ML20059E632

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Semiannual Effluent Release Rept for Jan-June 1990
ML20059E632
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 06/30/1990
From: Dubiel R
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20059E608 List:
References
NUDOCS 9009100258
Download: ML20059E632 (53)


Text

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PHILADELPH1A ELECTRIC COMPANY LIMERICK GENERATING STATION I

UNITS NO. 1 AND 2

-DOCKET NO. 50-352 (Unit 1)

DOCKET NO. 50-353 (Unit 2) 1 SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 12 JANUARY 1, 1990 THROUGH JUNE 30, 1990 9

Submitted to The United States Nuclear Regulatory Commission Pursuant to racility Operating License NPF-39 (Unit 1) and NPT-85 (Unit 2)

Preparation Directed by:

s G. M.

Leitch, Vice President i

Limerick Generating Station i

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l A

R. W. Dubiel, Services Superintendent L

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l TABLE OP CONTENTS t

i

'I.

Introduction i

11.

Tables l

A.

Summary of Radioactive G'.csous Effluents B.

Summary of Radioactive Liquid Effluents C.

Solid Waste Disposition Report l

t III.

Attachments e

A.

Supplemental Information - Assumptions Used in Report Generation B.

Residual Heat Removal (RHR) Service' Water Radiation Monitor Out of to Service C.

Process Control Program, Revision 9 i

(Submitted Under Separate Cover)

D.

Offsite Dose Calculations Manual, Revision 8 l

E.

Change in Environmental Monitoring Locations i

4 I

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+

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I.-

INTRODUCTION This submittal complies with the format described in f

Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water t

Cooled Nuclear Power Plants", Revision 1, June, 1974.

The following information is included as Tables to this report A summary of the gaseous and liquid effluent releases for the report period.

Where "0.00E+00" is used, it denotes the less than detectable level for the given isotope.

Composite particulate air samples, counted for beta emitters (eg. Sr-89, Sr-90), are submitted to an offsite vendor laboratory for analysis.

Since data for the second quarter particulate air samples were not available at the time this report was prepared, it will be necessary to submit an addendum in the future if second quarter particulate air samples results are reported >LLD.

Since Limerick Technical Specification limits for liquid and gaseous effluent releases are stated in terms of quarterly and annual offsite doses, " percent technical specification limit" is given as 0.00E+00.

A summary of solid waste dispositioned during the report period, to includes total activity shipped by waste type and an estimate of the error in the reported totals; the estimated composition of each type of waste by isotope; the number of shipments, mode of transportation, destination, type of container, total container volume, and solidification agent.

An explanation of Residual Heat Removal (RHR) Service Water Radiation Monitor Inoperability.

A copy of the Process Control Program revision 9 and ODCM revislon 8 and an explanation for all changes which were implemented during the report period; An explanation of changes to Environmentti Monitoring Locations.

l i

N II.

TABLES-i i

A.

SUMMARY

OF RADIOACTIVE GASEOUS EFFLUENTS January 1, 1990 to June 30, 1990 G

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JATE: )b/23/90 09:33

r-LJE NY A
iO WAS TE DISPOSAL Rc?CRT 3A5fsVS iFFLUc4TS -

0

. _ _ _ _..... _ _ _.. _.....'J M 4 A f ! O N OF ALc PiLEASi$

i U.41 T S :

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UwCTt s
25T.

TOTAL:

I 1

2

:RROR, 4:

i 4

F.5 510h ANC A C1;V AT.31 sASE5 1.

13fAL RIL:A5t CI

0.363I+01 :.0.776!+01 : 0 453E+02 :

2.

AVERAGE R:L L A 3E

':UCI/SEC: 0.4o72+00 : 0.9370+00 :

RATi c0R $5RIa0 1

3.

PERCd4T U TECMA ;AL:

4

0 010E+00 :
0. 0 0 0 E + '> 0 :

l SPECIFICAll)h LIMil :

3 IODINd5 1.

TOTAL I Ju14 5-131 CI

0.1)*E-04 : J.v00!+30 : 0.4 53E+ 02 :

l J.

aVERAsl F,

LiASt JCI/IEC: 0.250:-05 : 0.000d+00 :

1.:..__. Raid FOR PtRIJL

3. PIRQiNT Cf TECHNICAL:

4 0.030t+00 : 0.0004+00 :

Svt.IFICATIJN LIM;T :

,;. PARTICULATL5 i

li

1. PARTICULAfia AITH CI
0.b*7C-04 : 0.000E+00 : 0.453E+02 :

' _t HALF LIVL5 >e DAY 3

2. AVERAGE RiL 3 A$t
'JC I / s E C : 0.7J3C-05 : 0.0005+00 :

RAli FJE PER100 1.__.............__-__...__.......__....._______._._______

,a 3.

PERCENT 06 TeCNNIC-L:

0.000;+00 : 0.000i+00 :

a

!....._' P E C IF I C A T I O N L I PI T l:

4.

GROSS ALPIA CI

0. 0 J 0 i+ 10 : 0.0J0E+JO :

R A 010 AC T 1 H T Y iJ. TnITIUM

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1.

TsTAL RiL;A CI

0.000d+00 : 0.000d+00 : 0.453E+02 :

l....... _ _ _.......S E l i' 2.

AVE 4AsE R:L E ASE

UCI/5EC: 0.0J0s+00 : 0.000E+00 :

AATi 70R 35RIOD l...............______... ___ ______...___.........____...

J.

PERC2NT Cf TECHNICAL:

1

0.000;+00 a

>PECIFIC ATION LINIT :

' '0.000*+00 :

i 1..___.......__. __. __...___....._...__......._...____. _

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SITE: LIMERICK Uh17: vi

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. :lC4Ti.$T1CK 504T'NJou$ A0'J!

ATCP 'i t J C o..__..______............___................_______........__.___.....

N J C '. I J 6 5

UNIT 5 :

.O h f i a

.LARits au'RT;t WM R T E R RELIA 5*0 1

4 1

2 r

- 16 F13 31 Jk G ASi:,

A441 01

'J. 0 J C : + 0 0 : 0.~0)0d+00 : 0 000!+)0.: 0.000E+00 r

K483M CI

0.0301+30 :
0. 0 ') C ; + 0 0 : 0.000?+00 : 0.000!+00 :

KRISM C1

1.000:,JC.: 0 0J0i+00 : 0.000;+JO : 0.0002+00 :

KR85 C1

u.eJJC+0C : s.JJu:+JJ : s.030!+JO : 0.134E-02 :

K487 C1

0.030.*30 : J.000i+JO : C.000i+00 : 0.000E+00 :

___...............__.........a....___.....

1' Ka8d C1

2.000d+;;

0.03vs+0C : 0.000i+00 : 0.000i+00 :

KRB9 C1

C.0J0i+J0 : 0.0>0C+30 : C.000i+10 : 0.000E+00 :

FM 9 3 C;

C.0JC;+

0.000i+00 2 0.000i+00 :
0. 0 0( d+ 00 :

.__..__...........______.____.'JO.........................______.._____

Xi1313 CI

U.000:+.'0 ; C.0J00+JO : 0.000i+10 : 0.0u0i+00 :

AC133M C1

0.0J0i+JO : 0.000i+00 : U.000i*u0 : 0.000E+00 :

L I~~x$533~~~~~i'~5I~~~i~0!3235I30 I"0I636?i03'I'0I3035I30 I~3!303EID3~i

~

Xi1353 CI

0.000i+30 : 0.0000+00 : 0.000!+00 : 0.000d+00 :

X d135 C;

.6565+0c : 0.7175+01 : 0.0002+00': 0.433E-03 :

x01J7 CI

0.000d+)0 : 0.0002+00 0.000E+90 : 0.000E+00 :

i Xi136 CI

0.0004+JG : 0.CJ0:+06 : 0.000!+3C : 0.000E+00,:

TJTAL FCR :

PERIOJ cl

0.bs6E+0s : 0.747%+01 : 0.000E+00 : 0.1)SE-02 :

(A2JV:)

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JNIT: J1 J5fA C048

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.......'4 7 an0 m:$ f t 015d]5AL 44006T

FdLVi M$hJU5 EFFLat.75 FOR 6.Lia$1 3CINT 1 *R R1 A TAsa 00NT!bj0v5 MJ0.

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

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JUAAT;;

.UARita

UARiiR R.L;Aat0 1

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. 13C1655 1131 CI

0. i s4 2-A : 0.C30i+;0 : 0.0002+10 :.0.030E+00 :

1123 Ci

C.11 0.

75: 05 : 0.000i+)c : 0.000f+00 :

....____........__.........'s.-01 T)TAL FCA :

P E R i a *J w

.1 10 0; 2 C. 2 ' 61_ *> 3
C.000E+)( : 0.000E+00 :

l :

CabOVc) 3.

PALTICULATLa C14 CI

0.0J0i+00 : 0.000d+JO : 0.000!*JO : 0.000i+

.___............................................__..__....___._____00 CAS:

CI

J.CJ0i+00 : 0.000:+00 : 0.000!+00 : 00 i

.............................__..._........__...__.__....____'J0!+00:

M:45 4 CI

0.000!*JC : 0.000C+00 3 0.000i+JO : 0.000!+0

__________.___...___0 FE53 C1

. 0 00 S+ JO : 0.000t+00 : 0.000i+00 : 0

........._........._............................__________000E+00 C056 Cl 3.000c+JO : 0 000d+00 : 0.000E+Jo :

0. 0

................................ ____.._...______.._____....._00E+00 C0c)

CI

J.v00h+)0 : 0.000t+00 : 0.000l+30 : 0.000E+0

.......................__................__________.........__.....____0 2N65 C1

0.0J0;+90 : 0.030E+
0 000i+)0 : 0.000E+00 :

...............______....__.........__..__'JO

$%d7 C

0.000i+00 : 0.000:+00 : 0.000i+0J : 0.000!+0

..................................______...____........___....__. __0 :

$<9J C1

0 0J0i+40 : 0.000i+00 : 0.000i+o0 : 0.000i+00 :

1415

I
0.030E+00 : 0.000i+00 : 0.000!+00 : 0 000i+00 :

54124 il

0.000c+00 : 0.000!+00 : 0.000i+00 : 0.000E+00 :

1...........__.........._.............__...... ___-....... _______..__.

C5134 C1

0.000E+00 : 0.030.+00 : 0.000E+00 : 0.000E+00 :

i :

Csa )6 CI

0.000E+
J.000c+0C : 0.000E+00 : 0.000E+00 :

1_.....__........_-____....__..0J......___........___.____............

l:

C5137 CI

0.000E+00 : 0.000C+00 0.0005+00 : 0.000E+00 :

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IrFLsENT1aa0 ha5TE DIS:C3at R2A;4T s554 Jus 4 F - L u t J T 5.* C A i' Lia$i 00:31:

1 '!0 7. T, 114CX 40dTINvCv5 N;0 34TCs

............................................................10JE l

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L a k i t. < -

.UaRTi4

UARi~

OUARTER P:LJA5CJ 1

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2 J.

PARf!CULATIS (L;hTU)

BA14J C1

0.700d*J1 : J.00JJ+00 2 0.000!*JO :

..........................................................0.000E+00

' Ct161 si
J.J;0i+:0 a 0.0.02+ 0 : 0 000E+00 :

.-......--...............................';................0.000E+00

'i L: 194 La

J.030:+10 : 9.000;+30 : C.000:+)0 : 0.000!+

..................................................................00 4

T0TAL FJR' A

PERICO CI

,,. 0 ) L i +, ; ; ;. ; 3;;+ J( : e 0 JCi+ ?O : 0.g00E+00 :

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,Aatsui.FdLVE.Ti L4 <!Llas! J3;Nf:

i J44T 1 - 5;UTh 5fACK CCNT I TJCJS ti h :

JATC4 au?E I

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0,1115 :

JUARii;

.~UARTEA JUARTtd WUARTER R d L i & S E ;-

1 2

1 I

le FISSIJN GAS;$

Ad41 CI

0.000 :4 30 : J.)JGh+0L : 0.w00E+00 : 0.112E 03 :

K<b3M C1

C.000:+00 : 0.030~+00 : 0.000E+00 : 0.000d+00 :

KR65M CI

).JJus+0; J.000i+0) : U.0005+00 : 0.000i+00 :

1 I :

Ad83 CI

0.0J6:+;0 : 0.020I+10 : C.0000+00 : 0.000E+00 :

AASI Oi

v.00Ci+50 1 0.000i+JO : C.0002+0C : 0.000E+00 :

K485 01 C.0J0:+JO : 0.0.30;+00 : 0.000i+00 : 0.000E+00 :

4 KRS7 CI

s.000i+00 : 0 030: 4JO : 0 000i+00 : 0 000i+00,:

K490 Ci

0.0]O.+;0 : 0.0J0c+30 : 0.070i+>0 : 0.000E+00 :

X: 1319 CI

0.000 +JO : 0.000E+JO : 0.000i+00 : 0.000i+00 :

xE133M 61

J.J0Ci+00 : 0.000i+30 : 0.0005+00 :
0. 0 00 E+ 00 :

t xc133 CI

a.3J5d+20 : 0.11? +30 : 0.0002+00 : 0.000i+00 :

Xc1354 01

..; Jet +3) : 0.000i+00 : 0.000E+00 3
0. 0 00 E+ 00 :

\\.................__........._................___..........__..____....

Ae1J5 C1

C.1J1:+J1 : 0.4J0i+JU : 0.000E+30 : 0.000E+00 :

XE137 CI

0.000i+00 : 0.000i+00 : 0.000!+00 : 0.000E+JO :

ll Xi1JE CI

0 0)Ci+JO : 0.0J0d+JO : 0.0]OE+00 : 0 000E+00 :

3 TOTAL FJR :

l P:RIC) 01

0.13Si+>1 : 0.5395+00 : 0.000i+00 : 0.112 E-0 3 : -

i :

_.(.A b O V c )

l__

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2 Jte I T 1 - $JLTH STA;K t

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3ATC4 T. J E

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... _............. _ _............'4 J U 'J S

  • .0 D....____.....__...........__'.......___
'NJCLIJ55
U til t i :

JuatT:4 sV4F.T:4 ObaRT11 QUALTIR HiLIA520 2

1 0

1 2

4.

IJ0!h25 J

1131

0.000i+30 : 0.CJ0i+00 : 0.0004+00 3 0.000E+00 :

1133 CI

0.0002+JC : 0.0002+00 : 0 0002+s0 : 0.0002+00 :

TOTAL !JR :

i PERICJ CI

w.0JOI+20 : 0.0 J 0 s.0 : 0.0J0!+10 : 0.0300+00 :

(AdJVd) 3.

PARTICULAfth C14 C1

C.4 00 E+ JC : e.000i+00 : 0.0 00 5+ 00 :
0. 000E+ 00 :

1 Cd51 2

CI

0.3475 )4 : 0.000i+00 0.000i+00 : 0.000E+00 :

.+

MNL4 CI

0. J 0 0 i + 0.-
C.100i+00 : 0.0002+00 : 0.0006+00 :

F:51 c1

0.000:+10 : 0.000i+JO : 0.000E+00 : 0.0005+00 :

Cold L2

0.000d+00 : 0.000d*00 : 0.0002+00 : 0.000E+00 :

3 J

CJL J CI

0.0305+JO : 0.000f+00 : 0.000E+00 : 0.'000E+00 :

8 Z:4e 3 C1

0.000t+00 : 0.0005+00 : 0.000i+00 : 0.000i+00 :

SRe 1 CI

0.0005+00 : 0.0005+00 : 0 0005+00 : 0.000E+00 :

5290 CI

0.0J0i+00 : 0.000i+00 : 0.000E+00 : 0.000E+00 :

2R95 CI

0.000C+00 : 0.0 00 E+ 00 : 0.000E+00 : 0.000E+00 :

s S1124 CI

0.000d+00 : 0.000i+00 : 0.000E+00 : 0.000E+00 :

C5334 CI

0.000i+00 : L.0 00 i+ 00 : 0.0 00 E+ 00 :
0. 0 00 E+ 00 -:-

C3136 CI

0.000E+30 : 0.030i+00 3 0.000E+00 : 0.000E+00 :
- C5137 C1
0.000E+30 : 0.000c+00 : 0.0005+00 : 0.000E+00 :

G b9 n

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61TE: LIMERICK-JN1T:~ U1 JScR:. COMB

- RA T E 81_0 8 / 2 0 / WO -J 9 : 3 3 AND AS TE DISN $ AL r.i?u 4 T

!F8LUENT

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00ARicR- :

F; s t i A 3 h y 1

.2 1

2

.8

j. PAlTICULATid.(CJNT.,)
_... _ _. 0 CI
-0.030c+JO : 0. 0 1 0 c + 0 0 --: 0.000i+00.: 0.0305+30 :

1 41

-- :8 -

Ci141 C1
' o.000d+00.: C
0.0005+JO : 0.000S+001:

_ _ _ _ _ _... _ _ _... _ _ _ _' _ _........... '_ _ _'. 0 0 0 i + 'J O... _ _ _ _ _. - - _ _ _ _ _ _ _ _.. _ _ _.. _ - - - _

CI

0. 0 0 0 :. + 0 0 > :
0. 0 0 0 - + 0 0 : 0.000i+30 :
0. 0 0 0 ci+ 0 0 :

1

.Cil44 "8-TOTAL F0k.:

. 0.000:+00 :

--8 :

P-RIOD CI

.:-0.5472-14 :

0. 0'; J c + 0 0 : 0.000E+00 :

.8 (AS]Vc)-

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' - JASEJU3 2F iLUtNT S. ?OR

LEAsi AUIAT:

3 UNIT: 2-SuuTHJ5TArK

......_____......__..______________=

C01T.NJcVS FOC?

3ATCn MCJt

..... _ _ _ _. _ _ _ _ _ _ _ _ _ _.. _ _ _. _ _ _ _ _ ' _ _l NUCc Jd'

UNITS :

JuaRTER

.UARTtR vUARTEA JUARTt4 LiLis 1

2 1

I

-.....__.......________.__.___..___________...____,w-ws l'.

T15 h JN vA$is

_____________..___...~._______

-l AR41

~ CI
0.0J05+00 : O.0001+00 : 0.0005+00 : t.000E+00r:

K463M-C;

-G.00cE+)u : 0.00ci+00c: J. 0 00 d+ 00 : 0.000E+00 :

- had5M CI

0.CJ0s+10 : 0.0002+30 : 0.000!+J0 : 0.000E+00 :

H o

Kids CI

s.0 Jus +0V : 0.000i+JC : 0.00CE+00 :

___________._'___..________C.7 34 E 03 ; :.

j E t KRbI CI

.: 0.000d+10 : 0.0;0c+]C : 0.000E+00.: 0.0005+00 :~

H KR63-C1

0.0000+00 : 0.000:+00 : J.0002+JO : 0.000E+00 :

j 2

q KR89 CI

0.0002+JO : 0.0002+001 : 0.030E+JO : >0.000E+00 :

i"~ik90~~~~~~I'~C5~~~I~0 0055~30~I~0!305E730?? 0:000i+50 I 5:535s+00 i

~

8 X :131.9 CI

J 000E+JO :
0. 0uc i+ 0 0
0. 0J 0i+ 0 0 : 0.0

_______________...____.._______'J0f+00 Xi1339 CI

0.0002+JJ : 0.0002+00 : 0.000E+00 : :0.000i+00-:

X:133-CI

a.J465+JJ : 0.124d 01 : 0.000E+]O;: 0.000E+00 :

Ai135M CI

0.0005+)U : U.0J00+00 : 0.0001+00 : O.000E+002:

J 3 ________________________________________________________'____________

- 8 'XE135 CI

6.105-+01 : 0.376E 01 : 0.0005+00 : 0.0005+00 :

Xi137

. CI
0.0J0E+00 : 0.0J02+00:: L 0.0c 05+)Oz : J0.000E+00 :-

Xil38 CI

0.000:+00 : 0.000k+00 : 0.000d+002: 0.000E+00 :

~:

TOTAL S]R :

4 P1RIDJ LI

C.140d+01 : 0.5005-01 : 0.0002+)0 : 0.7 34 E-03 :

4 (AE]VE) b

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TABLES i

B.

SUMMARY

OF RADIOACTIVE-LIQUID EFFLUENTS January I', 1990.-to June 30, 1990

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1

!FFLUENT AND W AS TE LISAc5AL AdanWT I

~

l L10Ul0 EFFLUENTS 50MMATION

._______..-0F-ALL P: LEASES l

UN!TS

JUARTER 20 AR TE R

CST.

TOT AL ::

1 2

cRROR ao FIS510N AND ACTIVAT;0

____....__..___-J.oRJUJCTS s

i l

- 'l e T]TAL REL.ASE (Exit.:

C.

0. lie!-01-: 0.2393-01-:-0.630E+01 :

T41T., G A$f 5, ALP 9A):

. i-2a AVERAdi DIL UT :0

UCI/1L.: 0.511 -07 : 0.9415-07 :
_._ CONC. buk!bG O c f.10. z
-3o' PERCENT 07 5
0.030J+00 : 0 0005+)0 :

-APPL;CA3L: LIMIT-q 4.

TRITIUM

- i 1

i

1 l a TJTAL R 3L. A 5 2 41 0.
0.112E+02 0.630E+01 :

i

___........____..____.______..113f+02 i-2.

AVERAo2 CIL UTf D

JC;/1L : 0.*S7i-J4 : 0 3935-04 :

C]NC. VuRING PEElse :

3e PiRCENT'Op t.
0.0J02+00 :: 0.000E+00 :

i APPLICAJL; LIAIT Co DISiOLVEC ANU ENT<A!Ni3'GA$i5 I

11.-TOTAL RELS A 5e 01 0.

..._______.____.___......._____..._523C__22 : 0.1035-J1 : 0.630E+01 :

to AVERAGE DILUTat-
JC I / ?tL : ' 0. J J 6 E-0 7 - : -'0. 3 50 5-0 7 :

~

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i d..V]LUME WAST: RELEASc0.: LITERS : b.7533+07 : '3.939E+07 : 0.000s+09 :

__(PRIOR TO LILUTION)

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V JLUME -;ILUTI ON W ATiR : LITERS : 0.222E+09 : C.2865+09 : 0.000E+00' :

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Td129 CI

0.0J0i+00 : 0.'00CI+30 :

0.~ 0 0 0 E+ 0 0 ': ' O. 0 0 0 E+ 0 0 :

.._____..'i.__..________u_______________________________..______________.

. 00Ci+3) : J.030i+00 : ' O.000E+00 : 0.000E+00 :

..Til29 CI Ti1314 C1
J.000E+JO : 0 010:+00 : 0.000C+00 : 0.000E+00 :

1:

Td131 CI

0.000:+00 : 0.000E+00 : 0.000i+00-: 0.000E+00~:

Td132 CI

C.0a0E+JO : 0.000h+00 : O.0005+90 : -0. 0 0 0 E+ 0 0: :

1130 CI

O.000E+30 : 0.000E+00.: O.000E+00 :: 0.000E+00 :

1131 CI

. 0.000E+00 : l0.000c+00 : 0.000E+00 : 0.000E+00 :

1132 CI

0.0001+00 : 0.000i+00 : 0.000E+00 :.0.000E+00 :

1133 C1

0.0)Ci+0C : u.000:+00 : 0.000E+00 :~ 0.000E+00 :

I134 CI

0.000E+00 : 0.000l+00 : 0.000E+00 : 0.000E+00 :

1135 CI

7.000E+00 : 0.000E+00 : J.000E+00 : 0.000E400 :

9 I

-h 49

.i

'PAGE 4 CF-5

SITE 3 LIMERICK 1

'vNIT;?J1 USiRI'CONB SATE: 08/20/90 09:33 i

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UNITS :

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UARTER ";

';UARTER 8

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2 1

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CI:

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C3136 C1

3.c XE+00 :-J.fjc2+00 : 0.0005+00 : 0.000E+00 :

8 C5137 Cl

c.0J02+00 : U.0J0i+00 : 0.137d 02 :

______________._..___________________________________ _____-0.3722-03 4

C5138

oCI
U.J002+0. : 0.9 Jus +00 :.0.0002+00 :
0. 0 00 E+ 00 ::

f ic EA139

- CI
0.010:+10 : 0.010!+00 :.0.000:+001 : 0.000d+00 :

r EA140

TC 1
0.000E+00 : U.0]0!+00 : 0.000d+00 : 0.000i+00 :

j i

____=____________________________________'.__________________________

l A141 CI

0.000i+J0 : U.000i+00 : 0.000i+30:: 0.000E+001:

q Bal*2 CI

0.0302+30 : 0.0

____________________________.._______'J06+00 : 0.000i+00 : 0.000E+00 :-

J L4140 CI

0. )00 + 0; : U.033d+0L :

-J.0 00 5+ 00. :' O. 0 00 E+ 00 :

I~~LI545~~~~~I~~35~~~I~073335 IO I~0$6365I30 i"073035I35"i"550002I55~I.

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a

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. 0.0J0i+)0 : 0.000f+00 : 0.000E+]0 : 0.000E+00 :

Ch144 CI

0.000 300 : 0.000k+00 :EO.000i+00 : 0.000E+00 :

,a PR143 CI

0.0000+JO : '0.000i+00 : 0.000E+00 :-0.000E+00 :

t :PR144 C1

0.0005+00 : 0.0002+00 : 0.0000+00 : 0.000E+00 :

y hJ147

HC I
0.000E+30': 0.u00i+0C : -0.000E+00~: 0.000E+00 :.

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- UNIT 8 U1-USER: ' C 0 i18 DATEJ 08/20/90 09:33 JPFLU

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CI

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0.000d+)0 :-0.0005+
0.2065-J2 :- 0.5735-02 :

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0.317E-02 : C.4535-02 :

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a i0 II.

TABLES

'.i C.

SOLID WASTE DISPOSITION REPORT f

January 1, 1990.to June 30, 1990

' I l'

l 1'

4 I

i

.=,:

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PAGE 1 OF 4 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 01/01/90 TO 96/31/90 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DOSPOSAL(NOT IRRADIATED FUEL)

A.

UNIT 6 MONTH PERIOD ERROR, %

1.

TYPE.OF WASTE

m3 2.99E+92 a.

SPENT-RESINS, FILTER SLUDGES, EVAPORATOR BOTTOMS, ETC.

CI 6.91E+82 25%

ob. DRY COMPRESSIBLE WASTE, m3 2.19F'91 CONTAMINATED EQUIPMENT, ETC.

CI 4.52 88 25%

IRRADIATED COMPONENTS, m3

8. 90E-8 c.

CONTROL, RODS, ETC..

CI e.08E+@9 m3 9.90E+90 d.-OTHEh DESCRIBE)

CI.

9.99E+98

~

(QUADREX,.SEG) cPORTIONS OF THE' WASTE IS' PROCESSED'BY OFFSITE VENDORS ACTIVITY-IS ESTIMATED.

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I PAGE 2 GF 4 I

2.

ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

CATEGORY A - SPENT RESINS, CATEGORY.B - DRY COMPRESSIBLE FILTER SLUDGES, EVAPORATOR WASTE, CONTAMINATED EQUIPMENT, ETC.

BOTTOMS, ETC.

ISOTOPE WASTE CLASS B WASTE CLASS A WASTE CLASS A ACTIVITY

% ABUNDANCE -

ACTIVITY

% ABUNDANCE ACTIVITY % ABUNDANCE CI CI CI 2n-65 6.17E+01 13.14%

9.49E+01 43.53%

E,27E+00 48.37%

Cr-51 3.16E+02 67.31%

4.54E+01 20.82%

5.23E-01 11.14%

Cs-137 2.71E+01 5.77%

3.73E+01 17.11%

7.02E-01 14.94%

Cs-134 1.65E+01 3.51%

2.67E+L*

12.25%

4.32E-81 9.19%

I-131 9.00E+00 8.90%

0.00E+00 e.90%

0.00E+00 9.00%

Co-60 1.61E+01 3.43%

5.96E+00 2.73%

3.51E-01 7.48%

Co-58 2.12E+01 4.52%

3.09E+00 1.42%

1.54E-01 3.28%

Fe-55 5.12E+00 1.09%

4.03E+00 1.85%

1.30E-e1 2.76%

Sr-89 9.SOE+00 9.80%

0.00E+90-9.Ge%

2.09E-02 8.44%

C-14 2.09E-03 8.00%

4.88E-01 9.22%

9.28E-03 e.20%

Mn-54 5.50E+00 1.17%

0.SOE+00 9.00%

0.74E-02 1.86%

Nb-95 9.OBE+00 8.90%

0.00E+00 9.08%

2.14E-03 e.95%

H-3 6.00E-03 e.00%

1.30E-01 8.06%

2.01E-93 8.04%

Ba/La-140 8.OOE+00 e.90%

0.90E+90 8.80%

0.00E+0e 9.90%

Ni-63 1.82E-01 8.04%

0.00E+09-9.90%

'6.47E-03 e.14%

Ag-110m e.90E+0e

-9.90%

0.OOE+90 e.Be%

2.90E-05 8.90%

Zr-95 9.00E+00 e.90%

e.00E+00 9.80%

0.OeE+98 e.Se%

P-32 9.00E+99 8.99%

0.00E+09 G.90%

0.90E+00 9.Ge%

'Sr-90 9.13E-92 8.02%

2.99E-92 e.91%

2.05E-83 9.04%

Cm-242-8.00E+00 e.00%

0.'esE+00 8.80%

0.SOE+0e 9.90%

Pu-241 9.90E+99 9.90%

0.90E+00 8.00%

0.00E+0e 9.90%

I-129 9.90E+09 9.09%

0.00E+0e 8.90%

0.00E+00 9.90%^

Tc-99 9.90E+0e 9.90%

0.00E+00 8.90%

0.00E+00 8.e0%

Nb-94 9.00E+00 9.90%

0.00E+03 9.90%

0.SOE+00 9.90%

Ni-59 8.00E+0e e.90%

0.00E+00 e.80%

~ e.00E+0e 9.80%

Co-57 9.00E+00 8.90%

0.00E+00 9.90%

5.90E-95 e.00%

Ce-141 8.00E+00 9.90%

0.00E+0e 9.90%

3.78E-03 9.08%

TOTALS 4.70E+02 100.80%

2.18E+82 lee.80%

4.79E+0e 100.90%.

ACTIVITY IS ESTIMATED.

CATEGORY A (41 TYPE A LSA, 94 ) TYPE A LSA), CATEGORY.B (38. TYPE A LSA),

(1 ) TYPY A LSA):

CATEGORY C (NO SHIPMENTS MADE).

NOTE CATEGORY C IS IRRADIATED COMPONENTS, CONTROL RODS,-ETC.

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,i, PAGE'4 OF 4

^t B: IRRADI A1C FUEL SHIPMENTS (DISPOSITION)

NUMBER OF SHIPMENTS MODE OF TRANSPORATION DESTINATION

__~

N/A (NO SHIPMENTS MADE)

COMMENTS:

05 SHIPMENTS WERE MADE FROM LIMERICK TO QUADREX FOR PROCESSING.

04 SHIPMENTS WERE MADE FROM LIMERICK TO SEG FOR PROCESSING.

NO SOLIDIFICATIONS WERE.USED.

COMPLETED BY' k

{- d/ N / 90 d4!/

.[

/ 90 REVIEWED BY o

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I

'II I.: ATTACHMENTS.

]

I A[

SUPPLEMENTAL-INFORMATION' Pccility: Limerick Generating: Station - ?Jnits 1-~and'2 Lic3nse:

NPF-39e(Unit'1) and NPF-85 (Unit 2) 1.

Regulatory-Limits (Technical Specification Limits)

A.

Noble Gases:

1 1 500 mRems/Yr - total body

" instantaneous" limits 5 3000 mRems/yr - skin'

per. Tech Spec 3.11.2.1 l

2 5 10~mRads - air' gamma

- quarterly air dose' limits 5'20.mRads

-air beta per Tech Spec.'3.11.2.2, 3

5 20 mRads - air gamma

- yearly air dose limits-5 40_mRads - air beta per Tech. Spec. 3.11.2.2 B.

Iodines, tritium, particulates with half-life > 8 days:

1. 5-1500 mRems/yr - any organ'

" instantaneous" limits-I (inhalation path) per Tech Spec. 3.11.2.1

2. $ 15 mRems - any organ

- quarterly dose limits per Tech. Spec. 3.11.2'.3 3

1-30 mRems - any organ

- yearly dose limits per Tech. Spec. 3.11.2.3 C.

Liquid Effluents:

y l'.

Concentration < 10CFR20

" instantaneous" limits.per Appendix B,-Ta51e II, Col. 2 Tech.; Spec. 3.11.1.1 25 3 mRems - total body

- quarterly dose ~ limits per u

5 10 mRems - any organ

, Tech.; Spec.J3.11.1.2

3. 5 6 mRems - total body

-yearly doserlimits.per 5 20 mRems - any organ Tech. Spec. 3.11.1.2.

2.

Maximum-Permissible Concentrations Per LGS Technical Specification-3.11.1.l', MPCs are not used to-calculate permissible release rates and concentrations for gaseous releases.

The MPCs specified in 10CFR20, Appendix B, Table II,-

Column 2.for identified nuclides are used'to calculate-permissible-release rates and concentrations for liquid releases.

h m.

.7 o

~

3..

Avarrgn Enargy Based 1on gaseous 1 effluent 1 releases for thefreport period, taverage beta-energy-is 0.285 MeV and-average gamme energy.is 0.22f, Mev.

1 4.

Measurements and Approximations'of Total Radioactivi'ty-l 1

A.

Pission and' Activation Gases-The method used is the Canberra Series 90 Counting System; GS - Gas Marinelli.

i B.

Iodines The method used is the Canberra Series 90 Counting System;-

>j CH - Charcoal Cartridge.

C.

Particulate:

The method.-used;is the Canberra-Series 90 Counting System; PT --Air-Particulate Sample, 47 mm filter.

D.

Liquid Effluents:

The method used'is the Canberra Series 90 Counting System and the Radwaste Liquid Discharge ~ Pre-Release Method with a 3.5 liter Marinelli.

5.

Batch Releases A.

Liquid Q1 Q2

  1. of Batch Releases:

-125 174-1

-Total Time period for batch releases, * -

'0350

.10301

, Maximum tinte period. for ~ a batch release, 92 95 1

Average time period for batch release; 66.8 65.1 Minimum time period for a batch release, 30 58 Average stream flow (Schuylkill River) during periods of-release of effluents 1.16E6'

-1.05E6 into-a flowing stream, gpm Minutes

=

i DS

h B.-

Gennoum Ol' 02 j

l#Lo'f. Batch Releases:

0-9-

Total Time period for batch' releases, O

1800 MaximumLtime period'for'a-batch release, 0

780 1

'0 200-Average time period 1for batch release,

~

' Minimum time period-for a batch release, *

.0 60-

  • = Minutes-

-6.

Abnormal Releases A '.

Liquid ~

4 None B.

Gaseous None i

7.

_ Description'of LGS Effluent Release Points Release Point 1 = North Stack, Common Release Point 2 = South Stack, Unit 1 Release Point 3 = South Stack, Unit 2

(

Release Point 4 =' Hot Maintenance-Shop-Liquid Release Point =-LGS. Liquid Radwaste Discharge 8.

Description of LGS Liquid Dose Receptors.

Receptor 1 = LGS Liquid Radwaste Discharge' Point Receptor 2 = Cit'izens Home Water Company Receptor 3 = Phoenixville Water Company Receptor 4 =. Philadelphia Suburban Water Company

^ Receptor 5 = City of Philadelphia Crew Course l

.v l

l

I D

i jIII.. ATTACHMENTS:

LB.

RESIDUAL HEAT REMOVAL (RHR) SERVICE WATER RADIATION MONITOR INOPERABILITY L

'C' RHRSW radiation monitor has been L

Since February 1990 the I

inoperable.

This monitor.has been incapable of performing its

= design function because temporary circuit alterations (TCAs)-have been applied to valve HV-51-lF068A.

The TCAs have prevented isolations of-the valve.

During.lA RHR Shutdown Cooling. Operation, degradation of.the.

t

.HV-51-lF068A valve was noticed.' After investigation, it was determined that the valve was binding ~at approximately one inch off its closed' seat.

The~ valve was able to be fully stroked while RHRSW flow was present, however, with no flow the valve would not seat properly.

Valve binding seems due to disc / skirt guide

-interference.

This interference does not occur'with~ flow since the flow tends to center-the disc in the valve body.

Currently the valve is maintained in theLthrottled open position to; ensure at least 6000 GPM through the "lA" RHR heat exchanger while both heat exchangers are in service with both "A" loop RHRSW pumps

-running.

This configuration does'not cause any significant operationally difficulties but will force added duty on,the "lB" heat exchanger and associated loop components will'be used in emergency operations.only to limit any further valve degradation.

RHRSW Heat-Exchanger = isolation on the "lB" heat exchanger and associated loop components will be used in emergency' operations only to limit any further valve degradation.

RHRSW Heat Exchanger

'1 isolation capability will also be affected if the. valve is unable to fully close.

Tne plant's ability-to isolate.the; primary. side along with interim valve closure mechanisms reduces the risk'of a

+

postulated contaminated release.

Valve repair is planned to take place during theLupccming Unit 1

(

Refuel Outage beginning September, 1990.

L L

1 l

I

n o.

f i

i

.III' l ATTACHMENTS-Ci PROCESS CONTROL PROGRAM (PCP), REVISION 9.

Section 4.0 of the PCP was added--to-accommodate the. contingency for-.

-processing that' falls to meet disposal site, shipping and' t

. transportation requirements.- Extra steps have.been added to=the PCP toiensure appropriate processing to meet disposalLsite-and-

)

shippingLtransportation requirements.

Section 5.4 of the.PCP was added to address' surveillance requirements for. solidification.

This.section-describes batch: sampling tests of solidified' waste.-

t If. waste batch test specimen fall-to verify solidification, guidance for alternative: solidification parameters is-provided.

If initial. test. specimens fail to. verify solidification, cat least.

a.

three consecutive: batches,shall be tested until specimens-demonstrate solidification.

The; Process Control Program shall.be modified as' required,to assure solidification ofLsubsequent; batches.-.These surveillance requirements wereLnot addressed in.

previous revisions, j

6 49

J y V 4 U D e' U 6 0 -

9

-O l

LGS.

-PCP'

'RMF

- l Page 1 ofJ16 TJG/KJC/BWS/ds1' I

~

1 1

iq LIMERICK GENERATING STATION UNITS 1=AND,2 PHILADELPHIA ELECTRIC-COMPANY 1

s SOLID RADWASTE-SYSTEM i

PROCESS CONTROL PROGRAM

\\'

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APPROVAL:

/

l LPLANT MANAGER i

PORC. MEETING: gg y4 -

DATEi 3[/g i

tap 9

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si I

l:

LGS - PCP

=

R3v. 9 i

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Page 2 of 16 H

TJG/KJC/BWS/dsl i

1.0 PURPOSE This program provides guidance and boundary conditions'for preparation of specific procedures for processing, sampling, analysis, packaging and shipment of solid radwaste in accordance with State and Federal Regulatory requirements.

,y 2.0 SCOPE

~

This program is applicable to the Limerick Generating-Station solid radsaste processing system.

3.0 REFERENCES

3.1 49 CFR Parts 170 through 178 3.2 10 CFR Parts 20, 50, 61.and 71 3.3 Standard Review Plan 11.4, Rev.

2, including Eranch Technical Position ETSB 11-3, Rev. 2 3.4 Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification 3.5 Low Level Waste Licensing Branch Technical Position on Waste Form 3.6 Limerick Generating Station. Technical Specification 3/4.11.3 3.7 South Carolina Department of Health and Environmental Control Radioactive Material License,No. 097 t

3.8 Barnwell Waste Management Facility Site Disposal Criteria 3.9 State of Washington Radioactive Materials License No. WN-1019-2 3.10 Chem Nuclear Systems Inc. Topical Report RDS-1000 Radioactive' Waste Dewatering S,vstem RDS-25506-01-NP-A l

3.11 Stock Equipment. Co. Topical Report Quick Dry Process for 1

Dewatering Bead Resin and Filter Sludge, SRS-003-P Rev. O '.

3.12 Nuclear Pacific Inc. Topical Report for Dewatering System TP-02-P-A Rev. 1.

l U

LGS - PCF

-l.

R2v. 9 1

Page 3 of 16.

l' TJG/KJC/BWS/dsl i

3.13 Westinghouso-Hittman~ Nuclear, _Inc. Topical Report.STD-R I OllP-A, Mobile Incontainer Dewatering and Solidification System.

4.0 GENERAL

~

l Plant Technical Specifica ien 3/4.11.3 requires the Solid Radwaste Processing Syr. rett to be used in accordance with a Process Control-Program.A meet transportation and disposal site requirements.

[

It~is the intent of the. Process. Control Program to provide reasonable assurance of meeting the regulations and to demonstrate compliance with 10CFR61 by:

Defining the various waste streams

-Establishing a set of. process parameters that af5ect solidification and developing __ operational controls'for those parameters.

L Implementing a Waste Classification System in accordance with 10CFR61 and applicable Regulatory Guidance.

Providing an appropriate Quality Control Program as required by 10CFR20.311 When processing does not meet disposal _ site and shipping and transportation requirements, shipment shall be suspended'and the Process' Control Program, the implementing procedures and/or'the solid waste system'shall be corrected as I

necessary to prevent recurrence.

When process! g is not performed in'accordance with the-Process Control Program, the improperly processed waste'in each container shall be tested to ensure that it meets burial site and shipping requirements and appropriate administrative action will be taken to prevent recurrence.

4.1 - REVIEW, APPROVAL, CHANGES 4

4.1.1 Changes to the Process-Control Program shall be reviewed and approved by the Plant Operations Review Committee in accordance with Technical Specifications 6.5.1 and 6.13.

%I

~

+

^

U LGS -3PCPJ L

'lf

. Rev. 9 Hi

,lL Page 4 of-16J TJG/KJC/BWS/dsl

~

4.1.^ 2 _ Changes shal1~be submitted to the Nuclear Regulatory 1

Commission-in'the Semi-Annual Radioactive Effluent Release Report for the period in wisich'the change was made'in.accordance with Off-site Dose Calculation Manual Section I3.6.

l i

4.1.3 Changes;to resin dewatering implementing procedures z

cystems shall-require verification that the free or standing water content of the packaged product.is

'within!the<. limits established by regulatory limits via ST-0-RRR-733-0.

4.~ 2 USE OF VENDOR. SERVICES 4.2.2 For Vendor dewatering described in Section 5.2 and 5.3 the Chem Nuclear Rapid 1 Dewatering System RDS-1000 may be utilized.

A description of the Chem Nuclear 4

-equipment and process method'may be found:in Topical Report PDS-25506-01-NP-A previously submitted to the NRC.

4.2.3 For Vendor dewatering described.in Section 5.2 and f

5.3 the LN Technologies / Stock EquipmenttCo.-Quick Dry j'

Process may be utilized.' A descriptionsof theJLN-Technologies / Stock Equipment Co. equipment and..

-process method may be found in Topical Report: SRS-1 003-P Rev. O, previously' submitted to the:NRC.

l 4.2.4 For Vendor dewatering. described in: Sections 5.2 and 5.3, the Pacific Nuclear Systems.dewateringJequipment.

S may be utilized.

A description ofLthe Pacific

. Nuclear equipment and process method may be found~in Topical Report TP-02-P-A Rev.El, previously' submitted I

to the NRC.1 4.2.5' For Vendor dewatering descrided in. Sections 5.2.and 5.3, the Westinghouse-Hittman NuclearEdewatering i

equipment may be utilized.

A description of.the-Westinghouse-Hittman. equipment and process-methodomay be found in Topical Reporth STD-R-05-011P-A,y previously submitted to the NRC.

1 l

t I

4

'.b %

LGS - PCP, l

l Rev. 9 i

i Pago 5 of 16 l

TJG/KJC/BWS/dsl 5.0 IMPLEMENTATION The Process Control Program shall be implemented by the use

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l of approved plant procedures which provide the step-by-step dirtsetion for the operation of the process systems and shipment of waste to a licensed burial site.

A list of i

plant procedures which implement the Process. Control Program is gi"en in Table 6.1.

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5.1 WA.6TE STREAMS 5.1.1 CONDENSATE FIl.TER/DEMINERALIZER SLUDGE The contaminated waste product generated by the backwaoh of the condensate filter demineralizers consisting of contaminated powdered ion exchange resins at varying degrees of exhaustion, fibrous filter media, carbon overlay material, and small concentrations of various solids, activated and non-activated corrosion products.

5.1.2 WdSTE SLUDGE s

The contaminated waste product generated by the backwash of the liquid radwaste and fuel pool filters and demineralizers consisting of contaminated powdered ion exchange resins and bead resins at varying degrees of exhaustion, fibrous filter media, carbon overlay material and small concentrations of various solids and corrosion products.

5.1.3 REACTOR WATER CLEANUP PILTER/DEMINERALIZER SLUDGE A contaminated waste product gen 9 rated by.the backwash of the Reactor Water Cleanup filter demineralizers consisting of contaminated powdered ion exchange resins at varying degrees of' exhaustion, fibrous filter media, and small concentrations of various solids and corrosicn products.

5.1.4 DRY ACTIVE WASTE Dry. wastes consists of air filters, miscellaneous paper, rags, etc., f rom cont aminated areas; contaminated clothing, tools, and equipment parts j

that cannot be effectively decontaminated; and solid laboratory wastes.

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.l POg3 6 of 16 TJG/KJC/BWS/ds1 5.1.5 OILS / SLUDGES-WET RADIOACTIVE WASTES i

Oils consist of non-reclaimable contaminated oils and grease of various grades both synthetic or otherwise in free form or containing various amounts of solid material.

Sludge consists of sump dewatering sludges, filter solids, strainer solids and other wet solids too large to be handled by. conventional dewatering techniques.

5.2 PROCESS DESCRIPTION 5.2.1 CONDENSATE FILTER /DEMINERALIZER SLUDGE Each condensate filter /demineralizer backwash a.

consists of approximately 9,000 gallons of slurry with approximately 350 lbs (dry wt.) spent resins and crud.

b.

Successive backwashes are collected and allowed to settle in a Condensate Phase Separator.

As

)

the sludge settles, clarified liquid is decanted, For centrifuge dewatering of the settled sludge, c.

the phase separator is isolated when approximately 240 cubic feet of sludge has accumulated.

d.

For vendor dewatering of the sett. led sludge, the phase separator is isolated when approximately 360 cubic feet of sludge has accumulated.

The settled sludge is allowed to decay in e.

preparation for dewatering while further backwashes are routed to alternate phase separators.

f.

The phase separator contents are recirculated for a niinimum of 30 minutes to mix contents of the vessel, resulting in.a homogenous resin slurry.

(For centrifuge dewatering the mixture is approximately 5% dry wt. concentration.

For Vendor dewatering the mixture is approximately 7%

dry wt., concentration).

9 The solids slurry is then fed to a centrifuge or the External Processing Station for dewatering as appropriate.

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TJG/KJC/BWS/dsl 5.2.2 WASTE SLUDGE a.

Each backwash from a radwaste or fuel pool filter demineralizer consists of approximately 1,500 gallons of slurry, with approximately 60 lbs.

(dry wt.) spent resins and crud (may contain charcoal overlay).

b.

Each backwash from a radwaste demineralizer consists of approximately 1,500 gallons of slurry, with an average of 2,125 lbs.-(dry w

)

spent resins (may contain charcoal overlay' c.

Successive backwashes from radwaste filter demineralizers, radwaste demineralizers, and fuel pool filter /demineralizers are collected in the Waste Sludge Tank until approximately 12,000 gallons of liquid is accumulated.

d.

The Waste Sludge Tank contents are recirculated for a minimum of 45 minutes to mix contents of the vessel, resulting in a homogeneous resin slurry ranging from 0.5 to 6% (dry wt.) total solids.

During normal operation the Waste Sludge Tank contains only the radwaste and fuel pool filter demineralizer backwashes which result in-a 0.5%

(dry wt.) total solids concenuation.

Periodic radwaste demineralizer backwashes will increase tie solids level' to approximately 3% (dry wt.)

for $ne bed or 6%(dry wt.) for two beds.

e.

The solids slurry is fed to-a centrifuge for dewatering or to the External Processing Station for vendor services proce'ssing.

f.

Waste Sludge Tank contents may also be sent to a condensate phase separator for processing in accordance with Section 5.2.1.

5.2.3 REACTOR WATER CLEANUP FILTER /DEMINERALIZER SLUDGE a.

Each RWCU filter /demineralizer backwash consists of'approximately 1,100 gallons of slurry with approximately 48 lb. (dry wt.) spent resins and crud.

b.-

Successive backwashes are collected and allowed to settle in a phase separator.

As the sludge settles the clarified liquid is decanted.

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TJG/KJC/BWS/dsl For centrifuge dewatering of the settled sludge, c.

the phase separator is= isolated when' approximately 140 cubic feet of sludge has accumulated.

d.

For vendor dewatering of the settled sludge, the phase separator is isolated when approximately a

190 cubic feet of sludge has accumulated.

e.

The settled sludge is allowed to decay in preparation for dewatering while-further backwashes are routed to alternate phase separators.

f.

The phase separator contents are recirculated for

~

a minimum of 30 minutes to mix contents of the vessel, resulting in a homogenous resin slurry.

(For centrifuge dewatering the mixture is approximately 5% dry wt. concentration.

For vendor dewatering the mixture is approximately 7%

dry wt.. concentration).

g.

The solids slurry is then fed to a centrifuge or the External Processing Station.for dewatering as appropriate.

5.2.4 Resin sludges from different waste streams may be mixed to optimize packaging.

5.2.5 OILS / SLUDGES a.

Sludges and oils generated during operation and maintenance are collected in containers in appropriate approved areas throughout the plant.

The filled and labeled containers are sealed and moved to a controlled-ace'ess enclosed area for temporary storage.

b.

Oils and sludges can be solidified in appropriate containers by vendor. supplied equipment in accordance with approved vendor process-control procedures.

c.

Certain wet wastes may be allowed to dry and be treated as dry active waste.

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P0ge 9 cf 16 TJG/KJC/BWS/ds1 5.3 DEWATERING PROCESS CONTROL 4

5.3.1 Centrifuge Resin Sludge Dewatering a.

The 0.5-64 solids slurries discussed in Section 5.2 are fed to a centrifuge at a controlled flow rate for dewatering.

s b.

Operating variables such as centrifuge pond setting, bearing temperatures, equipment vibration, and differential torque are monitored i

to ensure optimum centrifuge operation and l

compliance with the free standing water criteria.

c.

The centrifuged resin is packaged in i

appropriately selected liners or High Integrity Containers (HIC).

Process system level probes extending into the liners or HICs ensure that void spaces within the container are minimized to the extent practical.

5.3.2 Vendor Resin Sludge Dewat'ering a.

The 7% solids slurries discussed in Section 5.2 are fed unthrottled to Vendor dewatering systems at.approximately 30 gpm.

b.

Vendor-dewatering operating variables such as waste type, process time, pump suction pressure, blower inlet pressure, ambient temperature and percent relative humidity are monitored to ensure optimum operation and compliance with the free standing water criteria for burial, Vendor dewatered resin is packaged in c.

i appropriately selected liners or High Integrity Containers (HIC).

Process system level probes and/or video cameras mounted within the fill head l

ensure the liner or HIC is filled without undue void spaces to the maximum extent practical.

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TJG/KJC/BWS/dsl l 5.4 SURVEILLANCE REQUIREMENTS FOR SOLIDITICATION 5.4.1 At least one representative test specimen from at least every tenth batch of waste shall be solidified.

5.4.2 If any test specimen fails to verify solidification, the solidification of the batch under tesb shall be e

suspended until additional test specimens can 5:'

obtained, alternative solidification parameters can be determined and a subsequent test verifles solidification.

5.4.3 If the initial test specimen from a batch of waste fails to verify solidification, representative test specimens from consecutive batches shall be tested until at least three consecutive test specimens demonstrate solidification.

The Process Control Program shall be modified as required to assure solidification of subsequent batches.

5.5 10CPR61 IMPLEMENTATION 5.5.1 WASTE CLASSIFICATION a.

For dewatered resin, waste classification shall be based upon dose-to-curie calculation and the use of scaling factors for hard to measure isotopes.

After each container fill, appropriate dose rates are obtained and inputted into Radman.

A detailed analysis is performed on an annual basis by an independent commercial laboratory to identify isotopic abundances and scaling factors via ST-0-RRR-731-0, ST-0-RRR-732-0.

b.

For dry active waste (DAW), waste classification shall be based upon isotopic analysis and the use of scaling f actors for Reactor--Water along with DAW dose-to-curie conversion.

g 9 966 c.

For oils / sludges, waste classification shall be based upon isotopic analysis and the use of' scaling factors for hard to measure isotopes.

A

. detailed analysis is perforr7d on each batch to be processed and packaged.

d.

A computerized waste classification and shipping program, RADKAN, is used to determine waste classification from the isotopic analysis and scaling factors.

Manual methods may be used if the computer system is not available.

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TJG/KJC/BWS/ds1 5.5.2 WASTE STABILITY a.

MINIMUM STABILITY REQUIREMENTS 1..

Waste at Limerick Generating Station is packaged in metal containers (drums, boxes, liners) or High Integrity Containers.

In no case shall radicactive waste be packaged'in cardboard or fiberboard boxes for burial.

2.

Dewatered resin is sampled as a minimum annually to verify that the free standing water content of the packaged product is within the limits established by applicable regulatory limits via ST-0-RRR-733-0.

In addition to the annual verification, the free standing water is determined whenever process changes occur that may significantly alter system dewatering performance.

3.

To prevent accumulation of radiolytically generated combustible gas in greater than Type.A radioactive waste packages containing water and/or organic substances, one or more of the following measures are taken:

The container is equipped with a vent to prevent accumulation of_such gas.

A determination by calculation, test, or measurement is performed to ensure that hydrogen generation is limited to a molar quantity that would be no:more than 5% by volume of the secondary container gas void at STP over a period of time that is twice the expected shipmbnt time.

The cask cavity will be inerted.

4.

Experience has demonstrated that utility waste streams do not contain or generate toxic gas, vapors,-or fumes and do not contain hazardous, biological, pathogenic, or infectious materials.

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TJG/KJC/BWS/dsl b.

WASTE STABILITY 1.

Dewatered resin required to be stabilized is packaged in High Integrity Containers (HIC)

~

that have been certified to meet the stability requirements of 10CFR61.56(b)..The HICs are handled.and stored in a manner such that their ability'to provide stabilizatibn is_not compromised.

The chemical and physical properties of the resin in no way compromises the integrity of the container.

2.

All reasonable efforts are made to eliminate unnecessary void spaces within the waste-packages.

5.5.3 LABELLING Each package of waste s'ill be clearly labelled to identify waste classiff ution.

5.5.4 S:11PMENT MANIFESTS Each waste shipment shall be accompanied by a shipping manifest giving a physical description of the waste, the volume, the radionuclide identity and quihtity, the tot &1 tadioictiVity, the principal chemical form, and waste class.

5.5.5 00ALITY CONTROL PROGRAM a.

The quality control program consists of required use of plant procedures which implement the Process Control Program and requirements'of'the Corporate Quality Assurance Program.

Audits by-personnel independent of the activities are performed and reviewed by appropriate management personnel, b.

In addition, the Process Control Program and implementing procedures are audited once per 24 months

.y the Nuclear Review Board in accordance

,with P,>nt Technical Specification 6.5.2.

5.6 ADMINISTRATIVE COhfROL 5.6.1 Processing of solid radioactive waste shall be performed by properly trained and qualified operat'ing personnel.

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TJG/KJC/tWS/dsl 5.6.2 Processing of radioactive waste shall be performed in accordance with approved Operating and/or Radwaste procedures.

5.6.3 Procedures for processing, containerization, and transport of waste shall ensure that specific DOT, NRC, and burial site requirements are satisfied.

s 5.6.4 Changes to implementing procedures are reviewed to ensure continued compliance with the Process Control Program.

5.6.5 Records of all data, tests, analysis results, and records of training,-inspection, and audits are maintained in accordance with plant QA procedures for record retention.

d.0 ATTACHMENTS, TABLES, FIGURES,

6 '.1 Table 6.1 Process Control Program Implementing Procedures.

6.2 Figure 6.1 Solid Radwaste Management System Process Flow Diagram.

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l TJG/KJC/BWS/ds1 ATTACHMENT 6.1 Process-Control Program Implementing Procedures A-99 Control of the Radwaste Process Control Program RW-100 Administration of the Radioactive Material and Radwaste Packaging and Transportation Program y

RW-101 Administration of Packaged Radioactive Waste RW-103 Isotopic Determination of Packaged: Radioactive Material RW-106-Review of Vendor Topical Report for Waste Processing RW-130 Administrative Controls for RADHAN RW-132 User's Guide to RADKAN RW-222 Sh'ipment of Radioactive Waste to Barnwell RW-223 Shipment of Radioactive Waste to Richland RW-230 Core Sample of Liners and HIC's RW-420 External Processing Station

  • Resin Transfer and Dewatering Using Pacific Nuclear Containers and Equipment S66.8.B RWCU Phase Separator Decanting S66.8.C Centrifuging RWCU Phase Separators S66.8.F Centrifuging Waste Sludge Tank S67.8.A Operating the Resin Pill Stations S67.8.A Equipment Alignment for Operation of a Solid Radwaste (COL)

Centrifuge S67.8.B Condensate Phase Separator Decanting-A S67.8.G Centrifuging Condensate Phase Separators S67.0.A External Processing of RWCU Phase Separators S67.0.B External Processing of Condensate Phase Separators S67.0.C' External Processing of Waste Sludge Tank i

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TJG/KJC/BWS/ds1 ST-0-RRR-731-0 Periodic Sampling and Analysis Program for the l

Determination of Abundance Factors l

l ST-0-RRR-732-0 Periodic Determination and Update of Abundance l

Factors for Gamma Emitting Isotopes ST-0-RRR-733-0 Sampling and Analysis of Dewatered Rerins for the Determination of Free Standing Liquid j

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ATTACHMENTS D.

O.D.C.M.

Revision 8 NRC Generic Letter (GL) 89-01 recommended that licensees relocate certain procedural details of Radiological Effluent Technical Specifications (RETS) into the ODCM.

Per GL89-01,-procedural details of Technical Specification sections regarding Radioactive Gaseous and Liquid Effluent Monitoring Instrumentation have been relocated to Revision 8 of the ODCM.

The-following have been relocated to the ODCM Dose limits for gaseous and liquid effluents; Technical Specification for liquid effluent concentration and liquid radwaste treatment system; Technical Specification for ventilation exhaust treatment system, venting and purging; Procedural details of Technical Specifications-for the Radiological Environmental Monitoring Program (REMP);

Meteorological monitoring instrumentation Technical Specifications; Site maps defining unrestricted areas and site boundary for radioactive gaseous and liquid' effluents; Programmatic controls concerning the reporting requirements for the Annual Environmental Operating Reporet and the Semi i

annual Effluent Release Report.

Revisions were also made to the ODCM according to the suggestions offered by the N.R.C. after reviewing revision 4, in their letter of December 8, 1988.

These changes include:

Specification of minimum cooling tower blowdown; Correction of transcription errors for bioaccumulation factors;.

Inclusion of an engineering diagram for the hot maintenance shop; Repositioning of subscripts for clarity; Inclusion-of Frick's Lock and Limerick Information Centers as locations within site boundary accessible to members of public.

i

l Changes have also been made to Chemistry-related setpoints.

These triisions include:

Wide Range At:cident Monitor setpoints:

The high setpoint is set at 10 tiines the alert setpoint, not to exceed 2.1 uCi/cc equivalent uling 2-onit maximum north stack flow rate; Routine operations alert setpoints shall not to exceed 1.lE-4 uC1/cc per FSAR table 11.5-2; Revision of containment purge setpoints for 2-unit maximum north stack flow rate; Specification of "non-gamma emitters" for the liquid radwaste discharge monitor; Specification of a maximum background count rate of 300 CPM for Service Water and RHR Service Water monitors; Guidance to establish the alert setpoint for containment purges through 1 or 2 inch vent lines, with the setpoint not to exceed 3.4E-6 uCi/c: per LGS FSAR table 11.5-2.

Miscellaneous revisions have been made to the ODCM to serve 2-unit operation and other purposes.

These revisions include:

I Correction of formula 2.23 to reflect the proper' location of the tissue-air ratio (1.11) factor; Reprinting of tables 2-2 for clarity; Revision of table B-1 and figure B-1.

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