Census 161 8.3 Interlaboratory Comparison Program 163 9 0 PART 1I1 REFERENCES 179 9

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART IlIl EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES Table 1.1 TMI-1 Liquid Release Point and Liquid Radiation Monitor Data 93 Table 1.2 TMI-2 Sump Capacities 94 Table 2.1 Liquid Dose Conversion Factors (DCF): DF 1j 100 Table 2.2 Bioaccumulation Factors, BF1 103 Table 4.1 TMI-1 Gaseous Release Point & Gaseous Radiation Monitor Data 116 Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiation Monitor Data 117 Table 4.3 Dose Factors for Noble Gases and Daughters 118 Table 4.4 Atmospheric Dispersion Factors for Three Mile Island - Station Vent 119 Table 4.5 Atmospheric Dispersion Factors for Three Mile Island - Ground Release 120 Table 4 6 Dose Parameters for Radioiodines and Radioactive Particulate In Gaseous Effluents 121 Table 5 2 1 Pathway Dose Factors, RI - Infant, Inhalation 135 Table 5 2.2 Pathway Dose Factors, RI - Child, Inhalation 136 Table 5.2.3 Pathway Dose Factors, RI - Teen, Inhalation 137 Table 5.2.4 Pathway Dose Factors, RI - Adult, Inhalation 138 Table 5 3 1 Pathway Dose Factors, RI - All Age Groups, Ground Plane 139 Table 5.4.1 Pathway Dose Factors, RI - Infant, Grass-Cow-Milk 140 Table 5 4.2 Pathway Dose Factors, R, - Child, Grass-Cow-Milk 141 Table 5.4.3 Pathway Dose Factors, RI - Teen, Grass-Cow-Milk 142 Table 5.4.4 Pathway Dose Factors, R, - Adult, Grass-Cow-Milk 143 Table 5.5.1 Pathway Dose Factors, RI - Infant, Grass-Goat-Milk 144 10

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART IlIl EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Paqe TABLES Table 5.5.2 Pathway Dose Factors, RI - Child, Grass-Goat-Milk 145 Table 5 5 3 Pathway Dose Factors, R. - Teen, Grass-Goat-Milk 146 Table 5.5.4 Pathway Dose Factors, RI - Adult, Grass-Goat-Milk 147 Table 5.6.1 Pathway Dose Factors, RI - Infant, Grass-Cow-Meat 148 Table 5 6 2 Pathway Dose Factors, RI - Child, Grass-Cow-Meat 149 Table 5.6.3 Pathway Dose Factors, RI - Teen, Grass-Cow-Meat 150 Table 5.6.4 Pathway Dose Factors, R - Adult, Grass-Cow-Meat 151 Table 5.7.1 Pathway Dose Factors, R. - Infant, Vegetation 152 Table 5.7.2 Pathway Dose Factors, R, - Child, Vegetation 153 Table 5 7.3 Pathway Dose Factors, RI - Teen, Vegetation 154 Table 5.7.4 Pathway Dose Factors, RI - Adult, Vegetation 155 Table 8.1 Sample Collection and Analysis Requirements 164 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 168 Table 8.3 Detection Capabilities for Environmental Sample Analysis 169 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air Iodine 171 Table 8.5 TMINS REMP Station Locations - Direct Radiation (TLD) 171 Table 8.6 TMINS REMP Station Locations - Surface Water 173 Table 8.7 TMINS REMP Station Locations - Aquatic Sediment 173 Table 8 8 TMINS REMP Station Locations - Milk 174 Table 8.9 TMINS REMP Station Locations - Fish 174 Table 8.10 TMINS REMP Station Locations - Food Products 175 11

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Radiological Controls Procedure 6610-PLN-4200.01 Oflse oevan non2No Offsite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental 176 Monitoring Program Stations within 1 Mile of the Site MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental 177 Monitoring Program Stations within 5 miles of the Site MAP 8 3 Three Mile Island Nuclear Station Locations of Radiological Environmental 178 Monitoring Program Stations Greater than 5 miles from the Site FIGURES Figure 1.1 TMI-1 Liquid Effluent Pathways 95 Figure 1.2 TMI-2 Liquid Effluent Pathways 96 Figure 3.1 TMI-1 Liquid Radwaste 106 Figure 3.2 TMII-1 Liquid Waste Evaporators 107 Figure 4.1 TMI-1 Gaseous Effluent Pathways 122 Figure 4.2 TMI-1 Auxiliary & Fuel Handling Buildings Effluent Pathways 123 Figure 4.3 TMI-1 Reactor Building Effluent Pathway 124 Figure 4.4 TMI-1 Condenser Offgas Effluent Pathway 125 Figure 4 5 TMI-2 Gaseous Effluent Filtration System/Pathways 126 Figure 6 1 Waste Gas System 157 12

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Radiological Controls Procedure 6610-PLN-4200.01 MTle Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE OF CONTENTS (Cont'd)

PART IV REPORTING REQUIREMENTS Section Paqe 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 182 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 183 3 0 PART IV REFERENCES 185 APPENDICES A.

Pathway Dose Rate Parameter (PI) 186 B.

Inhalation Pathway Dose Factor (RI) 187 C.

Ground Plane Pathway Dose Factor (RI) 188 D.

Grass-Cow-Milk Pathway Dose Factor (R,)

189 E.

Cow-Meat Pathway Dose Factor (RI) 191 F.

Vegetation Pathway Dose Factor (RI) 192 APPENDIX A - F REFERENCES 193 13

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Radiological Controls Procedure 0-PLN200.01 iteD laoRevsionl No Offsite Dose Calculation Manual (ODCM) 23 PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 14

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 1.0 DEFINITIONS The following terms are defined for uniform interpretation of these controls and surveillances.

1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is no more than 2000F. Pressure is defined by Technical Specification 3.1.2.

1.1.2 Hot Shutdown The reactor is in the hot shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is at or greater than 5250F.

1.1.3 Reactor Critical The reactor is critical when the neutron chain reaction is self-sustaining and Keff = 1.0.

1.1.4 Hot Standby The reactor is in the hot standby condition when all of the following conditions exist.

a.

Tavg is greater than 5250F

b.

The reactor is critical

c.

Indicated neutron power on the power range channels is less than two percent of rated power. Rated power is defined in Technical Specification Definition 1.1.

1.1.5 Power Operation The reactor is in a power operating condition when the indicated neutron power is above two percent of rated power as indicated on the power range channels. Rated power is defined in Technical Specification Definition 1.1.

1.1.6 Refueling Shutdown The reactor is in the refueling shutdown condition when, even with all rods removed, the reactor would be subcritical by at least one percent delta k/k and the coolant temperature at the decay heat removal pump suction is no more than 140'F. Pressure is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods.

1.1.7 Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

15

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 1.1.8 Refueling Interval Time between normal refuelings of the reactor. This is defined as once per 24 months.

1.1.9 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.

1.1.10 Tave Tave is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating, if such a distinction of loops can be made.

1.1.11 Heatup - Cooldown Mode The heatup-cooldown mode is the range of reactor coolant temperature greater than 2001F and less than 5250F.

1.2 Operable A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

1.3 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers, and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control, and/or protection. An instrument channel may be either analog or digital 1.4 Instrumentation Surveillance 1.4.1 Channel Test A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions.

1.4.2 Channel Check A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

16

Number TMI - Unit I I

Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Ofisite Dose Calculation Manual (ODCM) 23 1.4.3 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

1.4.4 Channel Calibration An instrument CHANNEL CALIBRATION is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter which the channel measures or an accurate simulation of these values Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.

1.5 Dose Equivalent 1-131 The DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132. 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table IlIl of TID 14844, 'Calculation of Distance Factors for Power and Test Reactor Sites". [Or in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.]

1.6 Offsite Dose Calculation Manual (ODCM)

The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radiological Effluent Controls, (2) the Radiological Environmental Monitoring Program and (3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

1.7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.8 Ventilation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust system prior to the release to the environment.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.

1.9 Purge - Purging PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purify the confinement.

17

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Radiological Controls Procedure 6610-PLN-4200.01 Tile Revision No Offsite Dose Calculation Manual (ODCM) 23 1.10 Venting VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided. Vent used in system name does not imply a VENTING process.

1.11 Member(s) of the Public MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

1.12 Site Boundary The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island.

The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM.

1.13 Frequency Notation The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception of "F."

No extension is allowed for intervals designated "F."

18

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 tiotleRevision No Offsite Dose Calculation Manual (ODCM) 23 Table 1-1 Frequency Notation Notation Frequency S

Shiftly (once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

D Daily (once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

W Weekly (once per 7 days)

M Monthly (once per 31 days)

Q Quarterly (once per 92 days)

S/A Semi-Annually (once per 184 days)

R Refueling Interval (once per 24 months)

P S/U Prior to each reactor startup, if not done during the previous 7 days P

Completed prior to each release N/A (NA)

Not applicable E

Once per 18 months F

Not to exceed 24 months Bases Section 1.13 establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,

transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified to be performed at least once each REFUELING INTERVAL. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed once each REFUELING INTERVAL. Likewise, it is not the intent that REFUELING INTERVAL surveillances be performed during power operation unless it is consistent with safe plant operation. The limitation of Section 1.13 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

19

661 0-PLN-4200.01 Revision 23 FIGURE 1.1 Gaseous Effluent Release Points and Liquid Effluent Outfall Locations 20

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01O Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation CONTROL:

The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.1.1 are not exceeded. The alarm/tnp setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

At all times

ACTION.

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluent monitored by the affected channel or declare the channel inoperable.

b.With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-1. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

For FT-84, and RM-L6, operability is not required when discharges are positively controlled through the closure of WDL-V257.

For RM-L12 and associated IWTS/IWFS flow interlocks, operability is not required when discharges are positively controlled through the closure of IW-V72, 75 and IW-V280, 281.

For FT-146, operability is not required when discharges are positively controlled through the closure of WDL-V257, IW-V72, 75 and IW-V280, 281.

BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the effluent concentrations of 10 CFR Part 20.

21

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Relnsion No.

Offsite Dose Calculation Manual (ODCM) 23 Table 2.1-1 Radioactive Liquid Effluent Instrumentation Minimum Channels Instrument Operable ACTION

1.

Gross Radioactivity Monitors Providing Automatic Termination of Release

a.

Unit 1 Liquid Radwaste Effluent 1

18 Line (RM-L6)

b.

IWTS/IWFS Discharge Line (RM-L12) 1 20

2.

Flow Rate Measurement Devices

a.

Unit 1 Liquid Radwaste Effluent 1

21 Line (FT-84)

b.

Station Effluent Discharge 1

21 (FT-146)

Table Notation ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:

1.

At least two independent samples are analyzed in accordance with Surveillances 3.2.1.1.1 and 3.2.1.1.2 and;

2.

At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup.

3.

The TMI Plant Manager shall approve each release.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 1x10-7 microcuries/ml, prior to initiating a release and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during release.

ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

22

Number TMI - Unit 1 I

Radiological Controls Procedure 6610O-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL:

The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip selpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-2.

ACTION

a.

With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Arinual Effluent Release Report why the inoperability was not corrected in a timely manner.

BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.

The low range condenser offgas noble gas activity monitors also provide data for determination of steam generator primary to secondary leakage rate. Channel operability requirements are based on an ASLB Order No LBP-84-47 dated October 31, 1984, and as cited in 20 NRC 1405 (1984).

23

Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS r

OPERABLE APPLICABILI1 661 0-PLN-4200.01 Revision 23 ACTION INSTRUMEN'

-Y

1.

Waste Gas Holdup System

a.

Noble Gas Activity Monitor (RM-A7)

b.

Effluent System Flow Rate Measuring Device (FT-123) 1 1

25 26

2.

Waste Gas Holdup System Explosive Gas Monitoring System

a.

Hydrogen Monitor

b.

Oxygen Monitor

3.

Containment Purge Monitoring System

a.

Noble Gas Activity Monitor (RM-A9)

b.

Iodine Sampler (RM-A9)

c.

Particulate Sampler (RM-A9)

d.

Effluent System Flow Rate Measuring Device (FR-1 48)

e.

Sampler Flow Rate Monitor 2

2 30 30 I

1 I

1 1

27 31 31 26 26 24

661 0-PLN-4200.01 Revision 23 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

4.

Condenser Vent System

a.

Low Range Noble Gas Activity Monitor (RM-A5Lo and 2(1) 32 Suitable Equivalent)

NOTE (1):

For one of the channels, an operable channel may be defined for purposes of this control and 3.1.2 1 only as a suitable equivalent monitoring system capable of being placed in service within one hour. A suitable equivalent system shall include instrumentation with comparable sensitivity and response time to the RM-A5Lo monitoring channel. When the equivalent monitoring system is in service, indication will be continuously available to the operator, either through indication and alarm in the Control Room or through communication with a designated individual continuously observing local indication.

25

Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS 6610-PLN-4200.01 Revision 23 ACTION INSTRUMENT

5.

Auxiliary and Fuel Handling Building Ventilation System

a.

Noble Gas Activity Monitor (RM-A8) or (RM-A4 and RM-A6)

b.

Iodine Samples (RM-A8) or (RM-A4 and RM-A6)

c.

Particulate Sampler (RM-A8) or (RM-A4 and RM-A6)

d.

Effluent System Flow Rate Measuring Devices (FR-149 and FR-150)

e.

Sampler Flow Rate Monitor

6.

Fuel Handling Building ESF Air Treatment System

a.

Noble Gas Activity Monitor (RM-A14 or Suitable Equivalent)

b.

Iodine Cartridge

c.

Particulate Filter

d.

Effluent System Flow (UR-1104A/B)

e.

Sampler Flow Rate Monitor OPERABLE APPLICABILI1 TY 1

1 I

I 1

N/A(2)

N/A(

2 )

NIt2 27 31 31 26 26 27, 33 31, 33 31, 33 26, 33 26, 33 1

NOTE 2:

No instrumentation channel is provided. However, for determining operability, the equipment named must be installed and functional or the ACTION applies.

26

Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS 661 0-PLN-4200.01 Revision 23 ACTION INSTRUMENT

7.

Chemical Cleaning Building Ventilation System

a.

Noble Gas Activity Monitor (ALC RM-1-18)

b.

Iodine Sampler (ALC RM-1-18)

c.

Particulate Sampler (ALC RM-1-18)

8.

Waste Handling and Packaging Facility Ventilation System

a.

Particulate Sampler (WHP-RIT-1)

9.

Respirator and Laundry Maintenance Facility Ventilation OPERABLE APPLICABILI-7Y 27 31 31 1

1

1#

31 System

a.

Particulate Sampler (RLM-RM-1) 1 Channel only required when liquid radwaste is moved or processed within the facility.

31 NOTE 3:

27

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 Table 2.1-2 Table Notation

At all times.

During waste gas holdup system operation.

Operability is not required when discharges are positively controlled through the closure of WDG-V47 and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT-150 are operable.

- - - During Fuel Handling Building ESF Air Treatment System Operation.

At all times during containment purging.

1. At all times when condenser vacuum is established.

1. 1. During operation of the ventilation system.

ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release

1.

At least two independent samples of the tank's contents are analyzed in accordance with Table 3.2-2, Item A, and

2.

At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup.

3.

The TMI Plant Manager shall approve each release Otherwise, suspend release of radioactive effluent via this pathway.

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and the initial samples are analyzed for gross activity (gamma scan) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the channel has been declared inoperable. If RM-A9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, Item C.3.f.

ACTION 30

1.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel(s) at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both channels inoperable, a grab sample shall be collected and analyzed for the inoperable gas channel(s):

(a) at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations.

(b) at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations (e.g. Feed and Bleed).

28

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01_

Title Revision No Offsite Dose Calculation Manual (ODCM) 23 Table 2.1-2

2.

If the inoperable gas channel(s) is not restored to service within 14 days, a special report shall be submitted to the Regional Administrator of the NRC Region I Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of declaring the channel(s) inoperable. The report shall describe (a) the cause of the monitor inoperability, (b) action being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence.

ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment.

ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service or is placed in service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . After 28 days, or if one OPERABLE channel does not remain in service or is not placed in service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the provisions of Technical Specification 3.0.1 apply, as if this Control were a Tech Spec Limiting Condition for Operation.

ACTION 33 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7 days, or prepare and submit a special report within 30 days outlining the action(s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABLE status.

29

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 fitle DRevislon No Offsite Dose Calculation Manual (ODCM) 23 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL:

The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20 2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 3 x 103 uCi/cc total activity.

APPLICABILITY: At all times ACTION.

With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.

BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section I.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for noble gases is based upon the assumption the Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

2.2.1.2 Liquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

30

Number TMI - Unit 1 Radioloaical Controls Prncedure 66110f-PILN-42nnff1 Title Revision No Oftite Dose Calculation Manual (ODCM) 23 APPLICABILITY: At all times ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking WaterAct.

BASES This control and associated action is provided to implement the requirements of Sections Il.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section IhIA of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 10 CFR 20. The dose calculations in the ODCM implement The requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977.

NUREG-01 33 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

31

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.2.1.3 Liquid Radwaste Treatment System CONTROL:

The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

APPLICABILITY: At all times ACTION:

a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2.

Action(s) taken to restore the inoperable equipment to OPERABLE status, and,

3.

A summary description of action(s) taken to prevent a recurrence.

BASES The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The intent of Section II.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section I.A of Appendix 1, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction.

32

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 feltleReension No Offsite Dose Calculation Manual (ODCM) 23 2.2.1.4 Liquid Holdup Tanks CONTROL The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a.

Outside temporary tank APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001-20-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:

The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a.

For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b.

For 1-131,1-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s).

33

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 fiteoRevislon No Offsite Dose Calculation Manual (ODCM) 23 BASES The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas while providing sufficient operational flexibility in establishing effluent monitor setpoints.

These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year (NUREG 0133).

2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL:

The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.

During any calendar quarter: less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b.

During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

34

Number TMI - Unit 1 Radioloaical Controls Procedure 6610-PLN-4200-01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1.

This control and associated action is provided to implement the requirements of Section ll.B, III.A and IV.A of Appendix 1, 10 CFR Part 50. The Control implements the guides set forth in Section I1.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept 'as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,' Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

2.2.2.3 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides In Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from lodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.

During any calendar quarter: less than or equal to 7.5 mrem to any organ, and b

During any calendar year: less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

35

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01_

Title Revision No Offsite Dose Calculation Manual (ODCM) 23 ACTION:

With the calculated dose from the release of lodine-131, lodine-133, Tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1.

This control and associated action is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section I.C of Appendix I. The ACTION statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable " The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section II.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

36

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.2.2.4 Gaseous Radwaste Treatment System CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the monthly projected gaseous effluent air doses due to untreated gaseous effluent releases from the unit would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ APPLICABILITY: At all times.

ACTION:

a.

With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability,

2.

Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3.

A summary description of action(s) taken to prevent a recurrence.

BASES The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section I1.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections Il.B and IL.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

37

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Ttle Revision No Offsite Dose Calculation Manual (ODCM) 23 2.2.2.5 Explosive Gas Mixture CONTROL The concentration of oxygen in the Waste Gas Holdup System shall be limited to less than or equal to 2% by volume whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume.

AVAILABILITY: At all times.

ACTION:

Whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume, and:

a.

The concentration of oxygen in the Waste Gas Holdup System is greater than 2% by volume, but less than 4% by volume, without delay begin to reduce the oxygen concentration to within its limit.

b.

The concentration of oxygen in the Waste Gas Holdup System is greater than or equal to 4% by volume, immediately suspend additions of waste gas to the Waste Gas Holdup System and without delay begin to reduce the oxygen concentration to within its limit.

BASES:

Based on experimental data (Reference 1), lower limits of flammability for hydrogen is 5% and for oxygen is 5% by volume. Therefore, if the concentration of either gas is kept below it lower limit, the other gas may be present in higher amounts without the danger of an explosive mixture.

Maintaining the concentrations of hydrogen and oxygen such that an explosive mixture does not occur in the waste gas holdup system provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50.

REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammability of Gases and Vapors.

38

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2 2.2.6 Waste Gas Decay Tanks CONTROL:

The quantity of radioactivity contained in each waste gas decay tank shall be limited to less than or equal to 8800 curies noble gases (considered as Xe-1 33).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any waste gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

BASES Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure."

2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL:

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 39

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 fitle DeveMsion No Offsite Dose Calculation Manual (ODCM) 23 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301 (d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20 2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2 1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

40

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01_

iteD alamsion No Offsite Dose Calculation Manual (ODCM) 23 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements 3.1.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL TEST operations during the MODES and at the frequencies shown in Table 3.1-1.

41

661 0-PLN-4200.01 Revision 23 Table 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL INSTRUMENT CHECK CHECK CALIBRATION

1.

Radioactivity Monitors Providing Alarm and Automatic Isolation

a.

Unit 1 Liquid Radwaste Effluents Line (RM-L-6) b IWTS/IWFS Discharge Line (RM-L-12)

2.

Flow Rate Monitors

a.

Unit 1 Liquid Radwaste Effluent Line (FT-84)

b.

Station Effluent Discharge (FT-146)

D D

D(3)

D(3) p P

NIA N/A R(2)

R(2)

R R

CHANNEL TEST Q(1)

Q(1)

Q Q

42

Number TMI - Unit 1 I

Radiological Controls Procedure 661__-PLN-4200.01 itie Rela Mnon2No.

Of fsite Dose Calculation Manual (ODCM) 23 Table 3.1-1 Table Notation (1)

The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the following condition exists:

1.

Instrument indicates measured levels above the high alarm/trip setpoint. (Includes - circuit failure)

2.

Instrument indicates a down scale failure. (Alarm function only.) (Includes - circuit failure)

3.

Instrument controls moved from the operate mode (Alarm function only).

(2)

The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participated in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement)

(3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.

43

Number il.n-Dl KI-Aflnn no4 TMI - Unit 1 D -4lnI

-rdnn f-ln rn e D

-nnnA..-,

Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL 6610 -PLN-4200.01 Revision 23 APPLICABILITY INSTRUMENT

1.

Waste Gas Holdup System

a.

Noble Gas Activity Monitor (RM-A7)

b.

Effluent System Flow Rate Measuring Device (FT-123)

2.

Waste Gas Holdup System Explosive Gas Monitoring System

a.

Hydrogen Monitor

b.

Oxygen Monitor

3.

Containment Purge Vent System

a.

Noble Gas Activity Monitor (RM-A9)

b.

Iodine Sampler (RM-A9)

c.

Particulate Sampler (RM-A9)

d.

Effluent System Flow Rate Measuring Device (FR-148)

e.

Sampler Flow Rate Monitor

4.

Condenser Vent System

a.

Noble Gas Activity Monitor (RM-A5 and Suitable Equivalent - See Table 2.1-2, Item 4.a)

CHECK CHECK CALIBRATION TEST P

P D

D 0

W W

0 0

D P

N/A N/A N/A P

N/A N/A N/A N/A M

E(3)

E Q(4)

Q(5)

E(3)

N/A N/A E

E E(3)

Q(1)

Q M

M M(1)

N/A N/A Q

N/A Q(2) 45

6610 -PLN-4200.01 Revision 23 Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT

5.

Auxiliary and Fuel Handling Building Ventilation System

a.

Noble Gas Activity Monitor (RM-AB) or (RM-A4 and RM-A6)

b.

Iodine Sampler (RM-A8) or (RM-A4 and RM-A6)

c.

Particulate Sampler (RM-A8) or (RM-A4 and RM-A6)

d.

System Effluent Flow Rate Measurement Devices (FR-149 and FR-150)

e.

Sampler Flow Rate Monitor

6.

Fuel Handling Building ESF Air Treatment System

a.

Noble Gas Activity Monitor (RM-A14)

b.

System Effluent Flow Rate (UR-1 104 A/B)

c.

Sampler Flow Rate Measurement Device CHECK CHECK UALIBRATIOUN ITSI APPLICABILITY D

W W

D D

D M

N/A N/A N/A N/A M

N/A N/A E(3)

N/A N/A E

E R(3)

R R

Q(1)

N/A N/A Q

N/A Q(2)

Q Q

46

Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL 661 0-PLN-4200.01 Revision 23 APPLICABILITY INSTRUMENT

7.

Chemical Cleaning Building Ventilation System

a.

Noble Gas Activity Monitor (ALC RM-1-18)

b.

Iodine Sampler (ALC RM-1-18)

c.

Particulate Sampler (ALC RM-I-1 8)

8.

Waste Handling and Packaging Facility Ventilation System

a.

Particulate Sampler (WHP-RIT-1)

9.

Respirator and Laundry Maintenance Ventilation System

a.

Particulate Sampler (RLM-RM-1)

CHECK CHECK CALIBRATION TEST D

W W

D D

M N/A N/A W

w E(3)

N/A N/A SA SA Q(2)

N/A N/A W

W 47

Number TMI - Unit I I

Radiological Controls Procedure 0-PLN-4200.01 Oite tnRevision No Offsite Dose Calculation Manual (ODCM) l23 Table 3.1-2 Table Notation At all times.

During waste gas holdup system operation.

Operability is not required when discharges are positively controlled through the closure of WDG-V47, and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT-1 50 are operable.

During Fuel Handling Building ESF Air Treatment System Operation.

At all times during containment purging.

At all times when condenser vacuum is established.

During operation of the ventilation system.

(1)

The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary and Fuel Handling Building Ventilation System, the supply ventilation is isolated and control room alarm annunciation occurs if the following condition exists:

1.

Instrument indicates measured levels above the high alarm/trip setpoint (Includes circuit failure)

2.

Instrument indicates a down scale failure (Alarm function only) (Includes circuit failure).

3.

Instrument controls moved from the operate mode (Alarm function only).

(2)

The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1 Instrument indicates measured levels above the alarm setpoint. (includes circuit failure)

2.

Instrument indicates a down scale failure (includes circuit failure).

3.

Instrument controls moved from the operate mode (3)

The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement.)

(4)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal.

1.

One volume percent hydrogen, balance nitrogen, and

2.

Four volume percent hydrogen, balance nitrogen.

(5)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One volume percent oxygen, balance nitrogen, and

2.

Four volume percent oxygen, balance nitrogen.

48

Number TMI - Unit 1 I

Radiological Controls Procedure 661 0-PLN-4200.01 Tidle ReiinNo Oftfie Dose Calculation Manual (ODCM) 23 3.2 Radiological Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 3.2-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Post-release analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1.

3 2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.

3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.

3.2.1.4 Liquid Holdup Tanks 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall be determined to be within the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to the tank.

49

661 0-PLN-4200.01 Revision 23 Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Type A.1 Batch Waste Release Tanks (Note d)

Sampling Frequency P

Each Batch I

P I

Each Batch I

)ntinuous I

lote )

ontinuous tote c) l l

,ntinuous ote c) ontinuoI Minimum Analysis Frequency P

Each Batch Q

Composite (Note b)

Gross alpha Sr-89, Sr-90 Fe-55 Type of Activity Analysis H-3 Principal Gamma Emitters (Note f) 1-131 Dissolved and Entrained Gases (Gamma Emitters)

(Note Q)

I Low I

Detei I

1 1

5xtT 51x 10 l

1 x10-5 Tr 1x10' l 5x10

1 x 1 o-6

T x T0-7 xltY 65 xlo 1 x 10o X 10.6 er Limit of ction (LLD) ml) (Note a)

I x 10o 5 x 1i,7 I x 10-6 1X 10.4 I

A.2 Continuous Releases (Note e) l(CN l

Cc l (N ECc (N

W Composite (Note c)

I Principal Gamma Emitters (Note f) 1-131 Dissolved and Entrained Gases (Gamma Emitters)

(Note g)

H-3 I

M Composite (Note C)

' Gross alpha Q

1 Sr-89, Sr-90 Composite (Note c)

Fe-55 50

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLNJ4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 Table 3.2-1 Table Notation

a.

The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal For a particular measurement system (which may include radiochemical separation):

4.66Sb LLD =

E x V x 2.22 x 106 x Y x exp (-XAt)

Where.

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 x 10' is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.

Typical values of E. V. Y and At shall be used in the calculation.

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement

b.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c.

To be representative of the quantities and concentrations of radioactive materials in liquid effluent, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

51

Number TMI - Unit 1 Radiological Controls Procedure I 6610-PLN-4200.01 Tle Revision No Offsite Dose Calculation Manual (ODCM) 23 Table 3.2-1

d.

A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and be thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e.

A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume or system that has an input flow during the continuous release.

f.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.

This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9 4.

9.

The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Effluent Release Report pursuant to T.S. 6.9.4.

52

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01_

Title Revision No Offsite Dose Calculation Manual (ODCM) 23 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3 2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM.

3 2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2-2.

3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, lodine-131, Iodine-133, Tritium, and Radionuclides In Particulate Form 3.2.2.3.1 Cumulative dose contributions from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM.

3.2.2.5 Explosive Gas Mixture 3 2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors covered in Table 2.1-2 of Control 2.1.2.

53

Number TMI - Unit 1 I

Radiological Controls Procedure 661 0-PLN-4200.01 Tidle ReiinNo.

Offsite Dose Calculation Manual (ODCM) 23 3 2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactivity contained in the vent header shall be determined weekly. If the concentration of the vent header exceeds 10.7 Ci/cc, daily samples shall be taken of each waste gas decay tank being added to, to determine if the tank(s) is less than or equal to 8800 Ciltank.

54

6610-PLN-4200.01 Revision 23 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency Frequency Analysis t

jiCiml) (Note a)

A.

Waste Gas Each Tank Principa Gamma 1 x lo, Dea akGa apeEach Tank

'Emitters (Note g)

Decay Tank Grab Sample B.

Containment P (Note b)

H-P (Nt b Eah 3

1x106 Purge l

Each Purge Grab

(

Principal Gamma 104 Sample Purge Emitters (Note g) x 1 C.

Auxiliary and MNtse)rbH-3 x0 Fuel Handling Building M

PicplGma1-Sample PrincipaGamma Air Treatment System Emitters (Note g) x 1 D.

Fuel Handling Building M (during System M (during H-3 ESF Air Treatment System Operation)

System Principal Gamma l

1 x 10-)

Grab Sample Operation)

Emitters (Note g) 1 x 104 E.

Condenser Vacuum M(Noteh M

H-3 6

Pumps Exhaust Grab Sample (Note h)

Principal Gamma l

1 x

4 (Note h)

Emitters (Noteg)

F.

Chemical Cleaning Building Air Treatment System M (Note I H-3 1 x 10.6 M

Nte1 xl-Gra SaplePrincipal Gamma l X 10'4 Emitters (Noteg)

G.

Waste Handling and Packaging Facility See Section I See Section I See Section I See Section I Air Treatment System of this table of this table :

of this table of this table H.

Respirator and Laundry Maintenance Facility l

See Section I See Section I See Section I See Section I Air Treatment System of this table of this table of this table of this table 55

6610-PLN-4200.01 Revision 23 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency a

Frequency a

Analysis (gCilml) (Note a)

All Release Types as Listed Above in B, C, D, F, G, ContiusW (Note d) 1 2

and H (During System Operation (Note f)io Charcoal 1-131 1 x 10.12

, (oSample Continuous W (Note d) :Principal Gamma (Note f)

Particulate Emtes(oeg1x101 (1-131, Others) 1 Ie l

Q l a Continuous Composite Gross Alpha 1 x lo`

(Note f)Particulate GrsAlh1x101 I a Sample a

e Q

ae Continuous Composite Sr-89, Sr-90 1 x lo" (Note f)

Particulate Sr8,S-0Ix1.

Sample a

J.

Condenser Vent Stack Continuous Iodine Cn.us W (Note d) 12 Sampler (Note j)

Continuous a

(Notled a

-3 0'

(Note k)

Charcoal 1-131 x 10.

56

Number TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 Table 3.2-2 Table Notation

a.

The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal For a particular measurement system (which may include radiochemical separation):

4.66Sb LLD =

E x V x 2.22 x 106 x Y x exp (-XAt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.

Typical values of E, V, Y and At shall be used in the calculation It should be recognized that the LLD is defined as an 'a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

b.

Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

c.

Tritium grab samples from the spent fuel pool area shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

57

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN4200.01 Title Revision No Offsite Dose Calculation Manual (011CM) 23 Table 3.2-2

d.

Charcoal cartridges and particulate filters shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler)

e.

Tritium grab samples shall be taken weekly from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 2.2.2.1, 2.2.2.2, and 2.2.2.3.

1

9.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.

h.

Applicable only when condenser vacuum is established. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

i.

Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.

j.

If the Condenser Vent Stack Continuous Iodine Sampler is unavailable, then alternate sampling equipment will be placed in service within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or a report will be prepared and submitted within 30 days from the time the sampler is found or made inoperable which identifies (a) the cause of the inoperability, (b) the action taken to restore representative sampling capability, (c) the action taken to prevent recurrence, and (d) quantification of the release via the pathway during the period and comparison to the limits prescribed by Control 2.2.2.1.b.

k.

Applicable only when condenser vacuum is established.

I.

Applicable when liquid radwaste is moved or processed within the facility.

m.

Iodine samples only required in the Chemical Cleaning Building when TMI-1 liquid radwaste is stored or processed in the facility.

58

Number TMI - Unit 1 I

Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

59

Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM)

V N23 4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations, "Energy" 4.2 Regulatory Guide 1.1 09, "Calculation of Annual Doses to Man from Routing Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977 4.3 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.4 TMI-1 FSAR 60

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Remsion No.

Offsite Dose Calculation Manual (ODCM) 23 PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS 61

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 PART II Definitions 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part 11 of the ODCM.

PDMS 1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMI-2 defueling has been completed, the core debris removed from the reactor during the clean-up period has been shipped off-site and the facility has been placed in a stable, safe and secure condition.

ACTION 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part of the controls.

OPERABLE - OPERABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function(s), are also capable of performing their related support function(s).

CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

62

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be

a.

Analog channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.

Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm andlor trip functions SOURCE CHECK 1.8 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

COMPOSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Either the volume of each individual sample is proportional to the flow rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite.

GRAB SAMPLE 1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes.

BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume.

CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE.

SITE BOUNDARY 1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM.

FREQUENCY NOTATION 1 14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

63

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN4200.01 TitleaRetMsion No Offsite Dose Calculation Manual (ODCM) 23 TABLE 1.1 Frequency Notation NOTATION S (Shiftly)

D (Daily)

W (Weekly)

M (Monthly)

Q (Quarterly)

SA (Semi-Annually)

A (Annually)

E N.A P

FREQUENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

At least once per 184 days.

At least once per 12 months.

At least once per 18 months.

Not applicable.

Completed prior to each release 64

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.0 CONTROLS AND BASES 2.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control.

2.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specified time interval shall constitute compliance with the control. In the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required.

2.0.3 In the event the Control and associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the Control, initiate appropriate actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to TMI-2 PDMS Technical Specification (Tech. Spec.) Section 6.8 2 within 30 days unless otherwise specified.

2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Radioactive Liquid Effluent Instrumentation is common between TMI-1 and TMI-2.

Controls, applicability, and actions are specified in ODCM Part I, Control 2.1.1 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL:

The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-2.

ACTION:

a.

With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

65

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.

66

6610-PLN-4200.01 Revision 23 Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT

1.

Containment Purge Monitoring System

a.

Noble Gas Activity Monitor (2HP-R-225)

b.

Particulate Monitor (2HP-R-225)

c.

Effluent System Flow Rate Measuring Device (2AH-FR-5907 Point 1)

2.

Station Ventilation System

a.

Noble Gas Activity Monitor (2HP-R-219) or (2HP-R-219A)

b.

Particulate Monitor (2HP-R-219) or (2HP-R-219A)

c.

Effluent System Flow Rate Monitoring Device (2AH-FR-5907 Point 6)

OPERABLE I

1 I

1 1

1 APPLICABILITY NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTE 1 ACTION NOTE 2 NOTE 2 NOTE 3 NOTE 2 NOTE 2 NOTE 3 NOTES:

1.

During operation of the monitored system.

2.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, secure Reactor Building Purge if in progress.

3.

With flow rate monitoring instrumentation out of service, flow rates from the Auxiliary, Fuel Handling, and Reactor Buildings may be summed individually.

Under these conditions, the flow rate monitoring device is considered operable. If the flow rates cannot be summed individually, they may be estimated using the maximum design flow for the exhaust fans, and the reporting requirements of Control 2.1.2.b are applicable.

67

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL:

The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2.

APPLICABILITY: At all times ACTION:

With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.

BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. These Controls permit flexibility under unusual conditions, which may temporarily result in higher than normal releases, but still within ten times the concentrations, specified in 10 CFR 20.

It is expected that by using this flexibility under unusual conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposure to an individual in off-site areas will not exceed the design objectives of Section II.A of Appendix I to 10 CFR Part 50, which were established as requirements for the cleanup of TMI-2 in the NRC's Statement of Policy of April 27, 1981.

2.2.1.2 Liquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited.

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

68

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 APPLICABILITY: At all times ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

BASES This Control requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 10 CFR Part 50. This will assure the dose received by the public during PDMS is equivalent to or less than that from a normal operating reactor. The limits also assure that the environmental impacts are consistent with those assessed in NUREG-0683, the TMI-2 Programmatic Environmental Impact Statement (PEIS). The ACTION statements provide the required flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section IIL.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977.

NUREG-01 33 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

69

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01_

ite Ralan non2No.

Offsike Dose Calculation Manual (ODCM) 23 2.2.1.3 Liquid Radwaste Treatment System CONTROL:

The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

APPLICABILITY: At all times ACTION:

a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information-

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2.

Action(s) taken to restore the inoperable equipment to OPERABLE status, and,

3.

A summary description of action(s) taken to prevent a recurrence.

BASES The requirement that the appropriate portions of this system (shared with TMI-1) be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The intent of Section II.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section I.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction.

70

Number TMI - Unit I Radiological Controls Procedure I 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:

The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following

a.

For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b.

For tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s).

BASES The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix I to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual dose limits specified in 10 CFR 20 and will not result in doses which exceed the design objectives of Appendix I to 10 CFR 50, which were endorsed as limits for the deanup of TMI-2 by the NRC's Statement of Policy of April 27, 1981. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary.

71

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. The absence of iodine ensures that the corresponding thyroid dose rate above background to an infant via the inhalation pathway is less than or equal to 1500 mremlyr (NUREG 0133), thus there is no need to specify dose rate limits for these nuclides.

2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL:

The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.

During any calendar quarter less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b.

During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION.

a With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-2.

This control and associated action is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section ll.B of Appendix I. The ACTION statements provide flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept 'as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through 72

Number TMI - Unit I Radioloaical Controls Procedure I 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, 'Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

2.2.2.3 Dose - lodine-131, Iodine-133, Tritium, and Radionuclides In Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from Tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.

During any calendar quarter: less than or equal to 7.5 mrem to any organ, and

b.

During any calendar year: less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of Tritium and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

73

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01__

Title ReDosion No Offsite Dose Calculation Manual (ODCM) 23 BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-2.

This control and associated action is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section II.C of Appendix I. The ACTION statement provides flexibility during unusual conditions and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section IlI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium and radionucdides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. The absence of iodines at the site eliminates the need to specify dose limits for these nuclides.

74

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.2.2.4 Ventilation Exhaust Treatrment System CONTROL The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.

The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability,

2.

Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3.

A summary description of action(s) taken to prevent a recurrence.

BASES The use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section I1.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections Il.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

75

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL:

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

76

Number TMI - Unit I Radiological Controls Procedure I 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

77

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