ML20099K425

Semiannual Radioactive Effluent Rept,Jul-Dec 1984

ML20099K425
Person / Time
Site:	Crane
Issue date:	12/31/1984
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20099K372	List: ML20099K364 ML20099K425
References
NUDOCS 8503200268
Download: ML20099K425 (87)

Text

-

EFFLUENT-AND WASTE DISPOSAL SEMI-ANNUAL REPORT i

July 1 through December 31, 1984 l

Supplem:ntal Information Facility TMI-l License DPR-50 1.

Regulatory Limits i

a.

Fission and activation gases:

TMI-l - Unit 1 Technical Specifications b.

Iodines:

Appendix A l

c.

Particulates, half-lives > 8 days:

d.

Liquid effluents-2.

Maximum Permissible Concentrations l

Provide the MPCs used in determining allowable release rates or concentrations.

a.

Fission and activation gases

• 10 CFR 20, Appendix 8 Table II.

b.

Iodines:

c.

Particulates, half-lives > 8 days:

d.

Liquid effluents:

3.

Average Energy Provide the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.

Ey=4.17E-1 E8=1. 3E -1 Ey+3=5.47E-1 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.

Fission and activation gases:

Gamma Spectroscopy, Liquid Scintillation, a.

b.

Iodines:

Gamma Spectroscopy.

c.

Particulates:

Gamma Spectroscopy, Beta Spectroscopy, Gas Flow Proportional, d.

Liquid effluents:

Gamma Spectroscopy, Liquid Scintillation.

5.

Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.

3rd 4th a.

Liquid Quarter Quarter 1.

Number of batch releases:

29 7

2.

Total time period for batch releases: (min.)

37465 69478 3.

Maximum time period for a batch release: (min.)

13260 12810 4.

Average time period for batch releases: (min.)

1292 2316 5.

Minimum time period for a batch release (min.)

145 4

6.

Average stream flow during periods of release of effluent into a flowing streams (Cat) 1.2.3 E6 1.31E6 b.

Gaseous 1.

Number of batch releases:

34 31 2.

Total time period for batch releases: (min.)

36887 52581 3.

Maximum time period for a batch releases (min.)

16123 27000 4.

Average time period for batch releases: (min.)

1085 1696 5.

Minimum time period for a batch releases (min.)

525 545 6.

Abnormal Releases 8503200268 850301 PDR ADOCK 05000209 l

a.

Liquid R

PDR 1.

Number of releases 0g 2.

Total activity releases:

N/A N/A l

b.

Caseous 1.

Number of releases: 2.

Total activity released:

N/A N/A

I f

TABLE 1A EFFLUENT AND WASTE DISPOSAL SDilANNUAL REPORT (1934)

CASEOUS EFFLUENTS - SUMfATION OF ALL RELEASES I

l Unit Quarter Quarter l Est. Total,i 3rd 4th

! Error.%

l.

1 A. Fission & activation gases l

_1. Total release Ci

<l.00E-4, <l.00E-4 N.A.

2. Average release rate for period

' DCi/see l

N.A.

N.A.

l 3. Percent of ' technical specification limit I } B.

Iodines

1. Total iodine - 131 Ci I

<1.00E-8, <1.00E-8 N.A.

2. Average release rate for period

.DCi/sec l

N.A.

N.A.

3. Percent of technical specification limit l

0-,

C.

Particulites

1. Particulates with half-lives > 8 days Ci

<1.00E-4,

1.27E-9 2.5El

2. Average release rate for period UCi/see l

N.A.

1.60E-10

3. Percent of technical spec'ification limit l

l 4. Gross alpha radioactivity Ci l <l.00E-11,l 7.93E-10 D.

Tritium

!1.Totalrelease Ct l 1.93E-5 j 1.79E-5 i 2.5El l

l 2. Average release rate for period LCi/sec l2.43E-6 j 2.25E-6 !

l 3. Percent of technical specification limit l

l l

i l

l Nite All less than (<) values are in pCi/cc.

l l

0% Tech Spec limits:

Listed on Dose Summary Table i

f

T TABLE 1C EFFLUENT AND k'ASTE DISPOSAL SEMIANNUAL REPORT (1984 )

CASEOUS EFFLUENTS - CROUND-LEVEL RELEASES Continuous Mode Batch Mode

.l Unit Quarter Quarter Quarter Quarter l

Nuclides Released i

3rd 4th 3rd 4th e

1.

Fission gases krypton-85 ci

<3.00E-6

<8.00E-6

<8.00E-6

<8.00E-6 krypton-85m ci

<5.00E-8

<5.00E-8

<5.00E-8

<5.00E-8 l

krypton-87 ci

<8.00E-8

<8.00E-8

<8.00E-8

<8.00E-8 krypton-88 ci

<l.00E-7

<1.00E-7

<1.00E-7

<1.00E-7 xenon-133 ci

<8.00E-8

<8.00E-8

<8.00E-8

<8.00E-8 xenon-135 ci

,<5.00E-8

<5.00E-8

<5.00E-8

<5.00E-8 xenon-135m ci

<5.00E-7

<5.00E-7

<5.00E-7

<5.00E-7 xenon-138 ci

<3.00E-7

<3.00E-7

<3.00E-7

<3.00E-7 Others (specify)

Ci Ci Ci unidentified Ci l

Total for period l ci l l 2.

Iodines iodine-131 ci

<1.00E-12

<1.00E-12 I<1.00E-8 l<1.00E-8 l

iodine-133 l ci

<1.00E-10 l <1.00E-10

<1.00E-8

<1.00E-8 iodine-135 ci

<1.00E-10

<1.00E-10

<1.00E-8

<1.00E-8 T tal for period ci l '

3.

Particulates strontium-89 Ci

<1.00E-11

<1.00E-11 strontium-90 Ci l <1.00E-11 1.27E-9 l

l I

cestum-134 ci

<1.00E-11

<1.00E-11 1<1.00E-8

!<1.00E-8 ccsium-137 ci l <1.00E-11 l <1.00E-11 l<1.00E-8

< 1. 00,E-8 bnrium-lanthanum-140 l Ci j<1.00E-11 }<1.00E-11 i<1.00E-8 1<1.00E-8 Nota:

All less than values (<) are in pCi/cc.

j

r-TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (l984)

LIQUID EFFLUENTS-SLMfATION OF ALL RELEASES Unit Quarter Quarter Est. Total l 3rd 4th Error. %

l A.

Fission and activation products l

1.

Total release (not including tritium, gases alpha)

C1 1.28E-3 7.07E-3

2. 5 F1 2.

Average diluted concentration l

during period pCi/mi 1.33E-10 8.13E-10 3.

Percent of applicable limit g

I l

B. Tritium l

1.

Total release C1 2.16E-1 3.26E-1 2.5El 2.

Average diluted concentration pCi/mi 2.25E-8 3.75E-8 l

during period l

3.

Percent of applicable limit l

I l

C.

Dissolved and entrained gases l

!1. Total release Ci l <l.00E-4

<l.00E-4 ! 2.5El 2.

Average diluted concentration i

during period pCi/mi N.A.

N.A.

b.

Percent of applicable limit 7.

! l l D.

Gross alpha radioactivity

p. Total Release Ci

.a.

l n-1 2.5El l

l Volume of waste released (prior to dilution) l liters l 5.52E6 6.7AE6 l 1.0E1

.i. Volume of dilution water used during period. j literal 9.60E9 8.70E9

!1.0E1 N:te All less than values (<) are in pCi/ml.

Cf. Tech. Spec. Limits:

Listed on Dose Summary Table.

1 I

TABLE 28 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984 )

LIQUID EFFLUENTS Continuous Mode Batch Mode Unit Quarter l Quarter Quarter Quarter Nuclides Released 3rd 4th 3rd 4th strontium-89 ci

<5.00E-8

<5.00E-8

<5.00E-8

<5.00E-8 strontium-90 ci

<5.00E-8

<5.00E-8 l7.12E-6 1.34E-3 cesium-134 ci

<5.00E-7

<5.00E-7 4.87E-5 3.07E-4 cesium-137 ci

<5.00E :< 5. 00 E-7 1.14E-3 3.42E-3 iodine-131

' ci

<1.00E-6

<1.00E-6

<1.00E-6

,< 1. 00E-6 cobalt-58 ci

<s.coE 7

<5.00r 7

<5.00r 7

<5 onr 7 cobalt-60 ci

<5.00E-7

<5.00E 7 9.19F-5 1.64F-4 iron-59 ci

<5.00E-7

<5.00E-7

<5.00E-7

<5.00E-7 zine-65 ci

<5.00E-7

<5.00E-7

<5.00E-7

<5.00F-7 manganese-54 Ci

<5.00E-7

<5.00E-7

<5.00E-7

<5.00r-7 l

chromium-51 ci

<5.00E-7

<5.00E-7

<5.00E-7

<5.00E-7 zirconium-a13bium-95 ci

<5.00E-7

<5.00E.7

<5.00E-7

<5.00E-7 l

l molybdenum-99 ci

<5.00E-7

<5.00E-7

<5.00E-7

<5.00E-7 l

technetium-99m ci

<5.00E-7

<5.00E-7

<5.00E-7

<5.00E-7 l

barium-lanthanum-140 ci

<5.00E-7 l<5.00E-7

'5.00E-7

'5.00E-7 l cerium-141 1

ci

<5.00E-7 I<5.00E-7

<5.00E-7 l<5.00E-7 Other (specify)

I I

I I

ci Iron-55 l

Ci

<1.00E-6

!<1.00E-6 k.00E-6 1.60E-3 l

i

! A n timony-125 ci

<5.00E-7

!<5.00E-7 h5.00E-7 I.05E-5 l 4

l l Phosphorus-32 ci

<1.00E-6 I<1.00E-6 h1.00E-6

<1.00E-6 l

Total for period (above) ci 1.28E-3 7.07E-3 xenon-133 ci l<l.00E-4 l<1.00E-4 Igl.00E-4 hl.00E-4 l xenon-135 ci j<l.00E-4 j<l.00E-4 kl.00E-4 hl.00E-4 I l

l l

l a

.- ~. _.

=-

TABLE-3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Q 984 )

SOLID WASTE AND IRRADIATED FUEL SHIPMEXTS s.

A.

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

~

1. Type of waste 6 M0.WH ESL Tom UNIT I PERIOD ERROR, %

a.

Spent resins, filter sludges, mJ 144.42 5.00

[

evaporator bottoms, etc.

C1 354.34 i

b.

Dry compressible waste, contaisinated m3 66.24 equipment, etc.

Ci 4.182 5.00 j

c.

Irradiated cc.nponents, control, rods, m3 N.A.

N.A.

etc.

Ci d.

Other (describe) mJ N.A.

N.A.

Ci e

2.

Estimate of major nuclide i

l-composition (by type of waste)

F a.

Cs-137 54.42%

Ni-63 21.03%

i fs Cs-134 14.37%

i j

H-3 5.34%

i l

b.

Cs-137 33.92%

H-3 55.28%

l co-60 2.38%

N1-63 4.42%

j Cs-134 3.04%

c.

i

}

i d.

I i

l t

i l

t t

}

3.

Solid Waste Disposition l

i i

Number of Shipments Mode of Transportation i

Destination i

a.

10 Shipments i Tractor / Flatbed Hanford. WA

)

a.

3 Shipments Tractor / F1atbed i

BarnwelI. SC a.

5 Shipments Tractor /14/190M-Cask i

Barnwell. SC i

b.

3 Shipments i Tractor / Flatbed i

Hanford. WA b.

3 Shipments Tractor / Closed Van Hanford, WA B.

• Irrabbuel ShipmentsNsfobony ask BarnweH, SC t

1 4

l Number of Shipments fModeofTransportation Destination

{

j M/A i

i l

M/A e

s e

i

• 1a.

Evap. bottoms solidified in steel liners using cement resins dewatered in High Integrity Containers l b.

Shipped in LSA (Type A) steel drums, and LSA steel boxes.

i Ic.

N.A.

id.

N.A.

i l

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

)

1 PLANT NAME:

THREE MILE ISLAND UNIT -l YEAR:

1984 i

MAXIMUM OFF-SITE DOSES AND DOSE C009fI'INENTS TO MEMBERS OF Tile PUBLIC **

SOURCE IST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER YEAR LIQUIn 1.22E-1 mrem 1.58E-Imren 1.91E-2 mrem 7.54E-2 aren SEE ANNUAL, EFFLUENTS Adult Wole Body Adult Whole Adult Whole Adult Whole Body Body Body AIRBORNE EFFLUENTS.

~

todines/Particulates 3.50E-9 mrem 3.81E-9 mrem 2.43E-7 mren SEE ANNUAL Clilld Bone REMP REP RT Total Body /Chilc Total Body / Child Noble Cases 4.8SE-5 mrem air 2.02E-6 mrcm

~

-0 mrad mrad dose (BETA) air dose (BETA) 2.58E-5 mrem skin L.24E-6 mrem skin

• • See THI-1 Semi-Annual Reports for 1984 Based on meteorology data provided in the TMI Unit I 1984 Semi-Annual Reports, as required by Reg. Guide 1.21.

YF m

M

~

ATTACHMENT ATTACHMENT - Joint Frequency Tables for 3rd Quarter (1984)

ATTACHNENT - Joint Frequency Tables for 4th Quarter (1984)

ATTACHMENT - Summary of Maximum Individual Dose Accumulation for Third Quarter of 1984 ATTACHMENT - Summary of Maximum Individual Dose Accumulation for Fourth Quarter of 1984 i

i l

1

.f

UNIT 1 Quarter Dose Report SUttiARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT I FROM July 1, 1984 through September 30, 1984

=

Estimated Location

% of Applicable Dose Age Dist Dir Applicable 10CFR50 App. I Effluent Organ (arem)

Croup (m)

(toward)

Limit Limits (area)

Quarterly Annual Ouarterly Annual Liquid Total Body 1.91E-2 Adult Receptor 1 1.3 6.4E-1 1.5 3.0 Liquid Liver 2.99E-2 Teen Receptor 1 6.0E-1 3.0E-1 5.0 10.0 Noble Cas Air Dose 0

5.0 10.0 (gamma-mrad)

Noble Gas Air Dose 0

10,0 20.0 i

(beta-mrad)

Nobis Gas Total Body 0

5.0 Noble Gas Skin 0

15.0 L__

=.. - - -

- _ = = = - - -

Iodine &

Total Body 3.81E-9 Child 3000 NNE 5.lE-9 2.5E-8 7.5 15.0 P ticulates n_

- - - - _ _ - - _ _ _ - _ _ - _ - _ - _ _ _ _ _ _=_- _- _

SUMMARY

OF MAXIMUM POPULATION DOSES FOR UNIT 1 FROM July 1, 1984 through September 30, 1984

--=

=--

Estimated Applicable Population Dose Effluent Organ (person-res)

Liquid Total Body 5.5E-3 Liquid Bone 8.8E-3 Caseous Total Body 1.6E-7 GI-Tract, Liver, Kidney, Lung, Thyroid 1.6E-7

UNIT 1 Quarter Dose Report SIMtARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT I FROM October 1. 1984 through December 31. 1984

.=-

_=-=_.

Estimated Loca*. ton

% of I

Applicable Dose Age Dist Dir Applicable 10CFR50 App. I Effluent Organ (mrem)

Croup (m)

(toward)

Limit Limits (mrem) i Quarterly Annual Quarterly Annual Liquid Total Body 7.54E-2 Adult Receptor 1 5.0 2.5 1.5 J.0 Liquid Bone 1.20E-1 Child Receptor 1 2.4 1.2 5.0 10.0

- - =. _ _ _ _ _ - -

_. -...=---

Noble Gas Air Dose 0

5.0 10.0 (gamma-mrad)

Noble Gas Air Dose 0

10,0 20.0 (beta-mrad) 5,0 Noble Gas Total Body 0

15.0 Noble Gas Skin 0

= - _ _ _ _ _ _ _.

s---

Iodine &

Particulates Bone 2.43E-7 Child 2500 WHW 3.2E-6 1.6E-6 7.5 15.0

_ - - _ - - _ - _ - _ _- _ _= _ - _ _ _- - - - _ _ _ -____ _--_-- _- - - - - - _=- _ -

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

m--_

=.

SUMMARY

OF MAXIMUM POPULATION DOSES FOR UNIT 1 FROM October 1, 1984 through December 31, 1984

=_= ___

=

-=__

- - - = _ _ - - _ _ _ _ _ _ _ _

Estimated Applicable Population Dose Effluent Organ (person-rem)

Liquid Total Body 1.6E-l' Liquid Bone 6.0E-1 Caneous Total Body 1.lE-6 Caseous Bone 3.5E-6

THIRD QUARTER 1984 J0174T FREQUENCY TABLES SITE 188EE MILE ISLB.

Sf/SS/95 89 48 SITE fpWIEE MILE ISLB.

W/W/W IS m MSum$ AT EAcae WIIe SPEES Ale sinEttsges eeOuRS A1 EACse W313 yEE3 Age pgSEggelo PE8808 0F BECORD =

94870809 84885824 PERIOS OF IIECORB =

S4879tSt 9400Wt4 51AS:LITT CLASE.

A 31/3Z STASILit? CLASS.

S 81/82 ELEVAftOpe.

SPEED.5PIWA 318EC1f ele.DIISSA LAPSE.3TISSA EL EV AT I0pe.

SPEED 5PISSA DISECTIEpe.BilSSA LAPSE.SitSSA W#983 WEESffppel WfBe3 WE3ffWNt

....-..I CIe t-3 4-7 S-12 13 18 IS-24

>24 1STAL DIRECT

.....3..18 89 24 af4 TOTAL Bl81EC1 XOle I-5 47 S-82 1 se 3

8 5

1 S

S 17 fe 2

e 1

9 8

8 3

pSE I

7 i

S S

S S

Bi8E 2

2 9

0 8

8 4

sig S

S 2

3 S

S 2

AE S

e 2

s e

S 3

DE I

3 1

0 8

9 8

EseE I

3 S

S S

S 4

E 2

3 S

S S

S IS E

3 4

S S

S S

7 EE 4

S S

S S

S IS ESE 2

4 i

S S

S 7

E I

S 3

0 0

9 IF SE 2

IS 2

0 3

0 34 SK S

83 2

S S

S 28 SSE I

I 2

S S

S S

5 4

23 1

S S

S W

5 4

S I

e S

8 31

$$W S

33 IS S

S S

St 55W 2

8 6

0 S

S 38 SW 4

IS 3

8 9

0 25 Sv 2

4 2

S S

S S

W5W IF S

4 S

S S

2c WSW S

2 2

9 0

S S

W 8

18 8

8 9

9 IS V

I I

I O

8 3

5 l#8W IS El 18 S

S S

82 Wesw I

S S

S S

y 18W 15 SS 33 4

I e

ISS

'vW 2

4 3

0 0

8 g

1888W 17 38 27 4

S S

70 8888b I

2 2

S S

g 107AL IS2 2SS 138 9

I e

400 TOTAL 31 S1 26 3

S S

IIS PER:005 Or CAttt f M00951 :

9 PERf 005 OF CALitt-e0 Ult 55 0

VARIASLE Bl#ECT!Oos 33 vARfAteLE 8ImEC180se S

N00#5 0F F9!5518eG DAT A -

29 HOURS CF n f 55118C DA1 A -

28 W /W/W 18:03 M M 88'92 Site. TMSE ftILE ISLS.

S!ft. ToSEE fetLE ISLS.

H0up5 AT EACat WitG SP E 9 A800 DipECTICII geOup5 AT EACs4 WIIG SPEES A8G Sf8ECTISIO PEnf 0D OF IeECOng =

S4878:01 848833r4 PERISS OF #ECENt3 =

S4879388-94089824 STASJLifv CLASS, 9

J1/32 DIREC180BI.BileSA LAPSE.St 9SA ELEv At tone.

SPEED.5PIGSA BlWEC1f 01s.BiteSA LAPSEiDTISSA 5'ASILl1T CLASS.

E NT/3r

- - - - -.. - - - - -. -.. - - - - - - - - -.. - - - ~ ~ ~.. - - - - - - - - - -. - -... ~.

ELEV Af l0Ie t.....SPEES.SplSSA.. -.. -... - -.. -. ~. - - - - - - -. - - - -. - -. - - - - - - - - - - -

WIIW WEE 9ferees Wits $ptEBit9941 WI'd S!hECilse 3-3 47 S-12 85-18 IS-24

• 24 TOTAL BIRECT yces 13 47 S.IF 13-10 19-24

>24 TOTAL Wiles s.

8 0

0 S

S S

S De S

ll 3

S S

S IS pesE S

S S

S S

8 MsE 5

4 S

S S

S S

pet 3

8 8

8 8

9 I

swE 8

4 8

8 8

8 5

I S

S S

S S

8 ENE IS S

2 S

S S

20 i

3 S

S S

S 4

E IS 25 9

9 9

8 48 (p.E ESE 3

S S

S S

S II ESE 12 22 S

S S

S be g

St 2

2 S

S S

S 4

SE 7

25 9

8 8

9 12 SSE 3

5 1

8 8

0 9

SSE ft 22 2

S S

S 34 S

S S

S S

I 5

0 87 Il S

G S

37 55W W

t 4

2 8

0 7

SSW 5

22 82 I

S S

40 5

3 3

0 3

S S

2 SW 7

84 7

0 0

S 20 S

2 9

8 8

9 2

45W 8

6 2

S S

S IS SW 2

8 8

8 9

9 2

W G

7 4

9 0

0 17 b5W 8

8 2

8 8

8 2

kW 3

82 2

3 8

8 29 t,

8 8

2 1

8 9

3 kW S

27 13 4

S S

SS basW ha W 3

I I

S S

S S

8dfW 3

ft 3

3 S

S IS pov TOTAL 8:2 236 St Il 9

0 429 TOT AL IS 24 IS 3

3 S

SS PERIO9S OF CAttttHCOR51, 3

PER10BS OF CAtt*lHouR51, 9

VARI ASLE 31#EC1108.

33 van 3ASLE SIpEC? lops S

HOURS Cr til551 PEG DAT A,

29 HOues or n85%Isoc SAT A 29

THIRD QUARTER 1984 JOINT FREQUENCY TABLES Sitt. Ts4REE MILE ISLB.

82/88#88 IS'"

5f fE, TeeEE MILE ISLS.

Sf/SO/W 10.39 te0LstS At EAC#8 Wftet SMED ANS Sl8EC180N Houms A1 EACH wits 8 SPEED Ases Rf8ECfl0Be PERISS OF SECOSS e 94878188-84885824 PER108 0F BIE0089

• S4873191 84883824 STASIL111 CLASS.

E 31/82 STASILITY class.

F 31/32 ELEv4110ps.

SPEED.SPISBA SIIIEC1101s.SilSSA LAPSE.3TISSA ELEVA180N.

SPEES.SPISSA 3ISEC1fes.DIISSA LAPSE.911SSA

...... -...... -........ - - -.. - -.. - ~. - - - - - - - - - - -. - -. - -. - - - - -

WIte8 SPEE3f M I yggg gpggggggg Wife 8 WleeS DISECT itus s.3 47 S.12 13-10 18-24 m24 TOTAL SIRECliose I.3 4-7 S-12 13 10 18 24

>24 TOTAL De S

33 8

8 8

8 SS N

13 4

I S

S S

IS 8e(

0 22 8

8 9

9 38 8

2 S

S S

S

, set I,S tee S

is S

S S

S 25

,g g

3 g

g g

g EleE S

4 S

S S

63 gyg gg g

g g

g g

g, E

32 S

S S

S S

48 E

14 5

S S

S S

IS ESE 29 18 S

S 8

9 II ESC 35 S

S S

S S

48 SE I4 Il S

S 8

N 2S SE 2S S

S S

S S

34 55E 26 37 8

8 3

43 SSE 22 2

S S

S S

24 5

23 37 8

9 0

8 38 5

27 2

S S

S S

20 55v 28 34 3

3 S

S 57 SSW 24 5

8 8

8 8

20 Sw 20 21 3

8 8

9 44 SW 12 5

0 8

S S

17 h$w 28 IS I

1 8

8 47 wSw 33 i

S S

S g

34 y

34 23 3

8 8

8 SS w

2g 9

S S

g 35 woey 14 23 Il I

S S

48 kN.a 83 4

1 3

8 9

IS sew I4 35 37 I

S S

87 86v 6

8 5

9 9

9 IS peev 38 27 Il S

S S

44 heeW 7

14 2

9 0

8 23 Tot AL 293 Els S2 3

S S

Sd7-total 2SI 70 IS S

S S

348 9

PE888036 DF C At t* f 843UR58 vAalASLE eleECT*0Be k3 ptp1036 0F CALNfM0be53 e

i vAplASit alpECTION SI Mcues w nI5588ec OATA 28 ecum5 or rel551pec paTA.

28 l

5fft. TeenEE isILE IEL3 32/90/98 18.12 5fft. 1:4 TEE fille ISLS.

82/98/98 19 13 esouSS A1 EACH Wile 8 SPEED A8e8 SileECTIsle le0USS AT EACH WIIES SPEED A888 SISEC180se PERIOS OF RECORB =

S48798SI-84SSSSr4 PERIOS OF SECSDS e 34878tSI.9400 Mt4 51ASILiff CLASS:

C 91/32 STASILIIT CLASS.

ALL 87/82

.............-...........--........--.....---.. LAPSE.9TISSA SPEE9.SPIMA afflECTiges.SilSSA ELEVATION.

SPEES.SPISA

.......-..ICII.BilSSA LAPSE.SflSSA SIflECT ELEVAtlose.

Vitas SPEE3ffW 1 Witas SPEE9tlept WINS WI8e8 l

pfmECTIOpe 83 4-7 S-12 13-19 18 24 m24 TOTAL SIREC110N 11 4-7 S-12 13-19 10 24

• 24 TOTAL De I

S S

S S

S S

N 33 SS IS I

S S

IM hasE I

S S

S S

S I

Nest 25 38 7

8 8

8 79 NE 2

S S

S S

S 2

M IS 27 4

S S

S 47 Lag S

I S

S S

S I

Eld 30 28 4

S S

S SS E

3 1

9 8

8 8

4 E

78 49 5

S S

S 124 ESE S

S S

S S

S S

ESE S4 SS S

S S

S s4S SE 5

S S

S S

S S

SE "S

SS S

S S

S 328 SSE 7

8 8

8 8

8 7

SSE 7S S2 7

8 8

8 844 5

3 S

S S

S S

3 5

69 SS 95 8

8 9

149 55v 7

0 8

8 8

8 7

55w 67 183 44 3

8 9

237 Sw 4

S S

S S

S 4

SW SS S3 35 S

S S

s29 wSW 9

9 0

S S

S S

ESV 73 39 e

i S

S 125 y

7 3

3 S

S S

IS b

04 54 S

S S

S 148 wesw 5

0 8

8 8

3 5

h86W 58 75 33 4

S S

IS3 ww 3

I 8

9 3

3 4

hw 46 138 73 10 8

8 269 hasw S

I S

S S

S I

kNw 42 SS 46 S

S S

876 101AL ES 7

8 8

8 8

72 101AL 9 72 SGI 299 27 I

O 2889 PERIODS Of CAiM Houe5I.

9 PERICDS OF CALNfMC* Jest 9

4 i

vapl ASLE OlptC180se S

v8RfASLE SIPECTione 213 HOURS OF MIS 5iteG Data 29 Hevers Der plssiper. Data 29

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FOURTH QUARTER 1984 JOINT FREQUENCY TABLES savE. veSiEE nstE ras.

GreewSS 'S d' sivE. ve=EE nlLE fa s.

SesSO/SS es.Se seuSs At EAtse wiss SPEES AIG SfMC1ggSg IEDips AT EACM WIIG SPEES Asg 33Mg1pgge PES 800 SF IECESDS =

S4I NISI.04825124 PERIOB OF MCSS9.

S4ISS:SI-94s23824 STASILITY CLASS.

A ST/St 51 ASILity CL Ass.

3 ST/SZ ELEVAll0es ELEVATISe.

SPEES. spi m NSECTISI.9ftMA LAPSE.SelSSA SPEES.SPISSA SIRECT30gs.9f9 M

. LAPSE. ST I Sta

............~................

wlNS SPEEartSW WI8e3 SPEE3trenne wgeg WING SIREC1 lose I-3 4-7 S-12 13-10 39-24

>24 1DTAL SinEC t :0se t.3 47 8 82 33.g3 38 24

>24 TOTAL N

I 2

I S

S S

4 N

3 3

3 8

g g

3 fedE 2

I S

S S

S 3

Nhc 8

9 9

9 g

g g

M S

3 8

8 8

8 3

E 8

3 3

8 9

8 4

EE I

8 8

9 S

S 3

EM-S 8

8 9

9 8

L 8

2 S

S S

S 2

E 8

3 3

S S

S I

ESE 5

S I

S S

S 12 ESE S

2 2

3 8

9 4

SE 3

8 8

8 8

9 IS SE S

4 S

S S

S 4

SSE I

2 S

S S

S 3

SSE 3

2 8

8 8

9 5

5 4

5 3

9 R

S 12 S

2 3

2 S

S S

7 55W 3

7 5

3 S

S 39 SSW 3

I S

S S

S 4

SW 3

3 9

4 S

S II Sb I

3 9

g g

y W5W 4

3 2

3 S

S S

WSW I

5 8

8 8

8 2

W 4

5

?

2 I

O 13 W

2 4

5 5

S S

et wests S

7

.3 5

S IS WW I

3 8

I O

se dew fI I4 9

II 2

S og NW e

8 3

g 4

g gg 8888W d

le le 83 9

9 37 Nhw 4

S 8

3 S

83

---..-.....-...-...........S TOTAL S2 76 34 38 4

8 294 tc*AL 28 El le 24 S

OS

---

.......----.............................S PERIOSS y CALntHOUR5:,

28 PERIODS Or CALnsHouR51 20 vastASLE SIPECTION is VA#lASL[ SfREC11CN 7

hours w ntssihc DATA.

S3 NCup5 er pl5%Ihc 3ATA.

53 S!?E. Tiett MILE IRS.

MM 38'M E!?E. TeeEE nsLE ISLS.

gju gg,4g 3W4995 A1 EAC84 W198 SPEES MS SIMC3388 PERIOS OF mECape'*"8'8 8 8

88e 9I9tCTte' PEstSS OF SECSDS =

S4889 34:25124 n

N N3.SPIMA SIREC1JWS.Sil m LAPSEiSTISSA STASILI*v CLASS.

9 91/93 ELEvATIeu.

SPEES.gPI m 3gSggtggSe,3gg g a tgpgg,gggggg wgeg WING SPEEBrtWI BlptCTION I.3 4-7 S-12 13-89 19-24

• 24 TOTAL WINI SimECTION 1-3 47 8.f2 93 49 13 24

>24 TOTAL

~~~~~~~~~

h 8

i S

S S

S I

Il S

S S

S S

El po eg 9

3 S

S S

S S

i s

peL i

S S

S S

S I

""E 14 8

3 S

S S

23 (g

g 8

9 8

8 8

I M

li 3

8 8

S S

IS t

8 s

3 S

S S

I EE ll 8

8 8

8 8

23 g3t 4

I I

S S

S S

E IS 21 3

3 S

S 42 5t 3

s S

S S

S 4

E b,-

IG de 7

8 9

3 s3 SSE 3

8 g

g g

g g

SE S

2g 38 4

S S

SI 5

S S

S S

S S

S SSE IS 28 3

S S

S 34 55W 9

2 l

I g

8 4

5 S

r4 3

9 3

g pg SW I

2 0

8 9

9 3

55b, 15 IS 7

8 8

8 37 W5W 2

S S

S S

3 2

SW 5

S S

9 g

gg w

I I

1 4

S S

S WSW s

O S

g g

g 74 weev 9

2 2

4 S

S S

W IS 23 28 IS 2

8 75 l

pov 2

I I

s S

S IS WNW 3

23 43 48 8

8 323 h'

7 le 27 28 5

3 Ss i

popew I

3 3

1 S

S S

hadb fp gy 33 4

g g

43 j

~~~"~"~~~~~~"~~~ISS

..........................-.-.........'S

Dial IS IS 88 S

S SS T01A.

283

SS 84 gS I'

PEpl095 Ol' CatttlMouRSI, 20

~~~"~"~~~~~~~"-~~~*----------------------.--g ygg wastI ASLE S181ECT ICM 4

PERf DOS F CALMsNOUR59 29 l

NOUSS N 'llS5ipsC BATA 55 VAftl ASLE BIRECT soss SS e43u#5 0F MI55;hG SATA, 53 i

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Si 8 s:e....-~..~-c.....:.:

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15

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e.a.g:=IV,w:W$e:35=lH:

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FOURTH QUARTER 1984 JOINT FREQUENCY TABLES (Specific Release Periods)

S p t. M et sen t f a s.

W IT. ISoff I entres 39,s4 s! tee DSSE solts fas.

48 17. 00:17 85/31/05 30.15 seSims At wase sSe asSatTress getfus AT EACM V81e AIG SIMET#198 PESIOS SF IIECOSS.

Sei 89-44e pgSISS W MCWS

• 84 8E8 I

51ASILI19 CLASS.

8 ST/SE giASgtsty CLASS.

A ST/

ELEVA110h.

SPEED.$PISSA SilIECTime.3f tSSA

- - - - -- ~ ~ ~ ~ -- -- --- ------- ---- ~ ~ -- L APSE. 3f t S8m EL EV AT I0es.

SPEE3.SplWA SISECTIW8DIlWA LA8SE. W MA

..................... -.. -..... - - - - - - - - -. - - - - - - - - * " * - ~ ~ ~ ~ ~

vlNS SPEEEtFEPeel wipeg SPEEStPS'948 vfhD ggseg DipE TICPe 33 47 S-12 t3-18 IS-24

• 24 TOTAL 35mLC1808e l ** 3 47 S.12 33-18 18 24 324 TOTAL

__......~.. __...

h 9

I O

S S

S 2

p, p

3 S

S S

3 peast S

3 3

S S

g g

we.

2 S

S S

S S

2 pet S

3 S

S S

S r

p,g 8

3 S

S S

S 3

Endt S

I S

S S

S 3

gwg g

3 a

S S

S 3

E S

e S

S 8

9 g

g 8

2 3

S S

S 2

ESE 8

3 2

9 3

8 3

E5e~

2 4

1 3

S S

7 SE S

2 S

S S

S 2

SE 2

4 3

8 8

8 7

SSE I

2 8

8 8

8 3

$$t S

2 S

S S

S 2

5 2

S S

S 4

5 2

8 3

3 S

S S

55%

3 g

S S

S 2

$$w 0

2 2

g S

S 5

Sw S

S t

8 8

8 e

Sw I

3 I

S S

S S

956 S

S S

S S

g g

W5v 2

I S

S S

S I

w 3

8 I

S S

2 w

2 I

8 8

8 8

I W'6%

S S

2 S

S 3

vaiw 4

4 8

8 8

8 8

NW S

e 2

S S

3 3

8 8

2 S

S 33 78W 8

3 S

I S

S 4

se,t, 2

y e

4 S

S 13

?ctAL t,

37 7

5 g

g

g. At 24 45 8

7 8

8 SE

........................,....................34 utg;;o n og c at tS N0lu158 G

PE*1035 Cr C Attie,0t.asi.

s vas : Am t. c apit 1 ? ope 2

v Aa s agt E E : =E C T IC's 84 W'S F fil558% 3A18 8

,c,*$ OF el55fesc 3A18-8 SITE. MSEE 80ft E ISLS.

18817. ISIf? I M/ft/SS 38 14 SITE. 78SIEE ftnt 79LS.

Isd!T. LSelf I SSntem 38,38 seats AT EACs4 vise WEES NG SIMCTICII fetSIS AT SAC 88 wieri SPEE8 NG Sffstfles PESim W M e Sel W128-44ffM S7 PESIM W IIECSS =

SelMIrt-94.3Sett stASILITY CLASS.

C ST/Sg STA88Litt CLASS.

9 ST/St ELEVAf f 0ne.

SPEES. SPI m SISECTilpee9Ilm LAPSE.SilSSA ELEVATIONr SPEES.W IM Blf8ECTitas.9ff m LAPS

...E.SftSSA WItet SPEE3ifen el WIMD SPEE98PEPHI v

wivt WIcet pipict f 3pe 13 4-7 S.t2 13-IS IS-24

>24 TOTAL DIRECil388

f. 3 4-7 S 12 II-IS IS-24 m24 TOTAq.

N 9

9 9

9 8

9 I

N 2

S 2

9 9

8 4

PSut S

9 9

8 8

8 0

'48 4 0

4 S

S S

S 33 8ut S

9 9

8 8

8 0

88E 4

5 8

8 8

8 5

Epee.

S S

S S

S S

S E86E IS S

S S

S S

39 E

S S

S S

S S

S E

S S

2 S

S S

IS ESE 3

e

?

S 8

8 3

ESE 7

IS 2

S S

S 28 SE I

I O

8 8

8 2

SE I

IS i

9 9

8 28 SSE S

S S

S S

S S

SSE S

IS t

S 8

9 gg 5

S S

S S

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ATTACHMENT I Revision 4 to the TMI-1 Off-Site Dose Calculation Manual (0DCM).

The TMI-1 ODCM, 9100-PLN-4200.01, Revision 4 was issued August 31, 1984, which was during the period of this Report (July 1 through December 31,1984).

The changes made in this Revision were administrative and will provide more explicit directions for implementation of the procedure. The REMP fish and aquatic sampling stations were changed from specific station locations to non-specific zones. The green leafy vegetables and fruits categories in Table A-1 were consolidated into one category " Food Products." This category consists of all NRC-required food stuff samples. The Table designators for the REMP sampling locations by media were amended to reflect the Table designators listed in the TMI-1 and TMI-2 Environmental Tech. Specs.

The following is a list of the page by page revisions. A copy of these pages are included for your reference.

Attachment ii - Table of Contents

1) Expanded Table A-1 to Tables 1 through 11 l

2) Renumbered Table A-2 as Table 12

3) Renumbered Map A-1, A-2 and A-3 to be Map 1, Map 2 and Map 3 respectively.

Page 3

1) Corrected Operations Procedure number from 1101.21 to 1101-2.1.

Page 4

1) Corrected to read "... past plant conditions. < LLD values..."

instead of "... past plant conditions < LLD values..."

Page 9

1) Section 4.2.3, second sentence was changed to read " Default parameter values..." instead of " Default parameters values..."

Page 12

1) Radionuclide I-133 Pi dose parameter was qualified with **, showing these values may be further reduced by a factor as large as 2 for the growing season and a second factor of 2 to allow for iodine effluent (see Note).

1 _.

Page 47

1) Changed Section 8 Tables A-1 and A-3 to Tables 1 through 12, and Map A-1, A-2 and A-3 to Map 1, 2, and 3 respectively.

Page 48

1) Changed Table A-1 to Table 1.

2) Eliminated the " Station Code" column so that only the NUREG Station-Codes are listed.

Page 49

1) Changed Table A-1 (continued) to Table 2.

2) Eliminated the " Station Code" column so that only the NUREG Station-Codes are listed.

Page 50

1) Changed Table A-1 (continued) to Table 2.

2) Eliminated the " Station Code" column so that only the NUREG Station-Codes are listed.

Page 51

1) Changed Table A-1 (continued) to Table 3 and Table 4.

2) Eliminated the " Station Code" column so that only the NUREG Station-Codes are listed.

Page 52

1) Changed Table A-1 (continued) to Table 5 and Table 6.

2) Eliminated the " Station Code" column so that only the NUREG Station-Codes are listed.

Page 53

1) Changed Table A-2 to Table 7 and Table 8.

2) Changed Table data and format to correlate to the new Tables.

Page 54

1) Changed Table A-2 to Table 9, Table 10 and Table 11.

2) Changed Table data and format to correlate to the new Tables.

Page 55

1) Changed Table A-2 to Table 12.

2) Eliminated the "NUREG Station Code" column.

3) Eliminated the (mi) note from " Distance" column and (0) note from

" Azimuth" column. l

Pag s 56 through 58

1) Added the pages to continue Table 12.

Page 59

1) Changed Map A-1 to Map 't.

i.

Page 60

1) Changed Map A-2 to Map C Page 61

1) Changed Map A-3 to Map 3.

j

?

i 0181A

Revision 4 List of Tables Page Table 2-1 Dose Factors for Noble Gases and Daughters 11 Table 2-2 Dose Parameters for Radiciodines and Radioactive 12 Particulate, Gaseous, Effluents Table 4-2.2 Pathway Dose Factors Due to Radionuclides Other 13 Than Noble Gases Table 1 TMINS REMP Station Locations Air Particulate 48 and Air Iodine i

Table 2 TMINS REMP Station Locations - Direct Radiation 48 (TLD)

Table 3 TMINS REMP Station Locations - Surface Water 50 j

f Table 4 TMINS REW Station Locations - Aquatic Sediment 51 Table 5 TMINS REMP Station Locations - Milk 51 Table 6 TMINS REW Station Locations - Fish and Aquatic 52 Plants Table 7 TMINS REW Station Locations - Food Products 52 Table 8 TMINS REMP Station Locations - Soil 53 Table 9 TMINS REMP Station Locations - Effluent water 53 Table 10 TMINS REW Station Locations - Precipitation 54 Table 11 TMINS REW Station Locations - Cryogenic Air 54 Sample Table 12 Radiological Environmental Monitoring Program 55 Sample Locations Map 1.

TMINS Location of Operational Radiological 59 Environmental Monitoring Stations within the Site Boundaries Mao 2 TMINS Location of Operational Radiological 60 Environmental Monitoring Stations within 5 miles of the Site Mao 3 TMINS Location of Operational Radiological 61 Environmental Monitoring Stations Greater than 5 miles from the Site 11

Revision 4 The setpoint concentration is converted to setpoint scale units using appropriate calibration factors.

This section of the ODCM is implemented by Operations Procedure 1101-2.1 Radiation Monitor System Setpoints and Radiological controls Procedure 1622 " Releasing Radioactive Gaseous Waste".

2.2 Other Isotopes Setpoints for monitors which detect isotopes other than noble gases are also established to assure that concentrations of these isotopes in gaseous effluents do not exceed the limits in 10 CFR 20.

Setpoints are established so as to satisfy the following equations:

t e<

1500 (eq. 2.2)

(F) x (P ) x (Dv) i where:

c=

setpoint concentration, in uCi/cc F=

effluent flow rate at the monitor, in cc/sec.

3 for the inhalation pathway Pi = pathway dose parameter, in mrem /yr per uCi/m and m2-mrem per uCi/sec for the food and ground pathway from Table 2-2.

yr 1500 = annual dose limit to any organ from particulates and iodines and radionuclides (other than noble gases) with half lives greater than eight days.

the annual average atmospheric dispersion factor for the worst-case D =

y sector; maximum X/Q, in sec/m3, for the i unrestrictedarea,andmaximumD/Q,inmghalationpathwayatthe i

, for the food and ground pathway at the nearest existing food and ground pathway locations.

Dispersion factors may be read or interpolated from Table B-1 (Appendix B) for releases from the station vent and Table B-2 (Appendix B) for all other releases.

The setpoint concentration is further reduced such that concer.tration contributions from multiple release points would not combine to exceed 10 CFR 20 limits.

The setpoint concentration is converted to setpoint scale units using appropriate calibration factors.

This section of the 00CM is implemented by Operations Procedure 1101-2.1 Radiation Monitor Systems Setpoints and Radiological l

Controls Procedure - 1622 " Releasing Radioactive Gaseous Waste".

t 2,

n

-v.--

,y

.,-,,w..,..

,,-,_,.w,-.+,-.-.

Rsvision 4 3.0 DOSE ASSESSENT (LIQUID EFFLUENTS) 3.1 LiquidEffluents-10CFR20 Limits For purposes of demonstrating compliance with 10 CFR 20 the following equation must be satisfied (C 3 E )i 1 (eg 3.1)

I i

i i

1 where:

Ci = the concentration of isotope, i, in the liquid effluent after dilution, in uCi/ml.

the maximum permissible concentration of isotope i in liquid effluent MPCi = in an unrestricted area per 10 CFR 20, Appendix B, Table II, Col 2 (See Appendix A to this manual) 3.2 Liquid Effluents - 10 CFR 50 Appendix I The dose from liquid effluents results from the consumption of fish and drinking water. Other pathways contribute negligibly at Three Mile Island. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression:

FW FW L

t Dose j = Z r (at ) X (C g) X [(AW j X ppg ) + ( AF j X FPt X 0.2)]

(eg. 3.2) g i

i i

i t where:

Dose j =

the cumulative dose commitment to the total body or any organ, j, from the liquid effluents for the total time period, in mrem.

the length of the tth time period over which Cit and at

=

t F are averaged for all liquid releases, in hours.

g Ci=

the average concentration of radionuclide i in undiluted liquid effluent during time period at fromanyl.iqu,idrelease,in g

uCi/ml.

NOTE:

For Sr-89, Sr-90, conservative concentration values will be used in the dose calculation based on similar past plant conditions. <LLD l

values are not used in dose calculations.

undiluted liquid waste flow, in gpm.

FW

=

g 9

_4-

R2 vision 4 the dose factor for each identified radionuclide, i, in, mrem /yr Ri=

per UCi/m3 for the inhalation pathway and m2. mrem /yr per uCi/sec for other pathways, from Table 4-2.2a.

Dy =

the annual average atmospheric dispersion parameter, for the worst-case sector, for estimati the dose to an individual at the criticallocatgon;X/Q,insec/m,fortheinhalationpathway, and D/Q, in m, for other pathways.

In the case of H-3 only X/Q's are used for all pcthways. Dispersion factors may be read or interpolated from Table B-1 (Appendix B) for station vent releases and Table B-2 (Appendix B) for all other releases.

release of radiciodines, and radioactive materials in particulate Qi=

form in gaseous effluents, i, with half-lives greater than 8 days, in uCi, cumulative over the specified time period.

3.17E-8 = inverse of the number of seconds in a year.

4.2.3 Alternative Calculational Methodologies As an alternative to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parameter values from Reg.

l Guide 1.109 (Rev.1) and/or actual site specific data can be used where applicable. Dispersion parameter values for such analyses may be drawn from Table B-1 and B-2 or may be computed from site meteorological data for the specified time period using acceptable models such as those presented in Regulatory Guide 1.111.

9-

Revision 3 Ttble 2-2 DOSE PARAKTERS FOR RADIOIODINES AM).'ADI0 ACTIVE PARTICULATE, GASEOUS, EFFLUENTS

• Pi Pi l

Pi Pi Radio-Inhalation Pathway Food & Ground Pathways l

Radio-Inhalation Pathway Food & Ground Pathways nuclide (neem /yr per 'C1/m3)

(m2. neem /yr per *C1/sec) nuclide (mrem /yr per "C1/m3)

(m2. mrem /yr per *Ci/sec)

H-3 6.5E+02 2.4E+03 I

Cd-115m 7.0E+04 4.8E+07 Cr-51 3.6E+02 1.1E+07 l

Sn-126

).2E+06 1.lE+09 Mn-54 2.5E+04 1.1E+09 1

Sb-125 1.5E+04 1.1E+09 Fe-59 2.4E+04 7.0E+08 1

Te-127m 3.8E+04 7.4E+10 Co-58 1.lE404 5.7E+08 l

Te-129m 3.2E+04 1.3E+09 Co 60 3.2E+04 4.E+09 i

Te-132 1.0E+03 7.2E+07 ZN 65 6.3E+04 1.7E+10 l

Cs-134 7.0E+05 5.3E+10 Rb 86 1.9E+05 1.6E+10 i

Cs-136 1.3E+05 5.4E+09 Sr 89 4.0E+05 1.0E+10 l

Cs-137 6.1E+05 4.7E+10 Sr 90 4.lE+07 9.5E+10 l

Ba-140 5.E+04 2.4E+08 Y-91 7.0E+04 1.9E409 l

.Ce-141 2.?E+04 8.7E+07 Zr 95 2.2E+04 3.5E+08 l

Ce-144 1.5E+05 6.5E+08 Nb 95 1.3E+04 3.6E+08 l

Np-239 2.5E+04 2.5E+06 MO 99 2.6E402 3.3E+08 l

I-131 1.5E+07 1.1E+12**

Ru 103 1.6E+04 3.4E+10 l

I-133 3.6E+06 9.6E+09'*

l Ru 106 1.6E+05 4.4E+11 l

Unident.

4.lE+07 9.5E+10 Ag 110m

),

3.3E+04 1.5E+10 l

I l

• The listed dose parameters are for radionuclides that may be detected in gaseous effluents. Additional dose parameters or isotopes not included in Table 2-2 may be calculated using the methodology described in NLREG-0133.

COThese values may be further reduced by a factor as large as 2.0 to allow for the half-year growing season and a second f ctor as lar as 2.0, to allow for 50% of the lodine effluent in organic form. These reductions confom to Reg. Guide 1.109 (Rev. 1.

Revision 4 l

5.0 LIQUID WASTE TREATENT SYSTEM 5.1 Operability The Liquid Waste Treatment System as described in Section 11 of the Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is available to perform its intended function:

a)

Miscellaneous Waste Evaporator (WOL-Z1B) or Reactor Coolant Evaporator (WOL-Z1A) b)

. Waste Evaporator Condensate Demineralizer (WDL-K3 A or B) c)

Waste Evaporator Condensate Storage Tank (WOL-T 11 A or B) d)

Evaporator Condensate Pumps (WDL-P 14 A or B) 5.2 Representative Sampling Prior to Discharge All liquid releases from the Liquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Tanks.

To provide thorough mixing and a representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate Transfer Pumps.

6.0 GASEOUS WASTE TREATMENT SYSTEM 6.1 Operability Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas from the vent heaoer/ tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release.

7.0 SOLID WASTE MANAGEMENT SYSTEM - PROCESS CONTROL PROGRAM (The Process Control Program is available as a separate document, see LIL 133, dated June 24, 1981.)

8.0 ENVIRONMENTAL MONITORING IWORMATION The Radiological Environmental Monitoring Program shall be conducted as outlined in Section 3.23, Table 3.23.1 of Amendment 72 to the TMINS Unit 1 Technical Specifications. Sampling locations will be as indicated in Tables 1 through 12 and Map 1, 2, and 3..

Revision 4 Table 1 THINS REMP STATION LOCATIONS-AIR PARTIOJLATE Ato AIR IODINE NBEG Station Code Distance Azimuth Al-1 0.4 mi.

00 El-2 0.4 90 M2-1 1.3 253 A3-1 2.6 358 H3-1 2.3 159 a

G10-1 9.8 127 J15-1 12.6 180 Q15-1 13.5 305 Table 2 TMINS REMP STATION LOCATIONS-OIRECT RADIATION (TLD)

NWEG Station Code Distance Azimuth Al-1 0.4 mi.

00 81-1 0.7 25 01-1 0.3 71 El-1 0.2 95 H1-1 0.4 167 J1-1 0.8 184 Kl-2 0.4 195 L1-1 0.1 221 N1-1 0.4 270 Pl-1 0.4 293 i

Ql-1 0.5 317 Rl-1 0.2 340 j

Cl-1 0.6 35 i

01-2 0.5 65 El-2 0.4 90 F1-1 0.5 117 Gl-2 0.6 143 L1-2 0.5 221 Rl-2 0.7 332

Revision 4 Table 2 b1NS EMP STATION LOCATIONS-DIRECT RADIATION (TLD) (CONT'D)

PUEG Station Code Distance Azimut1 K2-1 1.1 mi.

2000 L2-1 1.9 227 M2-1 1.3 253 N2-1 1.2 262 P2-1 1.6 297 02-1 1.8 310 A3-1 2.6 358 H3-1 2.3 159 A5-1 4.3 3

B5-1 4.8 18 C5-1 4.5 42 06-1 5.2 65 E5-1 4.6 81 F5-1 4.7 107 G5-1 4.8 131 H5-1 4.1 157 J5-1 4.9 182 K5-1 5.0 200 L5-1 4.1 228 M5-1 4.3 249 NS-1 4.9 268 P5-1 4.9 281 Q5-1 5.0 318 R5-1 4.9 339 810-1 9.4 21 C8-1 7.2 48 09-1 8.5 72 E7-1 6.8 86 E10-1 9.4 112 G10-1 9.8 127 H8-1 7.4 163 J7-1 6.5 177 K8-1 7.4 196 L8-1 8.0 225 - - -

Revision 4 Table 2 TMINS RO @ STATION LOCATIONS-DIRECT RADIATION (TLD) (CONT'0)

NLREG Station Code Distance Azimuth M9-1 8.6 mi.

2420 N8-1 7.8 260 P8-1 8.0 292 Q9-1 8.5 308 R9-1 8.1 340 C20-1 19.6 47 015-1 10.9 63 F25-1 21.1 113 G15-1 14.4 124 H15-1 13.2 157 J15-1 12.6 180 K15-1 12.7 204 L15-1 11.7 225 M15-1 11.9 237 N15-2 10.4 274 N15-1 13.2 276 P15-1 12.2 300 Q15-1 13.5 305 Q15-2 11.5 310 R15-1 11.2 330 Al-4 0.4 2

81-2~

0.4 26 B1-3 0.5 15-Cl-2 0.3 45 El-4 0.2 90 Gl-3 0.3 124 H1-9 0.3 148 J1-3 0.3 185 K1-5 0.2 202 Ki-4 0.2 208 N1-3 0.1 270 Ql-2 0.2 325 F1-2 0.2 102 50 -

)

Revision 4 Table 3 TMINS REW STATION LOCATIONS-SURFACE WATER (CONT'D_ )

NUREG Station Code Distance Azimuth N1-2A (R) 0.1 2700 J1-2 (R) 0.5 188 J2-1 (R) 1.5 182 A3-2 (R) 2.5 355 H3-2 (R) 2.3 165 H5-? (R,F) 4.1 160 09-1 (R,F) 8.5 30R G15-1 (F) 14.4 124 G15-2 (F) 13.6 128 G15-3 (F) 14.8 124 J15-2 (F) 14.7 178 F15-1 (R) 12.6 122 (R) = Raw Water (F) = Finished Water Table 4 TMINS RE W STATION LOCATIONS-AOUATIC SEDIT NT NUREG Station Code Distance Azimuth Al-3 0.7 mi.

08 G1-1 0.3 137 Kl-3 0.8 202 J2-1 1.5 182 K2-2 1.1 197 L1-3 0.5 225 51 -

Revision 4 Table 5 THINS REMP STATION LOCATIONS-MILK MJREG Station Code Distance Azimuth A2-1 ( W) 1.2 mi.

50 t

015-2 (MG) 10.0 68 02-1 (M) 1.1 65 G2-1 (M) 1.6 130 P7-1 (M) 6.7 293 A15-1 (M) 10.5 10 P4-1 (M) 3.6 295 E2-2 (M) 1.1 93 MG = Goat Milk M = Cow Milk Table 6 TMINS PEMP STATION LOCATIONS-FISH APO A00ATIC PLANTS Station Code Station Desionation I

TM-ACF-IlO Downstmam of Station Dischame TM-A0F-OKG Upst mam of Station Discharoe TM-AOP-IPO Downstream of Station Dischame TM-AOP-BKG Upstmam of Station Dischame AOF = Fish AOP = Aouatic Plants

I g

Revision 4 Table 7 TMINS REPP STATION LOCATIONS-FOOD PPODUCTS NJREG Station Code Distance Azimuth 02-1 (FPL) 1.1 mi.

650 G2-1 (FPL) 1.6 130 A9-2 (FPL) 9.3 357 P3-1 (FPL) 2.6 293 A15-1 (FPL) 10.5 10 El-3 (FPL) 0.7 90 E2-1 (FPL) 1.1 80 H1-2 (FPL) 0.9 150 TM-FPF-5F2 E6-1 5.9 100 12G2 M15-2 13.6 253 8Al H1-2 0.9-150 01-3 0.5 65 FPL = Broad Leaf Veoetation or Veoetables FPF = Fruits Table 8 TPINS REPP STATION LOCATIONS-SOIL NUREG Station Code Station Code Distance Azimuth TM-S-lC1 A3-3 2.5 mi.

3540 1F1 A9-1 9.2 0

1F2 A9-2 9.3 357 481 02-1 1.1 65 5Al' El-2 0.4 90 581 E2-1 1.1 80 782 G2-2 1.3 133 7B3 G2-3 1.6 132 7C1 G3-1 2.8 131 7F1 G10-1 9.8 jff 13.5 015-1 15g1 5F-

Revision 4 Table 9 TMINS REMP STATION LOCATIONS EFFLUENT WATER NUREG Station Code Distance Azimuth K1-1 0.2 mi.

2000 Table 10 TMINS REMP STATION LOCATIONS-PRECIPITATION NUREG Station Code Distance Azimuth El-2 0.4 mi.

900 H3-1 2.3 159 G10-1 9.8 127 Q15-1 13.5 305 A3-1 2.6 358 Table 11 TMINS REMP STATION LOCATIONS-CRYOGENIC AIR SAMPLE NUREG Station Code Distance Azimuth A3-1 2.6 mi.

3580 El-2 0.4 90 H3-1 2.3 159 M2-1 1.3 253 -

e Table 12 Revision 4 RAD 10LDGICALDtYIllDINENTAL PENITQglNG Panet $8lfLE Lor 4TIlkt Sample 5tation Map Medita

-.C9dt.-.

Ihdiff E111ADEC 821Balb Description AP.AI.ID Al-l 1

0.4 at 0*

ID N of site. North Weather Station TMI Al-4 0.4 2

N of Reactor Sutiding on W. fence adjacent to N Weather ID Station TMI 81-1 2

0.7 25 10 NME of site on light pole in middle of North Bridge THI 81-2 0.4 26 ID NNE of Reactor Butiding at Top of Dike TMI 81-3 0.5 15 NNE ef Reactor Butiding on W fence adjacent to S end of ID N Bridge TMI El-2 0.3 45 ID NE of Reactor Butiding at Top of Dike TMI D1-1 3

0.3 71 ID ENE of site on top of dtke, east fence TMI El-1 4

0.2 95 ID E of site on top of dike, east rence TMI El.4 0.2 90 10 E of Reactor Sutiding at Iop of Dike TMI ft-2 0.2 102 ESE of Reactor Butiding at top of Othe midway within ID Interim Solid Waste Staging factlity TMI GI-3 0.3 124 ID SE of Reactor Butiding at Top of Othe TMI HI-I 5

0.4 167 ID SSE THI Mi-9 0.3 148 ID SSE of Reactor Butiding at Top of Othe THI Ji-1 6

0.8 184 ID S TMI Ji-3 0.3 185 S of Reactor Butiding on wooden post by old S. Gate EW Guard ButIdtng TMI KI-I 7

0.2 200 ID Do site. RML-7 station discharge KI-2 8

0.4 195 10 SSW TMI KI-5 0.2 202 ID SSW of Reactor Butiding on fence behind Warehouse #3 iMI Ki

• 0.2 208 ID LS 4 9

0.1 221 SSW of Reactor Butiding on fence behind Warehouse s2 THI 10 SW of site. west of mechanical draft towers on dike TMI WI.

10 0.4 270 ID W of site on Shelley Island M l - r; 0.1 270 W of Reactor Butiding on fence adjacent to screenhouse SW entrance gate TMI NI-u 11 0.1 270 ID On site. station intakes (Units I & 21 Pt 12 0.4 293 ID WNW of site on Shelley Island O 's 83 0.5 317 10 NW of site on Shelley Island Ql-2 0.2 325 ID NW of Reactor Butiding on fence behind Warehouse al THI RI.I 14 0.2 340 AQS NNW of site at gate in fence on W side of THI. north boat dock Al-2 15 0.7 I

AQS N of site at North tip of THI Al-3 16 0.7 0

ID N of site at north tip of TMI Cl-I 17 0.6 35 ID NE of 56te on Route 441 N.

DI-2 18 0.5 65 AP.AIh'.ID.CR.S ENE of site on Laurel Road El-2 19 0.4 90 ID E of site on N side of Observation Center fl-1 20 0.5 117 AQS GI-1 21 0.3 137 ESE of site on Itoht pole on Route 441 N.

ID SE of site GI-2 22 0.6 143 SE of site on Route 441 S.

SW Ji-2 23 0.5 188 AQS Kl-3 24 0.8 202 SSW of site 5 of site below discharge pipe.___

Ttblo 12 (Cont'dl Revisloa 4 RADIOLOGICAL ENVIROMENTAL MONITORING PROGRAM SMFLE LOCATION (Cont'd)

Sample S'ation Map Medium Code Number Di stance Azimuth Description AQS L1-3 25 0.9 225 SW of site 3D Li-2 26 0.5 221 SW of site on Beech Island ID RI-2 27 0.7 332 NNW of site on Henry Island MG,FPL A2-1 26 1.2 5

N of site, f arm along Route 441 M, FPL,5 D2-1 29 1.1 65 ENE of site, f arm on Gingrich Road M,FPL G2-1 30 1.6 130 SE of site, farm on the E side of Conemago Creek SW,AQS J2-1 38 1.5 182 S of site above York Haven Dam ID K2-1 32 1.1 200 SSW of site on S Shelley Island ID L2-1 33 1.9 227 SW of site on Route 262 W,AI,lD.CH M2-1 34 1.3 253 WSW of site adjacent to Fishing Creek, Goldsboro Air Station ID N2-1 35 1.2 262 W of site at Goldsboro Marina ID P2-1 36 1.6 297 WNW of site of f of Old Goldsboro Pike ID 02-1 37 1.8 310 NW of site on access road along river N,Al.lD,RW,CR A3-1 39 2.6 356 N of site at Middletown Substation SW A3-2 40 2.5 355 N of site of Suotara Creek N,Al,RW,lD,CR H3-1 41 2.3 159 SSE of site at Falmouth-Collins Substation SW H3-2 42 2.3 165 SSE of site, York Haven Hydro M.FPL P4-1 43 3.6 295 WNW of site at Fisher's f arm on Valley Road ID A5-1 44 4.3 3

N of site on Vine Street exit from Route 283 ID B5-l 45 4.8 18 NNE of site, School House Lane and Miller Road ID C5-1 46 4.5 42 NE of site on Kennedy Lane ID Do-l 47 5.2 65 ENE of site off of Boagle Road I

ID E5-1 48 4.6 81 E of site, North Market Street and Zeager Road ib F5-1 49 4.7 107 ESE of site on Anosite Road ID GS-l 50 4.8 131 SE of site, Bainbridge and Risser Roads SW H5-2 51 4.1 160 SSE of site on Brunnor Island lD H5-1 52 4.1 157 SSE of site Guard Shack on Brunner Island ID J5-1 53 4.9 182 S of site on Canal Road, Conoungo Heights ID K5-1 54 5.0 200 SSW of site on Consuego Creek Road, Strinestoun ID L5-8 55*

4.1 228 SW of site, Stevens and Wilson Roads ID MS-l 56 4.3 249 WSW of site, Loulsberry and Roxberry Roads, Neuberrytoun 10 NS-1 57 4.9 268 W of site, of f of Old York Road on Robin Hood Drive

)

ID PS-l 58 4.9 281 WNW of site, Route 262 and Beinhower Road ID Q5-1 59 5.0 318 NW of site on Lunber Street, Highspire ID RS-1 60 4.9 339 NNW of site, Spring Garden Drive and Route 441 ID l DIO-l 61 9.4 21 NNW of site, West Araba Avenue and Mill Street, Hershey ID

C8-1 62 7.2 48 NE of site, Schenk's Church on School House Road ID D9-1 63 8.5 72 ENE of site on Mt. Gretna Road, Bellaire ID E7-1 64 6.0 86 E of site on Hummelstown Street, Ell.tabethtown FPF Eb-1 65 5.9 100 E of site, orchard at Masonic Homes ID F10-1 66 9.4 112 ESE of site, Donegal Springs Road, Donegal Springs

1. ,Al,RW,lD,S Glo-l 67 9.8 127 SE of site at f arm of f Engle's Toligate Road l

i isble 12 (Cent'd)

Revision 4 RADIOLOGICAL ENVIROWENTAL MONITORING PROGRAM SAPPLE LOCATION (Cont'd) e Sample Station Map Dbdlum Code Number Di stance Azimuth Descr iption 3D HB-1 68 7.4 al 163*

SSE of site on Saginaw Road, Starview ID J F-1 69 6.5 177 S of site on Maple Street Manchester ID KS-1 70 7.4 1%

SSW of site, Coppenhaf for Road and Route 295, Zion's View ID LB-1 71 8.0 225 SW of site on Rohler's Church Rd., Andersontown 10 M9-1 72 8.6 242 WSW of site on Alpine Road, Maytour, ID NS-1 73 7.8 260 W of site on Route 382,1/2 mile north of Lewisberry 3D P8-1 74 8.0 292 WNW of site on Evergreen Road, Reeser's Summit M

P7-l 75 6.7 293 WNW of site on Old York Road, New Cumberland SW,lD Q9-1 76 8.5 308 NW of site across from parking lot of Steelton Water Company ID R9-1 77 8.1 340 NNW of site on Derry Street, Rutherford Heights M,FPL A15-1 78 10.5 10 NNE of site, f arm on Route 39. Hummelstown ID C20-8 79 19.6 47 NE of site on Cumberland Strer, Lebanon 10 D15-1 80 10.9 63 ENE of site, Route 241, Lawn, PA W,,FPL D15-2 81 10.0 68 ENE of site, Route 241, 200 meters South of PA Turrylke Davidhizer Farm ID F25-1 82 21.8 113 ESF of site, Steel Way and Loop Roads, Lancaster SW Fl5-1 83 12.6 122 ESE of site, Chickles Creek SW,lD Gl5-1 84 14.4 124 SE of site at Columbia Water Treatment Plant SW Gl5-2 85 13.6 128 SE of site, Wrightsville Water Treatment Plant SW Gl5-3 86 14.8 124 SE of site, Lancaster Water Treatment Plant ID Hl5-1 87 13.2 157 SSE of site, Orchard and Stonecod Roads, Wllshire Hills 1

/P Al lu J15-1 88 12.6 180 S of site in Met-Ed York Load Dispatch Station SW J15-2 89 14.7 178 S of site at York Water Campany ID KIS-l 90 12.7 204 SSW of site, Alta Vista Road, Wolglestown at Dover Township Fire Dept. Bldg.

10 LIS-l 91 11.7 225 SW of site on West side of Route 74, Mt. Royal 10 MI5-1 92 11.9 237 WSW of site, West side of Route 74, in front of Earth Craf ts, Rossville i

FPF MI5-2 93 13.6 253 WSW of site on W side of Route 74, Lorew's orchard ID N15-8 94 13.2 276 W of site, Orchard Lane and Hortaler Road, Mt. Allen 10 N15-2 95 10.4 274 W of site, Lisburn Road and Main Street, Lisburn ID P15-1 12.2 300 WNW of site on Erford Road in front of Penn Harris Motel, Camp Hill AP Al,RW,lD.S Ql5-1 97 13.5 305 NW of site at West Fairview Substation ID Qi5-2 96 11.5 310 NW of site, Penn and Forster Streets, Harrisburg ID H15-1 99 11.2 330 NNW of site, Route 22 and Colonial Road, Colonial Park 5

A9-1 100 9.2 0

N of site off of Union Deposit Road FPL,5 A9-2 101 9.3 357 N of site on Union Deposit Road, W of Hoornerstown FPL El-3 102 0.7 90 E of site,100 m W of Peck Road and Zlon Road Intersection FPL(S E2-1 103 1.1 80 E of site on Zion Road 55 G2-2 104 1.3 133 SE of site on Engle Itoad :

Table 12 (Cont'd)

Rawlslon 4 RADIOLOGICAL ENVIROMENTAL MONITORING PROGR44 SMFLE LOCATION (Cont'd)

Senple Station Map Medium Code ph Distance Azimuth Description S

G3-1 105 2.9 al 131' SE of site on Governor's Stable Road Intersection with Keener Road FPL P3-1 106 2.6 293 WNW of site on Route 392 (Yocumtown Road)

AQF,M)P Indicator All locations where fish and plants are collected below the discharge are grouped together and referred to as " Indicator" (i.e., sectors 11 and geographically below)

All locations where fish and plants are collected above the discharge are AQF,AQP Control grouped together and referred to as " control" (i.e., sectors 12 and geogrwhically above)

AQS K2-2 107 1.1 197 SSW of site E of Shelley Island S

A3-3 108 2.5 354 N of site at Junction of Swatara Creek and Route 441 M

E2-2 109 1.1 93 E of site on Peck Road FPL,FPF Hi-2 110 0.9 150 SSE of site stand off of Rt. 441 S.

FPF DI-3 pll 0.5 65 ENE of site House next to Yinger's Greenhouse S

G2-3 l12 1.6 132 SE of site r. ear Conewago Cr.

IDENTIFICAT10N KEY ID = launersIon Dose (TU))

CR = Cryogenic air Sampie AQF = Flsh SW = Surface Water RW = Rain Water AQP = Aquatic Plants Al = Air lodine M = Milk (cow)

AOS = Aquatic Sediment M = Air Particulate MG = Milk (goat)

FPL = Green Leafy Vegetation or Vegetables S = Soll EW = Effluent Water FPF = Fruit

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. -61

,e 2

ATTACHMENT II Revision 3 to the TMI-1 Process Control Program (PCP).

The TMI-1 PCP, OP1104-28I, Revision 3 was issued July 31, 1984, which was during the period of this Report (July 1 through December 31,1984).

Operations memo 3210-84-0337 (attached) provides background as to the basis of the TMI-1 Process Control Program (PCP) and the input from W stinghouse e

Hittman who is under contract to GPU Nuclear to provide waste solidification services at TMI-1.

I The following is a list of the revisions by Section. A copy of the Program is included for your reference.

GENERAL All Procedure changes, other than those specified below, identified by " Change Bars" in the right margin were numbering or wording changes, and do not change the intent of the procedure.

j 1.0 SECTION 1.0 - PURPOSE i

a. ' Identifies that the Individual Waste Stream PCP's are a result from testing performed by Westinghouse-Hittman, included in Topical Report 4

4 STD-R-05-007 and meets the requirements of 10CFR61.56, Waste Characteristics.

2.0 SECTION 2.0 - COLLECTION AND ANALYSIS OF SAMPLES a.

Item 2.1.6 includes a new requirement that all chemicals used in the verification testing of a waste stream are identical to those used in full scale solidification.

b.

Item 2.2.2.2 has been changed to identify the information required on

{

the Test-Solidification Data Sheet, c.

Item 2.2.3.3 provides suggested time requirements to perform i

verification testing prior to performing full scale solidification.

3.0 SECTION 3.0 - TEST SOLIDIFICATION AND ACCEPTANCE CRITERIA

- a.

The note prior to 3.1 identifies the need to use sequential numbers i

when performing verification testing.

b.

The note prior to 3.2 has been added to notify Quality Controls of upcoming verification testing for monitoring purposes.

1 a

1-

,-w-

--,--n v---

v-

--.....,,-r

-m.-

l c.

Table 1 Solidification Ratios has been updated to identify the waste / binder ratios for the waste streams processed at TMI-1 for both

-unstable and stable waste forms.

d.

Items 3.2.7 and 3.2.9 incorporate the new steps for conducting verification testing for both unstable and stable waste forms.

e.

Items 3.5.1 and 3.5.2 provide upgraded parameters to be followed in the event verification testing results in an unacceptable product.

l 4.0 DATA SHEETS The Test Solidification Data Sheets and Calculation Sheets have been updated for the four (4) waste streams processed at TMI-1.

Data sheets are provided for both unstable and stable waste forms, except for concentrated waste which at this time is processed only as an unstable waste.

0181A. - _ _ -

Nuclear memorandum CHANGES TO THE PROCESS CONTROL Subject'.

Date:

August 7,1984 PROGRAM FOR RADI0 ACTIVE WASTE SOLIDIFICATION From'.

J. W. B0YER, RADWASTE OPERATIONS Three Mile Island Location:

ENGINEER III 3210-84-0337 File: NRC-LI To.

J. BURGESS, LICENSING ENGINEER 84-9200 i

Westinghouse-Hittman Nuclear Inc. is currently under contract with TMI-I to provide waste solidification services using cement.

Part of these services include Process Control Program (PCP) development to ensure consistency with regulatory changes.

With implementation of 10CFR61, Hittman has pursued the required testing of a variety of simulated radioactive waste streams in order to demonstrate compliance with the stability requirements of 10CFR61.56, " Waste Qualification" and the Branch Technical Position on Waste Forms.

Hittman has tested seventeen (17) waste streams commonly found at LWR. The fomulations were developed using Portland Type I Cement. To dcte, the test results of this qualification program are included in " Topical Report Cement Solidification Requirements of 10CFR61" (STD-R-05-007, Rev. O dated May 23, 1984).

The waste streams generated at TMI-I are bounded by those tested by Hittman. As a result, the fomulations converted into PCP's by Hittman for these waste streams have been included into the governing Process Control Program at TMI-I, OP 1104-28I.

OP 1104-28I Rev. 3, is currently applicable to the solidification of borated waste, oily waste, bead or powdered resin either as Class A unstable for borated wastes or Class A unstable, Class A stable, B and C for the other identified waste streams.

This program describes the methodology for determining the acceptable ratios of waste, binder and additives to ensure an acceptable waste product which meets the requirements of 10CFR61.56 and which is acceptable for burial.

Attached is a copy of the current approved revision of OP 1104-281.

The vertical lines in the right hand margin identify the most recent changes to the body of the procedure.

A0000e48 8 83

J. BURGESS August 7, 1984 3210-84-0337 These changes are a result of ICCFR61 implementation and based on the infomation supplied by Hittman resulting from their internal PCP adaptation of the Topical Report. These changes do not reduce the overall conformance of the solidified waste product to the existing criteria for solid waste.

W.

r

t. 8 9 JWB/dds cc:

W. T. Conaway, Radwaste Support Manager L. L. Ritter, Administrator II, Plant Operations CARIRS-TMI l

l l

k l

1 l

1104-28I Revision 3 07/31/84 IMPORTANT TO SAFETY ENVIRONMENTAL IMPACT RELATED COmOLLED COPY FOR USE IN UNITI ONLY THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 OPERATING PROCEDURE 1104-28I HITTMAN NUCLEAR AND DEVELOPMENTAL CORPORATION PROCESS CONTROL PROGRAM Incontainer Solidification CONTROL ROOM Table of Effective Pages WORKING COPY.

Page Revision Page Revision Revision Page Revision 1.0 3

26.0 3

2.0 3

27.0 3

3.0 3

28.0 3

4.0 3

29.0 3

5.0 3

30.0 3

6.0 3

31.0 3

7.0 3

32.0 3

8.0 3

33.0 3

i 9.0 3

34.0 3

10.0 3

35.0 3

11.0 3

36.0 3

12.0 3

37.0 3

s l':

i

!!:8 i

lMO OPb 15.0 3

16.0 3

18 3

N 19.0 3

!?:

i 648%

22.0 3

23.0 3

24.0 3

25.0 3

7 3/

Signature Date

[d N/44

~

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Signature Date Document ID: 0212T

,e--.

e

1104-28I Revision 3 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 OPERATING PROCEDURE 1104-28I HITTMAN NUCLEAR AND DEVELOPMENT CORPORATION PROCESS CONTROL PROGRAM Incontainer Solidification 1.0 PURPOSE The purpose of the Process Control Program (PCP) for incontainer solidi-fication is to provide a program which will assure a solidified product with no free 11guld prior to transportation for disposal and which meets the requirements of 10 CFR 51.56. Waste Characteristics.

The program consists of three major steps, which are:

a.

Procedures for collecting and analyzing samples; b.

Procedures for solidifying samples; c.

Criteria for process parameters for acceptance or rejection as solidified waste.

The PCP's for each waste steam included in this procedure are based on laboratory testing, the results of which are included in " Topical Report Cement Solidified Waste to meet the stability requirements of 10 CFR 61" j

(STD-R-05-007, Rev. 0) prepared by Hittman. These PCP's are valid for.

all liner types using electric or hydraulic mixing heads provided by Hittman.

2.0 COLLECTION AND ANALYSIS OF SAMPLES 2.1 General Requirements 2.1.1 As required by the Radiological Effluent Technical Specifications for PWR's and BWR's the PCP shall be used to verify the solidification of at least one representa-tive test specimen from at least every tenth batch of n

1.0

1104-28I Revision 3 l

l each type of wet radioactive waste (e.g., evaporator bottoms, boric acid solution, sodium sulfate solutions, resin and precoat sludge).

2.1.2 For the purpose of the PCP a batch is deflied as that quantity of waste required to fill a disposable liner to the waste level indicator.

2.1.3 If any test specimen falls to solidify, solidification of 4

the batch under test shall be suspended until such time i

as additional test specimens can be obtained, alternative I

solidification parameters can be det, ermined in accordance with the Process Control Program, and a subsequert test verifies solidification.

Solidification of the batch may then be resumed using the alternate solidification parameters determined.

2.1.4 If the initial test specimen from a batch of waste fails to verify solidification then representative test speci-mens shall be collected from each consecutive batch of the same type of waste until the three (3) consecutive initial test specimens demonstrate solidifications. The i

Process Control Program shtIl be modified as requires to l

assure solidification of subsequent batches of waste.

2.1.5 For high activity wastes, such as spent resin or used precoat, where handling of samples could result in personnel radiation exposures which are inconsistent with 4

the ALARA principle, representative non-radioactive samples will be tested.

These samples should be as close 2.0 f

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1104-28I Revision 3 i

to the actual waste and chemical properties as possible.

i Typical unexpended mixed bed resin shall be used to simulate the spent bead resin and the appropriate mix of anion to cation powdered resin shall be used to simulate used precoat.

i 2.1.6 All Chemicals used to condition or solidify waste or simulated waste in solidification tests shall be the l

actual chemicals used in full scale solidification.

2.2 Collection of Samples t

2.2.1 Radiological Protection j

2.2.1.1 Comply with applicable Radiation Work Permits.

2.2.1.2 Test samples which use actual waste shall be disposed of by placing in the disposal liner.

l 2.2.1.3 A Test Solidification Data Sheet will be maintained for each test sample solidified.

Each Data Sheet will I

contain pertinent information on the test sample and the i

liner numbers of wastes solidified based on each test sampie.

l

)

2.2.2 Test Solidification Data Sheet l

l The Test Solidification Data Sheet will contain pertinent i

information on the characteristics of the test sample solidified so as to verify solidification of subsequent batches of similar wastes without retesting.

l 2.2.2.1 a.

The test sample data for concentrated waste will include, but not necessarily be limited to, the type l

of waste solidified, major constituents, percent t

3.0

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

.=

1104-28I Revision 3 solids, pH, volume of sample, amount of oil in sample and the ratio of the sample volume to the final volume of the solidification product.

b.

The test sample data for spent resin and used precoat will include, but not necessarily be limited to, the type of waste solidified, volume of sample and ratio of sample volume to the final volume of the solidified product.

c.

The test sample data for other waste streams will include, but not necessarily be limited to, the type of waste solidified, volume of sample, amount of oil in sample, pH and the ratio of sample volume to the final volume of the solidified product.

2.2.2.2 The Test Solidification Data Sheet will include the Liner Number, Batch Volume, and Date Solidified, for each batch solidified based en simpic dc:cribcd.

2.2.3 Collection of Samples 2.2.3.1 Concentrated waste shall be kept heated or reheated to 130*F prior to testing.

bOTh$

if khe cobcebkr$ked wa$ke bad prevkous y be b neukra $

l 112ed prior to solidification to prevent boric acid precipitation the sample may be tested at ambient temperatures.

2.2.3.2 Two samples shall be taken for analysis. One sample shall be compatible with the standard size sample used for the radioactivity analysts and the second for the chemical analysis.

If the radioactivity levels are too 4.0 I

l

~ ~ ~~~~ ~ om so_

, m... e m

1104-28I Revision 3 4

high to permit full size samples to be taken then smaller samples shall be taken with the results corrected accordingly.

2.2.3.3 Samples should be drawn at least six hours prior to the planned waste solidification procedure to allow adequate time to complete the required testing and verification of solidification for Class A unstable waste. 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> should be allowed, if practical, for Class A stable, Class B and C wastes.

2.2.3.4 The tank containing the waste to be solidified should be j

mixed by recirculating the tank contents for at least one volume change prior to sampling to assure a representa-tive sample.

L i

2.2.3.5 If the contents of more than one tank are to be solidi-f 4

i fled in the same liner then representative samples of i

each tank should be drawn. These samoles should be of such size that when mixed together they form samples of standard size as prescribed in Section 2.2.3.2.

If the contents of a particular tank represents X percent of the total waste quantity to be solidified then the sample of that tank should be of such size to represent X percent of the composite samples.

i v

l l

e 5.0 i

1104-28I Revision 3 3.0 TEST SOLIDIFICATION AND ACCEPTANCE CRITERIA NOTE:

For the PCP test to be performed, use the Test Solidification Data Sheet for the waste stream and use the next sequential Sample No to identify the test.

3.1 Waste Conditioning 3.1.1 For concentrated waste (up to 14 weight percent) prior to solidification, the pH of the sample should be adjusted

'l to a range of 7.4 to 9.2 or greater than 11.5 with 50 wt.% sodium hydroxide (NaOH). The quantity of NaOH added shall be recorded.

NOTE:

If foaming is apparent during the solidification

)

testing the sample should be treated with an i

anti-foaming agent.

The quantity of anti-foaming agent required shall be recorded.

If a floating oil film is present in quantities greater than 1 percent by volume, the oil should be broken up with Maysol or other emulsification agent.

The quantity of emulsification agent added shall be recorded.

l 3.1.2 For bead or Dowdered resin, prior to solidification the

{

pH of the sample should be adjusted to a range of 5 to 8 if Metso Beads are used or to a range of 8 to 10 if they 1

l are not used. The quantity of NaOH used shall be recorded. This is required for Class A unstable waste l

only.

j 3.1.3 If waste oil is to be solidified, an emulsifier shall be l

added to pretreat the waste sample as follows:

a.

Allow one sample to stand undisturbed until the l

water /o11 interface is clearly discernible and E.0 p._-

1104-28I Revision 3 determine the percent by volume of the oil.

If this volume is greater than 40 percent add a sufficient quantity of concentrated waste to reduce the percent of oil by volume to less than 40 percent. Use the Test Solidification Data Sheet to determine the quantity of liquid to add. When the correct oil to water ratto is reached, measure and record the pH (pH paper may be used if a measurement cannot be made with a meter because of oil fouling).

b.

Prior to the test sample solidification, the waste oil is treated with a predetermined quantity of emulsifier.

For this application, Maysol 776 is used at a ratto of 1 part emulsifier to 5.1 parts oil by volume.

The emulsifier has a density of one, c.

After the emulsifier is thoroughly mixed into the sample, a quantity of Metso Beads the weight of which is twice the weight of the emulsifier used, is mixed in thoroughly unt'l the Metso Beads have completely dissolved.

i,3. 2 Test Solidification f:

NOTE:

ContacttheQualityControlsGroustoinformthemof the Test Solidification and if they care to witness the test.

3.2.1 Any sample to be solidtfled shall be pretreated as specified in Section 3.1.

I

[

A i

7.0

1104-28I Revision 3 3.2.2 Test solidification should be conducted using a 1000 ml.

disposal beaker or similar size container. Mixing should 4

be accomplished by stirring with a rigid stirrer untti a homogenous mixture is obtained, but in no case for less than two (2) minutes.

3.2.3 For the test solidification of resin, measure into a mixing vessel the appropriate ratios of waste and water based on the waste classification chosen. Measure out the required quantities of cement and Metso beads as shown in Table 1.

3.2.4 For the test solidification of used precoat, measure into a mixing vessel the appropriate ratios of waste and water based on the waste classification. Measure out the required quantities of cement and Metso beads as shown in Table 1.

3.2.5 For the test solidification of Concentrated Waste, measure into two mixing vessels 400 ml. of pH adjusted waste each. Measure cut the required quantitles of cement and Metso beads as shown in Table 1.

3.2.6 For the test solidification of Maste Oil and Concentrated Waste measure the appropriate of ratios of waste and Maysol No. 776 into a mixing vessel as shown in Table 1.

Stir mixture for no less than 5 minutes. Measure out the required quantitles of cement and Metso Beads.

8.0

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--,.-----en-,,._.e,-

e--,-

w

1104-28I Revision 3 SOLIDIFICATION RATIOS Table 1 CLASS A UNSTABLE Waste Water Cement Metso Maysol Ca(OH,)

Bead Resin 240 gm 90 ml 189 gm 19 gm Used Precoat 300 gm 90 ml 223 gm 22 gm Waste 011 and Conc. Haste 350 m1*

447.3 gm 51.8 gm 27.5 gm Conc. Haste Sample A 400 gm 440 gm 63 gm Sample B 400 gm 505 gm 84.2 gm CLASS A STABLE. 8 AND C t

Bead Resin 320 gm 235.3 ml 653.6 gm 18 gm Used Precoat 382 gm 151 ml 444 gm 10 gm Waste 011 and Conc. Waste 350 m1*

447.4 gm 51.8 gm 27.5 gm

• The 350 m1 is divided as follows: 210 ml C.W., 140 ml 011 l

9.0 a

r-y n

1104-28I Revisicn 3 NOTE:

Omit the following step if Metso Beads were pre.

vlously added.

3.2.7 For Class A unstable wastes mix the cement and additives together and slowly add this mixture to the test sample while it is being stirred.

3.2.8 After two (2) minutes of mixing and a homogeneous mixture is obtained allow the waste to stand for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.2.9 For Class A stable. Class B and C waste. mix the cement and additives together and slowly add this mixture to the test sample while it is being stirred.

If calcium hydroxide is being used, slowly add to the waste two (2) grams at a time. Mix for three (3) minutes between additions until all the additive is used.

Then add the cement and mix for one (1) additional minute.

3.2.10 Allow the sample to cure for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 120' 25'F.

NOTE:

If at any timi during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cure time the sample meets tne acceptance criteria, the liner solldtftcation may proceed.

3.3 Solidification Acceptability The following criteria define an acceptable solldtftcation process and process parameters.

3.3.1 The sample solidification is considered acceptable if there is not visual or drainable free water.

G 10.0

---

,,e

1104-281 Revisicn 3

/

3.3.2 The sample solidification is considered acceptable if

}

upon visual inspection the waste appears that it would r

hold its shape if removed from the beaker and it resists I

penetration by a rigid stick.

3.4 Solidification Unacceptability 3.4.1 If the waste fails any of the criteria set forth in Section 3.3 the solidification will be termed unacceptable and a new set of solidification parameters will need to be established under the procedures in Section 3.5.

1' 3.4.2 If the test solidification is unacceptable then the same test procedure must be followed on each subsequent batch i

of the same type of waste untti three consecutive test samples are solidified.

3.5 Alternate Solidification Parameters 3.5.1 If a test sample for Class A unstable waste fall to provide acceptable solidification of waste the following procedures should be followed.

1.

Mix equal volumes of dry cement and water tw ensure

(

that the problem if not a bad batch of cement.

2.

Add additional 50 wt.1 NaOH to raise the pH above 8 but less than 9.2 for borated wastes, i

3.

If the waste (other than waste oll) is only i

partially 9olidified, use lev:r wast: t: cement and i

4 Metso ratios. Using the recommended quantitles of i

1 I

cement and Metso Beads, reduce the waste sample to i

e 11.0 l

L

1104-28I Revisten 3 A

325 ml and continue reducing the sample volume by 25 ml. until the acceptability criteria of Section 3.3 are met.

4.

If the waste oil mixture is only partially solidified try using lower waste to cement ratios.

Reduce the quantity of waste by 25 ml. and the emulsifier by I ml., (This will result in a s;1ghtly higher concentration of emulsifier in the waste) and proceed with the test solidification. Continue with similar reductions until a satisfactory product is achieved.

3.5.2 If the test sample falls to provide acceptable solidification of waste following the actions of Section 3.5.1 the following sample analysis should be performed.

The waste should fall within the acceptable range.

l k'

f 9

12.0 I

= _

1104-28I j

Revisten 3 SAMPLE ANALYSIS For Concentrated Waste < 14 Weight Percent (24000 com as B) pH 7.4 to 9.2 or > 11.5 Percent Boric Acid i 14 ppe as Boron i 24000 Detergents No appreciable foaming during agitation 011 (floating)

< 1 percent by volume For 82ad and Used Precoat Resin i

pH

>5 Detergents No appreciable foaming during agitation 011 (floating)

< 1 percent by volume Waste Oil Mixed with Concentrated Waste pH

>5 Percent Boric Acid i 14 (prior to mixing) ppe as Boron i 24000 (prior to mixing) 011 1 40 percent by volume Detergents No appreciable foaming during agitation i

13.0

--+-

cr

-=

.-,,,w

.=

1104-28I Revision 3 1

i 3.5.3 For Class A stable. Class 8 and C waste test samples that fall to solidify, Contact Radwaste Operations Engineering for resolution.

t i

)

1 1

J t

i 14.0 i

r 1104-28I Revision 3 TEST SOLIDIFICATION DATA SHEE_T Class A Unstable Concentrated Waste Liner No.:

Sample No.:

Date:

I.

SAMPLE PREPARATION Sample Volume, m1.: Sample A Sample B (3.2.5) pH:

Volume NaOH solution used to adjust pH, ml Quantity of 011 percent:

Quantity of Emmuistfier, m1:

Quantity of Anti-Foam, m1:

,l Quantity of Cement Added:

Cement Ratio'

(#/ft' Waste)

Sample A gms Sample A l

Sample B gms Sample B Quantity of Additive Added:

Additive Ratio *

(#/ft' Waste)

Sample A gms Sample A Sample B gms Sample B Packaging Efficiency: Waste Volume / Solidified Waste Volume Sample A Sample B Prcduct Acceptable: Sample A Yes No (If no, refer to Section 3.5 and proceed as directed)

Sample B Yes No Additional batches solidified based on this sample solidification:

Liner Waste Liner Waste Liner Maste No.

Vol.

Date No.

Vol.

Date No.

Vol.

Date l

f-15.0 e,-

---,.em-m

1104-28I Revision 3 II. SAMPLE INSPECTION Test Solidifications Performed by:

Date Sample Contains "No Free Liquid":

Verified By Date FOOTNOTES:

1 The cement ratio is defined as the pounds of cement required to solidify one cubic foot of waste.

Ratios is this PCP yield cement ratios of 68.6 lbs/ft' and 78.8 lbs/ft' for samples A and B respectively.

2 The additive ratio is definsd as the pounds of additive required to solidify one cubic foot of waste.

Ratios in this PCP yield additive ratios of 9.8 lbs.ft' and 13.1 lbs/ft' for Samples A and B respectively.

t 16.0

-o

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w

1104-282 Revision 3 SOLIDIFICATION CALCULATION SHEET Waste Volume' ft':

(1) l Cement Ratio */ft*:

Sample A (2A)

Sample B (28)

Additive:

4 Additive Ratto. #/ft':

Sample A:

(3A)

Sample B:

(38) 8 Cement Quantity (1)' x (2A).

Ibs.

(4A)

(1)' x (2B) -

Ibs.

(48)

Additive Quantity

• i (1) x (3A) =

lbs.

(SA)

(1) x (38) -

Ibs.

(58)

FOOTNOTES:

1 The quantity of waste to be solidified in a single liner cannot exceed the maximum waste volume listed on the attached Solidification Data Tables.

2 4A and 5A define the minimum quantity of cement and additive respectively that must be mixed with the waste to assure solidification.

The recom-mended quantitles to use are represented by'4B and 58.

17.0

1104-28I Revision 3 SOLIDIFICATION DATA TABLES For Concentrated Waste NOTE:

Recommended Amount of Cement and Additives.

HN-100 HN-100 LVM Series 1 Series 2 Series 3 HN-1005 Series 3 Usable Liner Volume. (cu. ft.)

143 143 143 143 160.0 Max. Haste Vol. (cu. ft.)

77.6 75.7 97.1 93.3 108.6 Max. Solidified 114.3 111.5 143 137.4 160.0 Waste Vol. (cu. ft.)

Cement Added at ax. Haste Vol.

Weight (Ibs.)

6112.9 5964.5 7651.2 7350.4 8560.8 Volume (bags) 65 63.5 81.4 78.2 91.1 Anhydrous Sodlum Metasilicate Added at Max. Haste Vol.

Weight (Ibs.)

1016.2 991.6 1272 1222 1423.2 Volume (bags) 10.2 9.9 12.7 12.2 14.2 Max. Radiation Level 12 12 12 3

12 R/hr Contact

• 18.0 e

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-+

Y-

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s 1104-28I Revision 3 SOLIDIFICATION DATA TABLES For Concentrated Waste NOTE:

For the Minimum Amount of Cement and Additive.

HN-100 HN-100 LVM Series 1 Series 2 Series 3 HN-1005 Series 3 Usable Liner Volume, (cu. ft.)

143 143 143 143 160 Max. Haste Vol. (cu. ft.)

84.8 82.7 104.5 101.9 117 Max. Solidified Waste Vol. (cu. ft.)

116 113.1 143 139.4 160 Cement Added at Max. Haste Vol.

Weight (Ibs.)

5814.8 5673.5 7171.0 6991.8 8023.5 Volume (bags) 61.9 60.4 76.3 74.4 85.4 Anhydrous Sodium Metas111cate Added at Max. Waste Vol.

Weight (Ibs.)

830.7 810.5 1024.4 998.8 1146.2 Volume (bags) 8.3 8.1 10.2 10.0 14.2 Max. Radiation Level 12 12 12 3

12 R/hr Contact l

19.0

1104-281 Revision 3 1

CLASS A UNSTABLE AND STABLE. CLASS B OR C TEST SOLIDIFICATION DATA SHEET FOR WASTE OIL Liner No.:

Sample No.:

Date:

I.

SAMPLE PREPARATION (3.2.6)

Sample Volume, ml.:

(1) 011 Volume, m1:

(2)

Percent Oil by Volume:

(3)

Quantity of Water Removed or Added to Obtain 40% Oil by Volume:

(4) i pH:

(5)

Quantity of Emulsifier Added, m1:

(6)

~

Grams of Portland Type I Cement:

(7)

Grams of Anhydrous Sodium Metasilicate (ASMS):

(8)

Additional batches solidiffed based on this sample solidification:

Liner Maste Liner Naste Liner Maste No.

Vol.

Date No.

Vol.

Date No.

Vol.

Date II. SAMPLE INSPECTION Test So11difications Performed by:

Date Sample cured for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' at n20* i *F:

S Verified By Date Sample Contains "No Free Liquid":

Verified By Date 20.0

1104-281 Revision 3 III. PARAMETERS FOR FULL SCALE SOLIDIFICATION Quantity of Maysol 776:

(6) ml Maysol 776 (9) from above x 0.0214 = gallons Emulsifier per ft' waste (including water).

Quantity of Portland Type 1 Cement:

(7)

(10) gms cement from above x 0.1784 = lbs cement per f t' waste (including water).

Quantity of Anhydrous Sodium Metas111cate:

(8)

(11) gms ASMS from above x 0.1784 =

lbs. ASMS per ft' waste (including water).

FOOTNOTES:

1 If the sample is quallfled in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cure time, note the total hours cured. Class A unstable wastes may be cured at room tempera-ture for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

I 21.0

1104-287 Revision 3 CLASS A STABLE AND UNSTABLE, CLASS B OR C WASTE SOLIDIFICATION CALCULATIONS SHEET Volume of waste' (including water) to be solidified', ft':

(1)

Emulsifier Ratto, gallons /ft':

(Item 9, Part III)

(2)

Cement Ratio, lbs/f t':

(Item lo, Part III)

(3)

ASMS Ratto, lbs/ft':

(Item 11, Part III)

(4)

Quantity of Emulsifier to be added:

gallons (5)

(1) x (2)

Haste Volume (ft')

gallons /ft' Quantity of Portland Type I Cement to be added:

(1) x (3) -

ids (6)

Haste Volume (ft')

Ibs/ft' Quantity of ASMS to be added:

(1) x (4) =

lbs (7)

Haste Volume (ft')

lbs/ft' FOOTNOTES:

1 For the purpose of this PCP, the volume of waste is considered as the volume of oil plus the volume of water necessary for solidification.

2 The volume of waste to be solidified cannot exceed the maximum volumes listed en the Class A Stable and Unstable, Class B and C Solidification Data Sheets.

)

i 22.0

1104-281 Revision 3 SOLIDIFICATION DATA TABLES FOR WASTE OIL CLASS A UNSTABLE AND STABLE.

CLASS B AND C HH-100 Series 1 Series 2 Series 3 LVM 1005 Usable Liner Volume, (ft')

143 143 143 160 143 Max. Waste Volume (011 and water), ft' 86.4 84.3 101.0 113.0 101.0 Max. Solidified Volume, ft' 122.3 119.4 143.0 160.0 143.0 Maysol 776 Added at Maximum Waste Volume (gallons) 50.8 49.6 59.4 66.5 59.4 Portland Type I Cement Added at Maximum Waste Volume 1bs 6891.8 6724.4 8056.5 9014.2 8056.5 94 lb bags 73.3 71.5 85.7 95.9 85.7 ASMS Added at Maximum Waste Volume Ibs 794.6 775.2 928.8 1039.2 928.8 100 lb bags 8.0 7.8

- 9.3 10.4 9.3 Maximum Rad Level R/hr Contact 12 12 12 12 3

(1)

S = HN-600 Stackable G - HN-600 Grappable S&G = HN-600 Stackable-Grappable R = HN-600 Regular l

23.0 mw Mu 4 WD 6 O

1104-28I Revision 3 CLASS A TEST SOLIDIFICATION SHEET for used Precoat Batch No.:

Sample No.:

Date:

I.

SAMPLE PREPARATION (3.2.4)

Sampie Voluira, ir.1. :

(1) pH':

Volume NaOH solution used to adjust pH, ml (2)

Quantity of 011 %:

(3)

Quantity of Emmulsifier, (20% by volume of oil) ml':

(4)

Quantity of Anti-Foaming agent, ml:

(5)

Quantity of Cement Added:

Cement Rt.tio' (#/ft' haste)

Sample gms Sample (6)

Quantity of Additive Added:

Additive Ratio' (#/ft' Waste)

Sample gas Sample (7)

Product Acceptable: Sample Yes No (If no, refer to Section 3.5 and proceed as directed)

Additional batches solidified based on this sample solidification:

Liner Waste Liner Waste Liner Waste No.

Vol.

Date No.

Vol.

Date No.

Vol.

Date II. SAMPLE INSPECTION Test Solidification Performed by:

Date Sample Contains "No Free Liquid":

Verified By Date 24.0

1104-28I Revision 3 FOOTNOTES 1

If pH adjust is reautred, note chemical used, quantity used and pH after adjustment.

2 The cement-to-waste ratto is 48.7 pounds of cement per cubic foot of settled powdered resin.

If a quantity of cement is used for the test solidification that is different from the quantity listed, multiply the gms by 0.218 to obtain the correct pounds of cement per cubic foot of settled powdered resin.

3 The additive-to-waste ratio if 4.9 pounds additive per cubic foot of settled powdered resin.

If alternate additive ratios are used see the multiplier in Note 2 to obtain the correct pounds of additive per cubic foot of powdered resin.

4 The following table shows the minimum mix ratio for a 390 gms sample size of 5 to 27 dry weight percent powdered resin:

Minimum Slurry Concentration, Cement Additive Cement Adottive Dry Weight Percent (gms)

(gms)

(1b/ft')

(Ib/ft')

5 - 12 429 42.4 93.5 9.4 13 - 21 351 35.1 76.6 7.7 22 - 27 234 23.4 51.0 5.1 25.0 I

1104-28I Revision 3 CLASS A WASTE SOLIDIFICATION CALCULATION SHEET for Used Precoat Maste Volume to be Solidified':

(1)

Cement Ratto, #/ft': Sample (2)

Item 6 - Data Sheet Additive Ratio, #/ft': Sample (3)

Item 7 - Data Sheet Cement Quantity *

(1) x (2) =

lbs.

(6)

Haste Volume Ib/ft' Additive Quantity

• l (1) x (3).

Ibs.

(7)

Haste Volume Ib/ft' Quantity of Water to be added:

(1) x

=

gallons (8)

Waste Volume gal /ft' Divide the Quantity of Water to be added (8) by the supply flowrate (9) to determine how long water should be pumped to the disposal liner or use a preseasured quantity of water.

(8) +

gal / min (9) -

minutes (10)

Quantitles of additional additives that must be added to the liner are found by multiplying the volume of the additive used in the test solidt-fication, in m1, by 0.0249 and then by the volume of waste to be solidi-fled. Volumes of addittor.al additives are taken from items 2, 4, and 5 on Data Sheet.

ml x 0.0249 Xx (1) -

gallons (11)

Item 2, 4, or 5-FOOTNOTES:

1 The quantity of waste to be solidified in a single liner can not exceed the maximum waste volume listed on the Class A Waste Solidification Data Table.

2 6 and 7 define the recommended quantity of cement and additive respec-tively that must be mixed with the waste to assure solidification.

1 26.0 9

9y-3-

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-.---t---w r.

e w

--e e

1104-28I Revision 3 3

For decanted powdered resin, add 2.02 gallons of water per cubic foot of settled waste and 2.36 gallons of water per cubic foot of dewatered powdered resin.

3 4

Reduce the quantity of waste in the liner by 1 ft for every 10 gallons of additional additive.

N t

e i

27.0

1104-28I Revision 3 CLASS A WASTE SOLIDIFICATION DATA TABLE for Used Precoat HN-600' HN-200 Usable Liner Volume, ft' 65 60 Max. Solidified Waste Vol. ft' 65 60 Max. De=atered or DecanteJ Waste Vol., f t' 42.4' 39.2' Cement added at Max. Haste Vol.:

pounds 2063 1910 1 ft' bags 22 20 1/4 Water Added at Hax Waste Volume: gallons

.Dewatered 100' 93 Decanted 86 79 Anhydrous Sodium Metasilicate Added at Max. Haste Vol.: Pounds 206 191 100 bags 2

2 Max. Radiation Level R/hr Contact of Liner 100 800 FOOTNOTES:

1 Values shown for regular and grappatie. Multiply all values by 0.922 for stackable or 0.893 for the grappable!stackable liners. See Footnote 4.

2 Based on 18" maximum depth of filter studge in the liner, 16-3/4 inches in the stackable or grappable/stackable.

3 Based on 31 1/2" maximum depth of filter sludge in the liner.

4 For dewatered powdered resin, use 100 gallons of additional water for all sizes of HN-600 liners.

i 1

28.0

1104-28I Revision 3 CLASS B AND C TEST SOLIDIFICATION DATA SHEET for Used Precoat Liner No.:

Sample No.:

Date:

1.

SAMPLE PREPARATION f

Sample Volume, at:

(1)

Initial pH:

Quantity of 011', %

2 Grams Ca(OH): to raise pH to > 11.0, gm:

(2)

Grams Portland Type I Cement added, gm.

(3)

II. SAMPLE INSPECTION 1

Test Solidification Performed by:

Date Sample cured for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' at 120* =5'F:

verified By Date Sample Contains "No Free Liquid":

Verified By Date Sample is " Free Standing Monolith":

Verified By Date III. PARAMETERS FOR FULL SCALE SOLIDIFICATION:

Quantity of (Ca OH)::

(2) gm Ca(OH): from above (4) x 0.172 =

lb Ca(OH): per ft' decanted /dewaterec powdered resin.

Quantity of Cement:

(3) gm Cement from above (5) x 0.172 -

Ib Portland Type I Cement per ft' decanted /dewatered powdered resin.

FOOTNOTES 1

Must be 11% of waste volume.

2 If the sample is qualified in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cure time note the total hours cured.

29.0 4

v s

w

1104-28I Revision 3 CLASS B AND C WASTE SOLIDIFICATION CALCULATION SHEET for Used Precoat Haste Volume to be Solidified':

(1)

Ca(OH)2 Ratio: #/ft*:

(Item, 4 Data Sheet)

(2)

Cement Ratto; #/ft':

(Item 5. Data Sheet)

(3)

Quantity of Water to be Added:

(1) x

• gal /ft' -

gallons (4)

Quantity of Calcium Hydroxide (Ca(OH)2) to be added:

(1) x (2) -

lbs (5)

Haste Volume Ib/ft' Quantity of Cement (Portland Type I) to be added:

(1) x (3) -

Ibs (6)

Waste Volume Ib/ft' 1

The volume of waste, either d'matered or decanted settled solids, to be solidified in a liner cannot exceed the maximum settled waste volume listed on the Class B Waste Solidification Data Table.

2 For decanted powdered resin, add 2.75 gallons of water per cubic foot of settled waste, and 3.12 gallons of water per cubic foot of dewatered waste.

\\

s 30.0

1104-28I l

Revision 3 CLASS B AND C WASTE SOLIDIFICATION DATA TABLE for Used Precoat HN-600' HN-200 1

Usable Liner Volune, ft' 65 60 Max. Solidified Waste Vol. ft' 65 60 Max. Settled Waste Vol., ft' 36.5 33.7' 8

Water Added at Max.

Haste Volume:

gallons Dewatered 114' 105 Decanted 100 93 Ca(OH) Added 5

5 i

Cement Added at Max.

Haste Vol.: Pounds 2787 2574 1 ft' bags 29.7 27.4 Max. Radiation Level R/hr Contact of Liner 100 800 FOOTNOTES:

1 Values shown for plain and grappable liner. Multiply all values by 0.922 for stackable or 0.893 for the stackable/grappable liners. See Footnote 4.

l 2

Based on 15 inches of settled powdered resin in the liner, 14 inches for stackable and stackable/grappable.

)

3 Based on 28 1/2 inches of settled powdered resin in the liner.

4 For dewatered powdered resin use 114 gallons of additional water for all sizes of HN-600 liners.

5 To be calculated for each solidification.

31.0 m

w-,-

1104-28I Revision 3 l

CLASS A UNSTABLE TEST SOLIDIFICATION DATA SHEET for Bead Resin Liner No.:

Sample No.:

Date:

I.

SAMPLE PREPARATION (3.2.3)

Sample Volume, al:

(1)

Sample pH:

Volume NaOH solution used to adjust pH, ml:

(2)

Quantity of 011 %:

(3)

Quantity of emulsifier (20% by volume of oil), el:

(4)

Quantity of anti-foaming agent, at:

(5)

Temperature at Solidification *F:

Quantity of Cement Added:

Cement Radio' (Ibs/ft' Waste)

Sample gms Sample (6)

Quantity of Additive Added:

Additive Ratio * (lbs/ft* Waste)

Sample gas Sample (7)

Product Acceptable: Sample A Yes No Additional batches solidified based on this sample solidification:

Liner Waste Liner Waste Liner Maste No.

Vol.

Date No.

Vol.

Date No.

Vol.

Date II. SAMPLE INSPECTION Test Solidifications Performed by:

Date Sample Contains "No Free Liquid":

Vertfled By Date 32.0

=

r r-

-+

1104-28I Revision 3 FOOTN0TES:

1 The cement. ratio is defined as the pounds of cement required to solidify one cubic foot of dewatered waste.

The ratio in this PCP is 39.3 lbs/ft'.

2 The additive ratio is defined as the pcunds of additive required to solidify one cubic foot of dewatered waste. The ratio in this PCP is 3.93 lbs/ft'.

t I

i 6

33.0

l :

1104-28I Revision 3 CLASS A UNSTABLE SOLIDIFICATION CALCULATION SHEET for Bead Resin Waste Volume', ft':

(1)

Cement Ratto; lbs/ft':

Sample (2)

Item 6 Data Sheet Additive:

Additive Ratto, lbs/ft': Sample (3)

Item 7 Data Sheet Cement Quantity *

(1) x (2) =

lbs.

(4)

Waste Volume Additive Quantity *

(1) x (3) =

l b's.

(5)

Haste Volume Quantity of Mater to be Added in Gallons:

1 (1) x 2.25 -

gallons

'. 6 )

Haste Volume Quantitles of additional additives that must be added to the liner are found by multiplying the volume of the additive used in the test solidification, in al, by 0.0249 and then by the volume of waste to be solidified. Volumes of additional additives are taken from. items 2, 4, and 5 on the Data Sheet.

ml x 0.0249 x (1) =

gallons

• Item 2, 4, or 5 Data Sheet FOOTNOTES:

1 The quantity of dewatered waste to solidified in a single liner cannot exceed the maximum waste volume listed on the attached Solidification Data Tables.

2 (4) and (5) define the recommended quantity of cement and additive respectively that must be mixed with the waste to assure solidification.

3 Reduce the quantity of water in the liner by 1 ft' for every 10 gallons of additional additives.

l 34.0 w

v-w

1104-28I Revtsien 3 SOLIDIFICATION DATA TABLES SEAD RE5!N ggII:

For the Recensensed Amount of Coment and Additive.

MN-100 mm.600=

tarten 1 Series 2 Series 3 1121 tiL2AA 1

1 1

R Usatte Liner 143.0 143.0 143.0 143.0 59.5 59.6 64.6 57.7 64.6 j

volume (cu. ft.)

1 Man. Dewatered Weste Vol. (cu. ft.)

105.0 102.3 110.0 110.0 48.3 48.3 52.4 46.8 52.4 Mas. Solidified Weste Vol. (cu. ft.)

129.5 126.2 143.0 143.0 59.5 59.6 64.6 57.7 64.6 Coment Added at Max. Weste Vol.

height (1bs.)

4126.1 4020.8 4320.7 4320.7 1896.6 1899.6 2059.0 1839.0 2059.0 Volume (begs) 43.8 42.8 46.0 46.0 20.2 20.2 21.9 19.6 21.9 Anhydrous Sodium Metastlicate Added at Man. Weste Vol.

Watcht (1bs.)

412.6 402.1 432.1 432.1 189.6 190.0 205.9 183.9 205.9 i

volume (begs) 4.1 4.0 4.3 4.3 1.9 1.9 2.1 1.8 2.1 Water added te Max.

Weste Vol. (Gallons) 236.2 130.2 247.3 247.3 108.6 108.8 117.9 105.3 117.9 Mas. Radiatten Level R/hr Contact 12 12 12 3

800 ISO 100 100 100

• 5

. NN-600 Stackable G

e NN-600 Grappette 5+G = MN-600 Stackable/Grappable R

e MM-600 Regular 35.0

)

l i

)

w w

~ ** t 1104-281 Revision 3 CLASS A STABLE, CLASS B AND C TEST SOLIDIFICATION DATA SHEET g ',

for Bead Resin Liner No.:

Sample No.:

Date:

I.

SAMPLE PREPARATION Sample Volume, al:

(1)

Initial pH:

Quantity of 011 1:

Grams Ca(OH)2 to raise pH to >l1.5, gm:

(2)

Grams Portland Type I Cement added, gm:

(3)

Additional batches solidified based on this sample solidification:

Liner Waste Liner Waste Liner Waste No.

Vol.

Date No.

Vol.

Date No.

Vol.

Date II. SAMPLE INSPECTION Test Solidification Performed by:

Verified By Date Sample cured for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• at 120* 25'F:

Verified By Date Sample Contains "No Free Liquid":

Verified By Date III. PARAMETERS FOR FULL SCALE SOLIDIFICATION Quantity of Ca(OH) :

(2) from above x per ft*gm Ca(OH):

0.156 -

Ib Ca(OH) dewatered resin.

(4)

Quantity of Cement:

(3)

Ib Cement per ft'gs cement from above x 0.156 -

dewatered resin.

(5) 36.0

• 1104-28I Revision 3

)

FOOTNOTES:

I Must be'11% of waste volume.

2 If the sample is qualified in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cure time, note the total hours cured.

t I

4 4

d l

e 37.0 Id e-. e e m.

1104-281

+

Revision 3 CLASS A STABLE, CLASS B AND C WASTE SOLIDIFICATION CALCULATION SHEET for Bead Resin Volume dewatered resin to be solidified', ft*:

(1)

Ca(OH): Ratio, lbs/ft' Item 4 Data Sheet (2)

Cement Ratio lbs/ft*

Item 5 Data Sheet (3)

Quantity of Water to be Added:

~

Waste Volume (ft')

4 Quantity of Calcium Hydroxide (Ca(OH) ) to be added:

(1) x (2) -

Ibs.

(5)

~

Waste Volume (ft')

Ib/ft' Quantity of Cement (Portland Type I) to be added:

(1) x (3) =

lbs.

(6)

Waste Volume (ft')

lb/ft' 1

The volume of dewatered bead resin to be solidified cannot exceed the maximum waste volume listed on the Class A Stable, Class B and C Test Solidification Data Sheet for Bead Resin.

38.0

a g

a **

s 1104-28I Revision 3 CLAtt a sfaalf. CLA11 R AND f Wa1TE SOLIDIFICATIDN DATA TABLES for head Resin 8

NN-100 NN-600

inrias 1 1 arias 2 tariet 1 g

g i

1

$+G R

Usable Liner 143.0 143.0 143.0 143.0 59.5 59.6 64.6 57.7 64.6 V31ume (cu. f t.)

Mau. Dewatered 61.5

$9.9 77.9 77.9 32.4 32.5 35.2 31.4 35.2 Weste Volume (cu. ft.)

Man. Solidtfted 112.8 109.9 143 143 59.5 59.6 64.6 57.7 64.6 West e volume (cu. f t.)

C ((N): added at Mas, Weste volwme888 Wetpht (1bs.)

172 168 218 218 91 91 99 88 99 Volume (bags) 3.4 3.4 4.4 4.4 1.8 1.8 2.8 1.8 2.0 Portland Type !

Cannnt Adeed ct Ham. Weste vol.s s We19ht (1bs.)

6273 6110 7945.8 7945.8 3304.8 3315 3590.4 1202.8 3590.4 Volume (bags) 66.7 65.0 84.5 84.5 35.2 35.3 28.2 34.1 38.2 Watur Aseed to 271 264 343 343 143 i 143 155 138 155 Mas. Weste Vol. (Gallons)

Man. Red. Level 12 12 12 3

800 100 100 100 100 R/h

• Contact (1) 5 = NN-600 stackable Ge NN-600 Grappetle 5+G e NN-600 5tackable - Grappetle R = NN-600 Regular e

39.8

1 UNITED STATES 8

h NUCLEAR REGULATORY COMMISSION b',

{

j, W ASHINGTON. D. C. 20555 g

gg VM/

April 30, 1984 Lh f_.? H- [(st - 3/5 S ~

TMI-1 TO ALL OPERATING REACTORS AND APPLICANTS FOR OPERATING' LICENSES otscribucion no M 92(o l wa LttfM S2.ll 3 ( 55 Gentlemen:

Asstansa c.: 64M.

SUBJECT:

COMPLIANCE WITH 10 CFR PART 61 AND IMPLEMENTATION OF THE (hejd u RADIOLOGICAL' EFFLUENT TECHNICAL SPECIFICATIONS (RETS) AND oo. 3 c. 7 f f-ry ATTENDANT PROCESS CONTROL PROGRAM (PCP) (GENERIC LETTER 84-12)

This letter is to inform you that the waste manifest provisions of 10 CFR In*-e.esip.

20.311 became effective on December 27, 1983.

The manifest system is closely g

Huk111-Trl.122 /

related to Certain requirements of 10 CFR Part 61 that place new requirements

1. Wilson-Parsip on Classification and acceptable forms for low-level radioactive wastes being

$*[* e#N["26

[-

shipped from commercial nuclear power plants to commercial disposal facilities.

x

,The NRC staff has been made aware of the fact that neither the states nor the cettes-ret.tss rinfrock-rarste.

di I

sposal facility operators currently have sufficient resources to assure that Cl*"81- " l

!all inccming low-level radioactive waste is in compliance with these new Un*n*#$'Na$. /

regulations, reaseetbl9 Eastnes-Parsip.

I isions af Newton-Training g

t,a cey-Pa rsip.

5y rna-Admin.

troffst-Trl.196 During the development of Part 61, the NRC staff determined that H21**a-Tel L'5 compliance with the radioactive waste form requirements of Part 61 and the

("',dd'o*l88 certification requirements of 10 CFR 20.311 could be achieved by the develop-

,1a,,

fess-sev.alds.

ment and use of a Process Control Program (PCP) as an attendant part of the

/

cronsberase brst licensee's Radiological Effluent Technical Specifications (RETS).

This h>'ef.Yr'$;.

approach was determined to be acceptable by the responsible state regulatory s

agencies that license the disposal sites.,lieM9pessumpassenhver, thtt

cot.-sev.atas.

4 too re -P a rsi p.

I x

A fM.M'WY6g hgg 3 p(%

S;s'*1 l.L

• • ai=Mm4-==*==a=**==* -

edall-Admin.

As an interim maasure, the responsible state regulatory agencies and the cA m s x

x gocc-cherry util x x

disposal site operators have agreed to continue to accept nuclear power plant

[m,,

low-level radioactive wastes based upon the NRC staff's assurance tett W" M,

/

teuerd demonstmtiaWWMuttrcomp1Tandh esbanumimagesicamartts afdart41 endfart.2N hewedny I

%.ss.w

.n

- m w m anamamLamaUsudsumeendAISE3munik.ths:seenudanH6 Sea The NRC staff wil1 assume a good-faith effort on the part of these licensees to modify in a timely fashion the PCPs to accommodate all new and applicable Part 61 and Part 20 requirements. Maanna.orepared ta assist, wherricoquested...those li amamma a=hich.prasantly.hatte.esproved PCPs to assare tase$'4 hey are tifigrided t

f themoedheenau reettirements c6Jart 64; however, the NRC staff cannot offer evious N.G.gutyis uc.

the same type of assurances for those operating plants which do not possess rg; currently approved RETS and PCPs.

Prcept action may be necessary if radio-f rst. o$rr. 5 -4 f-8Y active waste shipments from these plants are to continue without interruption, l

l 8405010084

F

.e

" The NRC staff will make every effort to avoid any interruption of low-level radioactive waste shipments by its licensees. We are prepared to expedite the implementation of NRC approved RETS and PCPs for 'all licensees who request assistance.

If you have any questions concerning this subject, please contact either W. Gammill or F. Congel via your Project Manager.

f G. Eisenhut, Directorluteatf li.

. i ^

DNrr Division of'.icensing Office of Nuclear Reactor Regulation l

L l

't