ML20153D852
| ML20153D852 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/30/1988 |
| From: | Leitch G, Mccormick M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8809060055 | |
| Download: ML20153D852 (98) | |
Text
,
r PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-352-SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 8 JANUARY 1, 1988 THROUGH JUNE 30, 1988 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating License NPF-39 Preparation Directed by:
G. M. Leitch, Vice President Limerick Generating Station M * {_
,,e M. J. We Cormick, Plant Manager 8809060055 800630 ADOCK OSO g 2 PDR R
5 tIi
y f
TABLE OF CONTENTS I.
Introduction II.
Tables A.
Summary of Radioactive Gaseous Effluents B.
Solid Waste Disposition Report III.
Attachments A.
Supplemental Information - Assumptions Used in Report Generation B.
Residual Heat Removal (RHR) Service Water Radiation Monitor Failures C.
Process Control Program, Revision 3, 4,
5, 6, 7 (Submitted Under Separate Cover) 9
I, INTRODUCTION This submittal complies with the format described in 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 Cooled Nuclear Power Plants", Revision 1, June, 1974.
The following information is included as Tables to this report:
A summary of the gaseous effluent releases for the report period.
(There were NO liquid releases to the Schuylkill River during the report period.)
Where "0.00E+00" is used, it denotes the less than detectable level for the given isotope.
A nummary of solid waste dispositioned during the report period, to include: 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.
The following information is included as Attachments to this report:
An explanation of why inoperable Residual Heat Removal Service Water Radiation Monitors were not returned to service within the time specified, pursuant to Technical Specification 3.3.7.11.
A copy of the 5 Process Control Program revisions and an erp'.onation for all changes which were implemented during the report period.
An Amendment to the Gaseous Effluent Summary submitted in the Semi-Annual Effluent Release Report for the period July 1, 1987 through December 31, 1987.
II.
TABLES A.
SUMMARY
OF RADIOACTIVE GASEOUS EFFLUENTS January 1, 1988 to June 30, 1988 T
I e 17 r. g t..w..r. p 1 C.y UNIT: U1 l
USU(! MART I.,4. T E
- 6. 8 /.$ rd o. g 1.=)
g A.
rrT e Lir N T A yI. Lr a e. T.e I.r e. F.n. c. Ai R _r e n..e. t.
s GAEEOUe.
.r. F F L U E.N i c. _ _ e n..w..w. A T I n. y o.r
.o. e..e. e. r n... e r e N. e.lI I C.
O lJ A. P, T. f..D.
0.1J 4. 0.. T.L* O. i E c. I..
- 7. 0. T p.i.
r Le n..o.,
A. FISSION AND ACTIVATION OASES
- 1. TOTAL RrLEAe.r CI
- 0. n. n. a. r s. a. 0
- n. 10.ir s. n.,.
- n. 4 w. a. r. + n..,
- .. Ayt.r.Arr p.tLrAer
. Lv a I,/ c..r. e. e. c o n. t a. c 9.
- n...i m.. a. n.,
a.
RATE FOR PERIOD
- 3. PERCENT OF TECHNICAL:
- 0.000Ef00 1 0.000Ef00 :
SPECIFICATION LIh!T :
D. 10 DINES
- 1. TOTAi.
.r. 3 D I e r.1 i.,
- e. t
- n.. _a 4 e. r. n. 4 A.
.6. e r _ n..,
- n.. /. =. r r. a. n..-
- 4.. AyE e.4. C, E F.rL E A e. r
.u i r. I / e.r e.
- n....i r. e.. ^ r.
- a...n o...r. w w
RATE FOR PERIOD
- 1.. F E F.' C E.y T O F T E E. p y I(. s !..
- ..Ar>eEsAn t..^^nr466 qI.E C I.t I C a i 4y "U
t.t.k..i t C. PAM ICULATEE
- 1. p.4c.iJ C'JL MS V! i. u.
- r. t.
. v. ^..z r.n. r.' n.. ^. ^. ^. r + C. 6. ^ e. r. a. r 4 6..*
l HALF-LIVES 19 DAYE
- 2. AVERAGE RELEASE UCI/EEC: 0.i'4E-Of : 0.000E+00 :
RATE FOR PERIOD
- ?. PERCENT OF TECHNICAL:
- 0.000E400 : 0.000F+00 :
SPECIFICATION LIM T !
- 4. GROSS ALPHA CI
- 0.000r+00 0.000E+00 :
RADI0 ACTIVITY D. TRITIUM
- 1. TOT A'.
RE
- e..t
<s. m.. r. 6. 4 n... c. a e. r. n..z n.. n.. n. t. 4 6., i.
.......... _ _ _ '. E A e. r e
e n. C I.e e. E C
- n.. e.1.e r. o. r.
.i n.. i 1 e. r. o.
... ALir R. A C, E R.r L E A e. r RATE FOR PERIOD
- 3. PERCENT Of TECHNICM :
2
- 0.000E+00 : 0.000E+00 :
SPECIFICATION L!MIT :
.c.t. r :- 1
- n..r c.
CITE! LIMERICL Uh'! T U1 USER: MART A T f.
0 8,/ 9 E./ Q Q
.t.i e r.,. 0 ErrLC""I A ND UA c. i.r p.i e.s.gc. Ai. p. e c. n. c. T GASEOUS EFFLUENTS FOR RELEASE FOINT:
1 NORTH STACM CONTINU0UE MODE FATCH MODE
! NUCLIDES UNITS : OUARTER
- QUARTER :
QU/tRTER QUARTER RELEASED 1
2 1
- 1. FISSION GASES AR4i C-I
- 0. 0 A A. r f o. n.
A.. A. 0 A..r. 4. 0 A.
A.. A. 0 A. r 4. A. A.
A.. A. A. A. r_ 4. A. A.
+
e b R.D.1M CI A.
0 A. A. ri A. A.
A.- e 0 r o. r. 4. A. A.
A.. A. A. r r 4. A. A.
A.. A. 6. A. r 4. A. A.
e e
e e
b E O r..g w
L
- g. 4. 0 S r. Y A. A.
A. e. A. o..r 4. A. q e.
A o, e. 3 A. r A. A. 0 e A.. A. A. A. r ; r..,
A e
e s.
s.
e V. e. e r e
at
^ A V e. A. A. F. I ^. ^.
A.. A. A. 6. r 4. A. A.
L,
- A. A. A. r 4. A. A.
e a
A.. A. r A. r 4. A. A.
e L.
e J
rr.s e
e e
b' P-L. 7 8
e'
% e. A. A. P J A. A.
A.. A, A. A. F 4 A. *.
A.. A. A. A. r 4. A. A.
A.. r 6. /.. " 4. A. r..
A
+
5.
I R. A E e
e F*
^A V e. A. A. r q o. r A.. ?. A. a r t A. 0 e
/.*. A. A. A. r. 4 A. A.
A. e. A. A. r 4. A. r A
+
w e
wl e
e bm.o n.
- o..f e
e
- o. e A. a. r A. A. A e,
o. A. A o. r 4 r.t A.
.e A. A. A. A..r a. o. t, f. A. A. o. r 4 A. A.
A
.i e
lw e
e e
s V. Ci i A.
- f..t A.. A. A. A. r a r. o.
(.
A. A. A. r 4. A. r..
A.. A. A. A..r 4. A. A.
e e
f.w A. A. A. r 4 r /.
e
.i s
e e
e e
e X E.17. l a
- r. I A.. A. A. A. E 4. A. A.
A.. A 4. A. r. 4. A. 0
- A,. 3 A. o. r. i o. f A.. A. A. o. r. 4. A. A.-
m e
va s ar t e.
e X L i s a.y A.. V ^. 6 r i A. A.
A.. O O.e r. A.
'e
^
S h, e. A. A. r 4 ^ 6 A
A.. A. ^J V. 4. A. A.
^&
e e
61 e
e
.V e
v.
XE132 CI 0. A. A. A. r e. A. A.
- e.. o. o t. r 4 6. 4
- 6.. A. A. A. r 4. A. A.
0. A. A. A. r 4. A. A.
+
e
+
e XE135M CI
- 0.000E400 : 0.000E+00 : Ce000E+00 : Ce000E+00
! XE135
- CI
- 0.000Ef00 : 0.422Ef01 : 0.000Ef00 : 0.000E+00 :
! XE137
- CI
- 0.000E+00 ! 0.000E+00 : 0 000E+00 : 0.000E+00 :
XE130 CI
- 0.000E400
- 06000Ef00 : 0.000E400 : 0.000E+00 :
UNIDENT.
CI
- 0.000Ef00 1 0.000Ef00 ! 0.000E+00 : Oe000Ef00 :
TOTAL FOR :
F r R ICI.
.i
- e. I 0 0 o o..r + 0 0 0.. A. i.r + A t.
- 0. A. A. n. e 4. A. A.
A.. A. b. b. e + r.. A.
w e
s e
l
( A B O'.'E )
r N T E F, C C.' ' O E R A C. E e. t t.e. r s t.y p c. A. e..... n. t e.
e.
rW.
.C A ' T
_ n..t O.
. S.' T E ' ' I.". r. R' ' c..r US'.R! M ART I,
- . ATE : 0E/25/09 12:51 li EFFf.UENT AND Uf.STE DISPOSAL REPORT b
GASEQUS EFFLUENTS FOR RELEASE POIHf!
1 NORTH STACK CONTINUOUS MODE PATEH MODE I NUCLIDES
- UNITS : GUARTER OVARTER O!.' A R1 F R OVARTFR :
- RELEASED 1
2 1
2 2 10 DINES
- 17
^
'l. 9 4 O. r. n.,a 0. 6.S e. r
- 6. 9
- n.. o. n. n..r 4. A. n.
- n.. n. a. a. r 4. r.,6 e.
Jewd LA e
1..
1si
- e..t
- 6...a.m o. r. n. 4
- n.. i. 4.e.r n. v.
0. n. n. o. r a. n. n.
- n.. n. a. n. r a. n. i l TOTAL FOR :
F c R. s e. t.
- e. I n,.m... r. n. 1
- n...s.u, c.. n.s
- n.. n. a. a. r t. C, n,.
r.,. e n. n. e s. a. n..,
s 1
(AF0VC)
- 2. PARTICULATEC t.a. J L.t (n. o. n. n. r $ n. n.
- n.. e. n. ?., r a. n. n.
n,. n. o n. r A. 6. A.
a A. e. n. t. r. a. r..a e
4 e
e e
e e
crc rt
- e.. n. r. e. r a n. ^.
0. A. /s o. r a. t r.
- n.. s. n. a..r. 4 6. n.
.. n. 0 o. r. 4. a. o.
a s
- m. 6r g
- e..t
- o.. o n e..r s. n. n.n.. e n. o. r a. n. a. s..n. n. n. c e. n.
- a.. n. e. n. r. a. n. n.
F.r e. n
- r. I
.i 0. a. n n..e t. n 0
- n.. n..,n. e.t. o. n.
- n.. o. n. n. r a. n, n.
- n.. a. n. n. e 4. n. e..
i
~
COrC CI
- n.. n. n. 0.r a. n. n.
. n.. o. n. a. r. 4 e n.
- n. 0 0 e. r s. o. ss.
- n.. n. 0 0 e. s. a. n.
C060 CI
- n.. o. n. r + 0 C,
- e. a.. n. o. n. e f o. n.
- n.. n o. n. r a. n. n. n.. o. n. o. r + n. n.
ZN65
- CI
- 0.000Ef00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
- SRet
- CI
- 0 000E+00 : 0.000Ef00 : 0.000Ef00 : 0.000E+00 :
! SR90 CI
- 0.000Ef00 : 0.000Ef00 : 0.000Ef00 : 0.000E+00 :
ZR95 CI
- 0.000E400 : 0.000E+00 0.000E+00 : 0.000Ef00 :
SP124
- CI
! 0.000Ef00 : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 :
CC134 CI
! 0.000E400 : 0.000C+00 : 0.000E'00 : 0.000E+00 :
- CS136
- CI
- 0.000Ef00 : 0.000EfC0 l 0.00CE400 1 0.000E+00 i C E.13 'e CI
^ o. ^. n. [ 4 M.. ' C. ^. ^. ^. E '. ^. ^. ' ^ o n. ^. r f ^. ^.
^. ^. ^. ^. r a. n. n.
ENTER C C ] TO CRACE SCREEN AND CONTINUE :
C
m-i Fs A e e
- n. r - e.
SITE: LIMERICt.
UNIT: U:
1 USER: MART l
DATE: 00/25/98 12:51 E F F' U F H T.4 H D W.^.C. T r p.i c. o n. a s.i.
- p. _e.o n. p. v.
.v GASEOUS EFFLUEHfS FOR RELEASE POINT!
1 NORTH STACK CONTINUOUS MODE PATCH MOPE NUCLIPES
- UNITS : QUARTER QUARTER QUARTER
- QUARTER
? RELEASED :
1 2
1 2
- 3. PARTICULATE! 'CONTL)
It A 14 n.
I 0. 0 0 n. r f a. n..
- n. 0 o. n. r a. n. n.
- 6.. o. n. n..r 4. n e.
- n.. n. e. n. r a. n. n.
C.r 141
- e..s
- 0. v. n..e f n. n,
- n.. n. n. e c 4. n. n.
- e.. n. a. 0.r. n. o.
- n.. e. n. n. : s. n. a.
nn E144
- e.,
A. 0o.0e4.e.0 n..a.n.n..ra.n.n.
- n.. n. 0 o. r 4. n. n.
- n.. n. e. e. : 4. n. n.
g u.s. HT.
C.'
O. '. n 's.r
^w'
^ ^^^C466
'. O. ^. ^. n..r
- C ^. '. ^.. ^. ^. !. ' + ^. ^.
l TOTAL FOR :
F rF t 0 c, CI
- e.. e. n. <. e.. n. r.n...s a. n e. 2...,-
- n.. n. e. a..r i. 0 e..
A.. n. n. n. e r. e. n.
.. e
( r..,,, r,g L N J e.c. r...f..
, Tvn
- s. e. e. c..c. e t o.) i <
- e. n.o. #,. hm..e e.
tae.c
..t
.e n. e
- s. o_ r.
e.
s.
S I T E. i w...e r. t e..r.
UNIT: UI USED: NAPT DATE! 09/25/99 12:51 EFFLUrNT 6HD WASTE DI5F056L REPORT GASEOUS EFFLUEMIS FOR RELEASE POINT! 2 UNIT 1 - SOUTH STACK CONTINUOUS t:0DE PATCH MOIe
! NUCLIDE!
UNITS : QUARTER
- QUARTER OU/:RTER OVARTER
- RELEASED 1
2 1
2
- 1. FISSION GASES AR.41 e
=*
+
^
e
+
V. A A. A _r 4. A. A.
- o.. A. A. o..r 4. A. A..
A.. A. A. A. r A. A. A.
A.. A. A. A..r A. A. A.e.
e LJ e
v v e
I.'h*t w M F2
- T 3. ^ A. o..r. t. A. A.
A.. A. A. a..r. g a. r.
A.. A. A. A. c. A. A.
A.. A. A. A r. A. A. A.e.
rA w v e
t'R A. r.M e.
af e
L.
A.
0 A. A. r. A. A. A.
A.. A. n. o..r 4. A. A. i.
O C,AA.r+A.A.
0. A. A. A..r 4. A. A.
s.
h' b' ^ r (4
.T A.. ^ ^ A. F 4 0 A.
A.. A. 6. A. r. 4. A. f 0. A. A..i E 4. A. A.
A.. A A. A. r f A. A.
y.
e Vv v _
I.' r 0 9
- e. *1 A.. A. A. e r. J. r ^
h.
+
e A^6r
, e A. e. 51 t. + A..*
O. A. 0 (. *. 4. A. F.
A. e. A. A. r A. n. n.
A w
s.
y R. m o A.t A.. ^ A. ^. r. J. A. A.
e e
A.. A. q. a r a. A. A.
o,. A. A. r. r 4 A %
s A.. A A. A. r A. A. A.
.. Lv
).
w.
w e
v.
e V
e.
S r. o. r..
t
- e. 4 A.. A. A. a..r 4. A. A.
A.. A. A. A. r 4 6 6 A.. A. A. b.r 4. A. A.
AA A. e v. 6..r 4. A. a n
e 1
e e
e
.~...............-...........
t,p pe r.1 A..A.66..rtio.
^. 0 ^. ^..E. #.
^^^ ^^ '
^......re...
^^^.
^..... e. o. n.
X r. t o..
C.,
A.. A. r> a. r. 4. A. A.
- o.. A. n. a. r. 4. A. 6
- e.. A. 0 0 e. 4. A. A.
A.. A. A. A. r a. n. o.
e
. u
! XE133h CI
- 0.000E400 : 0.000Ef00 : 0.000E+00 : 0.000E+00 :
XE1is
- e..r
- 0. n. C:A. r 2 6, C..
A.. A. A A..r + n. o.
0. 0 n. o. r 4. A. A.
4 A.. A. A. A. r 4. A. A.
e
+
e XE135N CI
- 0.000E+00 : 0.000E+00 0.000Ef00 0.000E+00 :
XE135 Cl
- 0.000Ef00 : 0.395E+01 : 0.000E+00 : 0.000E+00 :
XE137 CI
- 0.000Ef00 : 0.000E+00 1 0.000E+00 : 0.000E+00 :
XE130 CI
- 0.000E+00 : 0.000Ef00 : 0.000E+00 : 0.000Ef00 :
UNIDENT.
CI 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
T0f.it FOR :
PERIOD CI
- 0.000E+00 : 0.3E!E401 : 0.000E+00 : 0.000.e+00 :
(AF0VE)
ENTEP [ C ] TO ERASE SCREEN AND CONTINUE :
C
c#... e r.
- e. c e.
SITE! LIMERIC UNIT: UI USER: MART D A T E. e B / o r. / e. B.,.6. r,
. s E F.F LILr t.8 T M.' i ". iY2 T r r,I e. e n..:.e..
.p e r n. e t.
GASEOUS EFFLUENTS FOR RELEASE POIMT! 2 UNIT 1 - SOUTH STACE CONTINUOUS MODE PATCH MODE NUCLIDES
- UNITS : OVARTER
- GUARTER OVARTER :
006RTER RELEASED 2
1 l
2
- 2. 10 DINES
.e., !
n!
- n.. n. n. e r f o. n,
- o..., r. o..r. n. 4 A. n. 0 n. e 4. n. n.
- n.. e., n. n. r. i. e. n.
w s
I.3,
- e. I
- n. 0 a. n. t f,) n.
- 0. n. n. a. r + n. e A.. n. o. n. r 4. n. n.
A.. o. n. o. r t. n. n.
e TOTAL FOR :
PcR.I0Ir CI 0, n. o n. e t. n a.
0. m. e. e. e _ o. 4
- n.. n. o. n..r a. n. n.n.. n. o. n. e t. o. n.
s.
l (ADOVE)
- 3. PARTICULATES c4
- e..s
- n.. e. r. n..r a. n. n.n.. s. n. e. r 4. n. e.
- n.. n. o. n. r a. n. e. n.. a. n. e. r 4. a. ?.
e 4
- r. E rs
- r. '
- n.. a.- 0 0.r a ^, <
e,. a. n. ^..r 4 n. e
^
- a. n. n. r a. n. e.
- e. n.. n. e. e. r e. n. a.
nues
- e. i
- n.. n. e. a. r 16 8
- n.. r., e. n. e 4 n. e.
9. n. a. r..r a. n. n.
e e n. n. r a. r. e.
s F C e n,
- c..e 0. n 0 n..e 4. 6. e.
n. n. n. e. r 4. e. n.
. n.. n. 0 a..r t. n. a.
- n.. n. o. n. r a. n. n.
s s
C050
- CI
- 0.000E+00 : 0.000Ef00 l 0.000E+00 ; 0.000Ef00 :
l C060 C.e
. C. 0. n. n. r a. n n.
- n.. n. 0 n, E A. n. n.
- n. 0 n. o. r 4. a. n.
- n.. e. n. n. r 4. n. n.
.s l
ZN65 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Et00 :
SR09
- CI
- 0.000E400 : 0.000E+00 : 0.000Ef00 : 0.000E+00 :
SR90
- CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 1 0.000E+00 ;
2R95
- CI
! 0.000E+00 : 0.000E+00 : 0.000Ef00 ! 0.000Ef00 :
! SP!24 CI
- 0.000E+00 : 0.000E+00 ! 0.000E+00 : 0.000Ef00 :
- CC134 CI
- 0.000Ef00 0 000Ef00 1 0.000E+00 : 0.000E+00 :
- CS!36
- CI
- 0.000E+00 : 0.000Ef00 : 0.000Ef00 : 0.000E400 :
Ldl./
e V.
0.
4..
0..
0..v.
. 0. Cj
..I ENTER [ C] TO ERAEC SCREEN AND CONTINUE :
C
1
-. r e.
5 F..e C.
C' r I v..e. L., M e F, C.v.
' UNIT: U1 USER! MART 2
, w,c a 1.3. t o.
u A T o-..
2
.,, e s.
E. F.C ' U f N T. A.ii*i LI./ a T r ' f.. ? A C n,)i
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6 L.
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4
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- i. 0 i)./. T T r t.
A l.i A. F. T r. t.
+
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.m L.. L E A e. EI, 1
1
- 3. PARTICULATEe (CONTD)
I Al as 0 A
- ^*
- 0. A. 0 o..r f A. 6 A.. v^ ^. A. f. f A r,.
A 0 A. A. Ff C> A.
A.. A. A. A..C 4. A. A.'.
e L. 4 e
u e
P { 4' 4.9 a.t V. ^.. /. F A. A. ?
.f A.. A. A. A. r. 4. A. A.'.
A.. A. 6. A. C 4. A. A.
^
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A. e. A. A. r 4. A. f L
e w
e
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(. 9 V. A. A. o. r A. p p e
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- n.. c. A. A..r a. 0 A.
A.. A. A. A. r 4. A. A.
A.. A. A. A. r 2 4 6 A.. A. A. A. r 4. A. r TOTAi. F o..c.
p r g. I C. I,
- r..i
- e.. n. A. A..e n.,,
A..
.n. o..r o. A.
- c. n. n. o..e t. A. n.
- e. A. o. n.. t. r e.
i.
(A00VC) t E N T.r p.
.r C ' 7 0 r. p.p.. e. v...e r. ps, u t.
- r. o.. m...n. e t
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t
C A C. r.
7,
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a ! T. E. L.T.> r e. T P. V..
O UNIT! UI USER: MART DATE: CE/25/8e 12:53 Er. FLUrfle.
.f.u. D W.A. e. T e.r
- e. c.n. c. ni R. r.e. n..c T 4
GASEOUS EFFLUENTS.e0R RELE6SE FOIMT! 4 H0T MAINTEN^NCE SHOP CONTINUOUS MODE PATCH MODE NUCLIDES : UNITS : GUARTER : GUARTER CUARTER :
QUARTER 8 RELEASED :
1 2
1 2
'.1.
FIS$10N GASEC fJ e 0 A. A. r i A. A.
A.. A. A, A. r. J. A. 6 A.. A. A. A. r 4. A. A.
A.. A. A. A. r 4. A. A.
AR.41 P. I A, e. A. A. r i A. n.
V. A. A A. E 4. A. A.
A.. A. A A r. 4 6. A.
. ^
h' S *n U,t be.
f.' T V e. A. A. F + A. A.
A s
^ A s.
e b b. 0 r.k.
- e..t v. A. A, A. r i A. 0.
A.. v^ A. A. r 4 A. 0 *. C,. A. A. A. C. 4. A. A.
A.. A. A. A. r.1. A. A.
^
r s e
b.e. U.
Ct r/. A. 0 A.r. f s,)
C.
A. A. A. r 4 A. A.
A.. A. A. A. r 4. A. A.
( 0 A.A. C.4. A. r.
ar A
4 e
- r.. A. S A. E Y A. n.
A.. A. A. A. r 4. A. A.
A.. A. A. A. r. 4. r. A.
A.. A. A. A t 4 6. ^.
v f e...
- e. *
.i A
A.. V.A,r1 8A.
A.. A. A. A. r a. A. A.
b'e p A.
- e. '
A.
- 4. ) o. f f A. A.
e. A. r. c. i A. ?.
A
^6 t.
a.
1 s
e b.p C n,
- f. I
(,. A. A. e r a r. e, A.. A. 6. A. r t A. A.
A.. A. h. o. r a..s.*
A.. A. =, f> r 4. A. S.
s s_
F. f O A<
- r. t k. A. A. A..r 4 A, A.
A. e (, h A. r 4. A. A.
A., A. A. A. r 4. A. A.
A.. A. A. A. f 4. A. A.
A u
V. A A. A.r. t A. A.
A.. A. A. A..r. 4 A. A.
A.. A. A. A..r 4. A. A A.. A A, A r a. r. o.
^
,X "
- 1. 9 M f5 L
v s e
l XE133M CI
- 0.000E400 : 0.000E400 0.000E+00 l 0.000E+00
- XE13, CI 0 0 ^. A. r + n. o.
A.. A. r. A. r 4. A. A.
A.. A. A. A. r 4. A. 0 A.. A. A. A. r t. A. A.
XE135M CI
- 0.000Ef00 : 0.000E+00 : 0.C00E+00 : 0.000E+00 :
XE135 CI
- 0.000E+00 : 0.000E+00 : 0.000Ef00 1 0.000E+00 :
XE137 CI
- 0.000E+00 : 0.000Ef00 : 0.000E+00 ! 0.000F+00 :
1 XE130
- CI
- 0.000E+00 ! 0.000E+00 : 0.000E+00 : 0.000Et00 :
UNIDENT.
CI
- 0.000Ef00 1 0.000E+00 : 0.000E+00 : 0.000E+00 :
l TOTAL FOR :
. e. A. A. 0 e. 4. n A.
A.. A. A. A..r t. A. A.
F.c R. I O r.,
CI
- 0. 0 0 A. r + n, n.
- 0. A A. C. e + n. o.
. s s
s (A!OVE)
ENTER C C ] TO ERASE SCREEN AND EONTINUE :
C l.
O
.c s.. A. r
- o. o r.
c.
SITE: LIMERICM UNIT: U1 USER: nAni l
BATE! 08/25/CE 12:53 EFFLUENT AND L'ASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE PO!HT:
4 HOT MAINTENANCE SHOP CONTINU0VE MODE PATCH MODE
- NUCLIDES : UNITS : QUARTER
- OVARTER QUARTER : GUARTER x._.n, c3e.Et3 1
1
.A
- 2. 10 DINES 1131
- CI
- 0.000E400 : 0.000E400 : 0.000E+00 : 0.000E+00 :
1117 CI 0. A. o. 0 r +. t.s.
A.. C. 6. o. r + A. A.
A.
0 A. A..r 4 A. A.
r.,. A. A. A. r 4. A. A.
s TOTAL TOR :
F# F..f o. r (2
0. A. A. 6..r 4. s.67 A.. ^ A. o..r t n. o.
A.. A. A. 6..r + S. A.
A.. A. A. A. T 4. A. A.
c v
( A [, n. >)[.s
- 3. PARTICULATES C14 C.f 0. A 0 A. _r 4. t.AA.
A..t. A. r 4.A.A.
%A.
A.. A. A. t _r 4. A. A.
A.. A. A. o..r 4. A. "
C R' 9. !
CI
- 6.. A. 0 0 r i A. A.
A.. O. A. A. r + ^ ^..,.
A.. A. A. r. J 4. A. A.
A.. A. A. A. r. 4. A. A.
Mi r 4 e_ I
- n.. o. 0.r 4. A. A.
A.. A. A. a. r 4. A. A.
A.. n. 0 n,r 4. A.,
A.. A. A. o. r. 4. A. A.
as FE!9
- CI
- 0.000E+00 : 0.000s..O : 0.000E+00 : 0.000E+00 :
C050
- CI
- 0.000Ef00 : 0.000EiOC ! 0.000E+00 ! 0.000F+00 :
C060
.I e.,. 0 A. e. r i C,C..
- e.. A. A. o. r 4. 0 A.
- r.. s A A. r + A. A, A.. A. A. A..r 4. A. A.
ZN65
- CI
- 0.000Ef00 : 0.000E+00 : 0.000Ef00 : 0.000E+00 :
! SR89
- CI
- 0.000Ef00 : 0.000Ef00 0.000E+00 1 0.000Ef00 :
- CR90 CI
- 0.000Ef00 : 0.000Ef00 : 0.000Ef00 : 0.000E+00 :
- ZR95
- CI
- 0.000Ef00 : 0.000Ef00 : 0.000Ef00 1 0.000Ef00 :
SB124 CI
! 0.000Ef00 : 0.000Ef00 0.000Ef00 : 0.000F+00 :
- CS!?4
- CI
- 0.000Ef00 : 0.000E+00 : 0.000E+00 1 0.000E+00 :
! CS136 CI
- 0 000E400 : 0.000E+00 : 0.000E+00 0.000f +00 :
C0137 CI
- 0.000E40? : 0.000E400 : 0.000E400 : 0.000E400 '
ENTER C C 3 TO ERA!E CCREEN AND CONTINUE :
C
FACE o Or e SITE: LIMERICt:
UNIT: U1 USER: MART DATE: 06/25/08 12:54 EFFLUENT AND WASTE DISFOSAL REPORT
-GASEOUS EFFLUENTS FOR RELEASE POIHi!
i HOT MAINTENAPCE SHOP CONTINUOUS NODE PATCH MODE i NUCLIDES
- UNITS !
GUARTER l
QUARTER OUARTER GUARTER :
RELEASED 1
2 1
2
- 3. PARTICULATES (CONTD)
BA140
- CI
- 0.000Ef00 : 0.000Ef00 0.000Ef00 : 0.000Ff00 :
- CE141
- CI 0 000Ef00 0.000E400 : 0.000Ef00 0.000Ef00 :
- Celi 4
- CI
! 0.000Ef00 : 0.000E400 : 0.000l+00 : 0.000E+00 LiHIIirH T.
CI
- n. 0 n. o..e t o n.
- n.. o. n. n. e f n. n,.
- n.. o. n. n. e. 4. 0. 6.
- n.. o. n. n..e A. n n.
TOTAL FOR :
ptrIoIi cI
- o.. o. n. ^. E + o. ^. ' ^ ^ ^ ^ r 4. ^. ^. ' ^ ^^^r'A.o.
- ^ ^^^^^ *
( A D 0'.'E )
ENTER C C 3 f0 ERASE SCREEN A?!D COMTINUE C
l I
l i
l i
r' IIo TABLES B.
SOLID WASTE DISPOSITION REPORT January 1, 1988 to June 30, 1988 I
i f
t i
l l
9 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 01/01/88 TO 06/30/88 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) l 1 TVPE OF WASTE l
UNIT d 6-MONTH l EST. TOTAL l PERIOD ERROR. %
l l
- a. Spent resins, ft,lter sludges, evaporator bottoms, etc.
m3 2.27E+2 l
l Cl 7.8SE+2-1.94E+1 l
l
- b. Dry compressible waste, contam~nated equipment. etc.
m3 3.50E+2 l-l C1 7.85E+0
~ 4.66E+1 l
l
- c. Irradiated components, control rods, etc.
m3 0.00E+0 l
l C1 0.00E+0 0.00E+0 L
l d.
Other (describe) l m3 0.00E+0
[
Ci H 0.00E+0 O.00E+0 b
- 2. ESTIMATE OF CAJOR NUCLIOE COMPOSITION (by typ3 of wOcto) l TYPE A l
TYPE 8 h
TYPE C lj TYPE O l
l --
l:
ISOTOPE ACTIVITY l PER CENT ACTIVITY l PER CENT ACTIVITY I PER CENT ACTIVITY l PER CENT l
~
l (C1)
(Cl)
(Ci)
(C1) l l
1 l
l H3 H
8.09E-1 1 1.03E-1 [
4.02E+0 l 5.12E+1 l l
l l
l l
C14 l
1.78E+O l 2.27E-1 l 7.52E-3 l 9.59E-2 l l
l l
l i
CR51 l
2.28E+2 l 2.91E+1 l 5.82E-1 l 7.42E+0 l l
l l
l l
MN54 l
8.06E+0 l 1.03E+0 l 5.82E-2 l 7.04E-1 l l
l
'l l
t 1
FESS I
3.10E+1 l 3.94E+0 l 3.99E-1 l 5.09E+0-l l
l l
l l
C058 l
5.35E+1 l 6.82E+0 l 2.58E-1 l 3.29E+0 l l
l 0
l 1
FE59 l
2.68E-1 1 3.41E-2 l l
l l
l H
l l
l NI59 l
l l
l l
l l
l l
l CO60 l
3.27E+1 1 4.16E+O l 4.26E-1 l 5.43E+0 l l
l l
I NI63 l
3.83E-1 l 4.87E-2 l 4.14E-4 l 5.28E-3 l l
l l
l l
ZN65 l
3.93E+2 l 5.01E+1 l 2.09E+0 l 2.66E+1 l l
l l
l N894 l
l l
1 l
l l
l l
SR90 1
1.27E-1 l 1.62E-2 l 1.20E-3 l 1.53E-2 l l
l l
l N895 l
1.16E+1 !
1.47E+O l 8.52E-4 l 1.09E-2 l l
l l
l l
ZR95 l
6.29E+O l 8.01E-1 1 4.78E-3 l 6.09E-2 l l
l l
l 1
TC99 l
6.73E-3 l 8.57E-4 l l
l l
l l
l RU103 l
1.35E+O l 1.72E-1 l l
l l
l l
'q
]
l RU106 l
7.97E+O l 1.01E+O I l
l l
l l
l I
I129 I
i l
1 I
I I
i 1
1 1131 l
5.01E+O l 6.38E-1 l l
l l
j i
l 4
l CS134 l
1.29E+O l 1.65E-1 l l
l l
l l
l i
l CS135 l
l l
l l
l l
l H
1 CS136 l
l l
l 1
l 1
1 l
CS137 l
1.40E+0 l 1.78E-1 l l
l l
l l
l BA140 l
9.90E-2 l 1.26E-2 l l
l l
l
]
l CE141 l
5.67E-4 l 7.22E-5 l l
l l
l l
l CE144 l
l l
l l
l l
l l
PU239 l
3.25E-5 l 4.14E-6 l l
l l
l l
l l
PU241 l
6.59E-3 l 8.39E-4 l 1.90E-5 l 2.42E-4 l 1
l l
D l
AM241 l
7.OOE-4 l 8.91E-5 l l
l l
l l
l l
AM243 l
l
[
l l
l l
l l
l CM242 l
l l
l l
l l
l l
CM243 1
5.22E-4 l 6.65E-5 l l
l l
l l
3.
SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF TRANSPORTATION OESTINATION 31 Truck CNSI, Barnwell, SC 5
Truck CNSI. Chanahon. IL 2
Truck Ouadrex, Oak Ridge, TN
III.
ATTACHMENTS i
A.
SUPPLEMENTAL INFORMATION Facility: Limerick Generating Station - Unit 1 Licanse:
NPF-39 1.
Regulatory Limits (Technical Specification Limits)
A.
Noble Gases:
1 5 500 mRems/Yr - total body "instantaneous" limits per 5 3000 mRems/yr - skin Tech Spec 3.11.2.1 2
5 5 mRads - air gamma quarterly air dose limits per 5 10 mRads - air beta Tech Spec. 3.11.2.2 3
5 10 mRads - air gamma
- yearly air dose limits per 5 20 mRads - air beta Tech Spec. 3.11.2.2 B.
Iodines, tritium, particulates with half life > 8 days:
- 1. $ 1500 mRems/yr - any organ "instantaneous ~' limits per (inhalation path)
Tech Spec. 3.11.2.1 2
5 7.5 mRems - any organ quarterly dose limits per Tech. Spec. 3.11.2.3 3
5 15 mRems - any organ yearly dose limits per Tech. Spec. 3.11.2.3 C.
Liquid Effluents:
- 1. Concentration < 10CFR20 "instantaneous" limits per Appendix B, Ta51e II, Col. 2 Tech. Spec. 3.11.1.1
- 2. $ 1.5 mRems - total body quarterly dose limits per 5 5 mRems - any organ Tech. Spec. 3.11.1.2 3
5 3 mRems - total body yearly dose limits per 5 10 mRems - any organ Tech. Spec. 3.11.1.2 2.
M,aximum Permissible concentrations Per LGS Technical Specification 3.11.1.1, MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.
The MPCs specified in 10CPR20, Appendix B, Table II, Column 2 for identified nuclides are used to calculate permissible release rates and concentrations for liquid releases.
3.
Average Energy E determination based on gaseous effluent releases for the report period is J.224 MeV.
40 Measurements and Approximations of Total Radioactivity A.
Pission and Activation Gases The method used is the Canberra Series 90 Counting System; GS - Gas Marinelli.
B.
Iodine:
The method used is the Canberra Series 90 Counting System; 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 Gystem and the Radwaste Liquid Discharge Pre-Release Method with a 3.5 liter Marinelli.
S.
Batch Releases A.
Liquid Q1 Q2
- of Datch Releases:
0 0
Total Time period for batch releases, 0
0 Maximum time period for a batch release, O
O Average time period for batch release, 0
0 Minimum time period for a batch release, 0
0 Average stream flow (Schuylkill River) during periods of release of effluents 1.07E+06 1.0E+06 into a flowing stream, gpm
= Minutes
B.
Gaseous 01 02
- of Batch Releases:
0 0
Total Time period for batch releases, O
O Maximum time period for a batch release, 0
0 Average time period for batch release, 0
0 Minimum time period for a batch release, 0
0 0 = Minutes 6.
Abnormal Releases A.
Liquid None B.
Gaseous None 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 Citizens Home Water Company
=
Receptor 3 = Phoenixville Water Company Receptor 4 = Philadelphia Suburban Water Company Receptor S = City of Philadelphia Crew Course l
l E
III.
ATTACHMENTS B.
RESIDUAL HEAT REMOVAL (RHR) SERVICE WATER RADIATION MONITOR FAILURES During 1987, an investigation of numerous RHR Service Water Radiation Monitor low sample flow alarms revealed the accumulation of corrosive materials on the walls of the sample piping.
Inoperability of the A, B, and C monitors and subsequent Corrective Action was discussed in Semi-Annual Effluent Release Report No.
7.
l During this report period, the "D" monitor was modified to l
incorporate new pipe material (from carbon steel to stainless i
steel) and reduced bendings in the pipe line (to facilitate sample i
flushing).
Post-Modification Testing has concluded that higher sample flow rates are achievable with the improved sample pipe design.
At the present time, the "D" monitor has been returned to service.
Modification to the "C" monitor is in progress.
Modification to the "A" and "B" monitors, which are currently out-of-service due to the low sample flow alarms, is scheduled for completion prior to the Second Refueling Outage.
The Technical Specification requirement to sample RHR Service Water every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> continues to be observed when necessary.
1
1 i
III.
ATTACHMENTS C.
PROCESS CONTROL PROGRAM (PCP), REVISION 3, 4,
5, 6, and 7 Revision 3 of the PCP incorporated provisions for use of vendor services, to expand the discussion concerning Management review and approval of the document, and to describe the Administrative controls of the Program.
The PCP was revised four successive times
(#4-#7) to provide the ability to utilize "vendor" dewatering services.
Each revision incorporated vendor topical reports and licensee-approved vendor procedures.
A diagram of the Solid Radwaste Treatment System was included in Revision 7.
A copy of each revision and descriptions for all changes is included under separate cover.
~
PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-352 SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 8 JANUARY 1, 1988 THROUGH JUNE 30, 1988 Process Control Program Revirxions 3, 4,
5, 6,
and 7 Subtit rd to The United States Nuclear Regulatory Commission Pursuant to Facility Operating License NPF-39 Preparation Directed by:
G.
M.
Leitch, Vice President I
Limerick Generating Station G-ii
/)$
. I1 * ' ' {m m..
M. J.- Mc Cormick, Plant Manager
PROCESS CONTROL PP' NRM (PCP), REVISIONS 3, 4,
5, 6, and 7 Revision 3 of the PCP 'ncorporated provisions for use of vendor services, to expand the discussion cor.erning Management review and approval of the document, and to describe the Administrative controls of the Program.
The PCP was revised four successive times
(#4-87) tc provide the ability to utilize "vendor" dewatering services.
Each rev3? ion incorporated vendor topical reports and licensee-approved vei. dor procedures.
A diagram or the Solid Radwaste Treatment System was included in Revision 7.
A copy of 2
.;ach revision and descriptions for all changes is included within.
a E
A
'Q;.
/I
+
1
?_ _
CIIANGES TO TitC PCP, REV 3 IPrgelSectionI From I
I I
l To l
Re'ison i
l l
g-1 I
ITable of Contents l
gRemoved - procedu n i fermat change g
i I
I I
l l
1 l 1.0 IProvide guidance and boundary
[This program provides guidance and Editorial change g
l l
l Iconditivas for preparation
[ boundary conditions for l
l l
l
[
l lpreparation...
[
g i
I I
I i
l g
(
l I l 3,4 l Low Level Maste Licensing Branch l Low Level Waste Licensing Branch l Removed revision number and date.
g l
I iTechr.ical Position on Radioactive
[ Technical Position on Radioactive l Intend to maintain references as I
l IWaste Classification. Rev. 0 (5/83) Faste Classification.
[ current.
g i
i l
l l
l l
1 l 3.5 iLow Leve.
aste Licensing Brrnch l Low Level Waste Licensing Branch l Removed revision number and date, g
l l
ITechnical Position on Waste Form,
[rechnical Position on Waste Form l Intend to maintain references as g
I l
lRev. O s5/83) l l current.
l l
1 1
I I
l l
l I l l
p!merick Generating Station l Reference added g
l l
l
[rechnical Spe ification 3/4.11.3 l
l l
I I
I I
i l
i l
l 1 13.6 IBurial Site Criteria for Barnwell ph rnwell Waste ;tanagement FacilityjRevised to refic t proper name of g
l l
lS.C.
dated 1/4/82 pire Dinosal Criteria l document.
g I
I I
I t
i i
1 l 3.7 l South Catolina Department of licalth pouth Carolina Department of
[ Removed amendment number.
Intend tog l
l land Environmental Control llesith and Environmental Control l:naintain references as current.
g i
i IRadioactive Material License No. 097 pladioactive Material License 097 l
g I
I l Amendment No. 41 (Barnwell Facility) l l
g i
l l
l l
l g
f I
I I 3.9 15 tate of Washington Radioactive litate of Washington Radioact.ive
[ Removed amendment number.
Intend tog l
l hterials License No. WN-1019-2, Staterials Licenne No. WN-I-019-2 paintain references as current.
g i
I IAmendaent No. 15 (Richland Site) l l
l l
l l
l 1 14.0 kJPERATING ORGANIZATION FENERAL
'[To provide a section discussing the g
'Section deleted bectionadded I'" **
I l
l l
[
[ review and approval requirements for g I
I I
l
[PCP revisions, and the requirements l l
l l
l jfor use of venoor services.
g i
l I
l l
l l
I I
I l
I 2 15.0
!:'ROCESSING IMPLEMENTATION
[Ilt's change l
I I
I I
l 2 15.1 Igaste Types
}/aste Straams pditorial change g
i l
l l
l
CIIM:GES TO TIIE PCP, REV 3 IP_D9glSectionl From l
To l
Reason l
l l2 f5.1 lCondersaceFilter/Demineraliter I ondensate Filter /Demineralizer l
[
C l
g g
g Sludge Sludge l
Editorial change, addition of l
I e contaminated vaste product a.
The vasta product generated by the Th g nerated by the backwash of the barbon overlay as a media l
g g
jbackwashofthecondensatefilter l
demineralizers
! condensate filter demineralizers I l
Iconsistiug of contaminated l
l b.
Sludge consiste of p
- ered ion I owdered ion exchange rasins at l
[
g
!p exchange resins at varying degrees varying degrees of exhaustion.
l l
forexhaustion, fibrous filter media Ifibrous filter media, carbon l
l g
g j and small concentrations of various loverlay material, and strall l
l g
g gsolids and corrusion products Iconcentrations of various solids,I l
Iactivated and non-activated and l
l Icorroston products l
2 5.1.2 Waste Sludge Waste Sludge I
!The contaminated waste prodect l Editorial change, addition of carbon a.
The waste product generated by the backlash of the liquid radwaste
! generated by the backwash of the 'Ioverlay as a media
[
j' g
g and fuel pool filters and liquid radwante and fuel pool l
l g
g g
g g
g emineralizers filters and demineralizers i
l d
consisting of contaminated I
l g
g g
g gb.
g Sludge consists of powdered ion powdered ion exchange resias and l l
g g
gexchange resins and bead resins at bead resins at varying degree of I l
l l
gvarying degrees of exhcustion, exhaustion, fibrous filter media,I l
l l
g gfibrous filter media (nd small carbon overlay matarrial and small l l
l g
g gconcentrations of various salids concentrations of various solids l l
l g
g gand corrosion producca and corrosion products l
2 5.1.3 Recctor Water Clen.nup Filter /
Reactor Water Cleanup Filter /
l l
l gDemineralizer Sludge Demineralizer Sladge l
l l
I l
l la.
gThe waste product generated by the lA cortaminated waste product
! Editorial change l
g I
l genernted by the backwash of the l
g gbackwash of the liquid rak aste g
I l
and fuel pool filters and reactor water clean:,p filter l
l ldemineralizers g
I I
demineralizers consisting of l
l g
l contaminated powdered ion y
lb.
l Sludge consists of powdered ion exchange resins at varying degrees!
l l
g g
l lexhange resins and bead resins at of exhaustion, fibrous filter I
l media and small concentrations of I I
l l varying degrees of exhaustion, g
fibrous filter media, and small various solids and corrosion l
l concentrations of various solids proaucts and corrosion products
n CIIANGES TO TIIE PCP, REV 3 lPagelSection!
From l
To l
RLason l
l 7
l lfil/ Sludges-WetRadioactive lAdCed additional vasts streta
-[
3 l 5.1.5 l
l g
)
)
g aste Oils consist of non-reclam-g 4
l l
l gable... to be handled by conven-
.g l
l g
gtional devatering techniques.
g i-1 I
l l
l l
3 1 5.2.t lA ccedensate filter-demineralizer lEach condensate filter /demineral-lRe ised to reflect current mode g
g l a.
g l
l gbackwash connir.ts of approxtmately tier backwash consists of approx-of operation.
I g
l l9,000 gallons of slurry with an mately 9,000 gallons of slurry I
l l
gaverage of 280 lbs. (dry vt.) spent ith approximately 315 lbs.
g I
dry wt.) spent resina and crud.
l l
gresins and crud.
g l
l 1
l Backwashes are collected and settled I
uccessive backwashes are collectec To reflect the true capacity of the l
l l b.
g I
In a condensate -Sase seperator.
pnd allowed to settle in a Conden-phase seperator. Detailed informa-l g
l Clarified liquid is deoanted until pate Phase Seperator. As the tion such as level alarms found in l
g l
g l
l l
l214 ft' of settled sludge is pludge nettles the clarified liquic implementing procedures.
j l
l gobtained, as annunciated by high is decanted. The phase s]perator g l
l l
l level clarms LAH-67-133A/B (233A/B) s isolated when approximately g
l l
l lThe tots.1 number of backwashes 60 cubic feet of sludge has g
l l
laccumlated in one phase seperator pecumulated.
g j
l l
[shall be limited to 17.
l g
g I
I I
l l
l l
l d.
[The phase seperator liquid level is lrhe phase seperator liquid level o provide the proper resin slurry g
ased on adjusted phase seperator g
lis adjusted to provide a total l
l l adjusted to provide a total tank pank batch volume of approxtmatelylgcapacity.
Detailed information l
l l
l batch volume of at least 9,500 g
puch as level indicators is found g
l l
l lgc11ons. Total batch level is p.100 gallons.
l l
)nonitoted using L1-67-108A/B (208A/B)l gin implement.ing procedures, g
l s
i I
I i
l l
l 4
l5.2.1 l
tgRemove detail provided by inplement-lg l
lf.
[The soli.is :41utry feed to a centri-rhe solids slurry is fed to a l
l l
[fuge is con. rolled at 18-22 gpm by pentrifuge for dewatering or to ing procedures. Added Externni g
l l
IFVC-67-046A/ B.
phe External Proe essir.g Star ton rocessing System as an alternative g l
l l
[or vendor services processing.
penns of processing.
g f
l 1
l l
l j
4 l5.2.2 l
l l
g i
la.
b backwesh from a radwar,te or fuel fach backwash from a radwaste. c,r (To reficce present slurry vo'umes g
l I
bool filter demineralizer coasists Juel pool filter demineralizer pnd add charcoal over lay as >-
g I
l bf approximately 1,925 gallons of tonsists of approximately 1,500 lf11rer media.
l blurry, with an average of 60 lbs.
y,allons of slurry, with an average l g
l(dry vt.) spent resins and crud.
pf 60 lbs. (dry vt.) spent resins. l g
,f
..,c 3
-s +
. i-
,~
'l f
- k N
p O. EE b
('
CIIANGES TO TIIE PCP, REV 3 IP ISection1 From l
To l
Reason I
I I. age _I I
I i
g-I 4 15.2.2 I
I l
g i
Ia.(Con'tj land crud (may contain charcoal l
g i
I I
I l overlay).
l g
I l
l!
I b.
I A backwash from radwaste desirera-lEach backwash from a radwaste l Add charcoal overlay as a filter l
l l I I
I liz-vr consists of s'pproximately I dcmineralizer concists of approx- { media.
g I
I i 1,50n gallons'of slurry, eith an Iimately 1,500 gallons of slurry, l g
I I average of 2125 lbs. (dry vt.)
Iwith an average of 2.125 lba.
l g
e i
l I spent resins.
's(dry vt.) spent resins (maf l
l 1
I I
lcontain charcoal overlay).
l g
I I
I i
1 i
I 4 15.7.2 I
I l
g J,
lc.
I Backwashes from radwasta filter l Successive backwashes from radwastjeEditorial changes, remove detail il l l
Idemineralizers, radwar?.e demineral-Ifilter demineralizers, redwegte l
l such as level indicaror numbers I
l I izcre, and fuel pool filter deminermR-demineralizers, and fuel gool l vhich are in implementing procedure gl.
I l
l izers are cojiected in the vaste i filter /demineralizers are collectejl l
l l 1
l alud**e tank until approxi.zately lin the Waste Sludge Tank until l
g i l l
I 12,000 gallons of liquid is lapproximately 12,000 gallons of
[
g
! I I
Iaccumuleted. Total batch level is l liquid is accumulsted.
l l
l l
l monitored using LI-66-004 (radwaste l l
l l
l l control room) or L1-f,6-005 (local l
[
g I I I
Ipancl).
l
{
g i
l i
I l
g 1
4 15.2.2 I
I l
l l
l
'd.
l Waste sludge tank contents are IThe Waste Sludge Tank contents
'l Raised the recirculation time to l
l' I
Irecirculated for a minimum of late recirculated for a thinimum ll l l
l30 minutes to afx contents of vessellof 45 minutes to mix contents of Iimprove homogeneity of resin slurry.l I
l I
I Iresulting in a homegerous resin I the vessel, resulting in a homoger(-
l l
l l I
Islurry ranging from 0.5 to 6:
lous resin slurry ranging from I
l l
I I
I I
I(dry vt.) total solids.
10.5 to 6% (dry wt.) total solids. l I
i I.
I The solids slurry feed to a IThe solids is fed to a centrifuge l Remove detail found in implementing l e
I
!centrift.ge is controlled at 18-22 I for dewatering or to the Externa 1 l procedures,% Added external process-l I
I I
I l
lgpm by FvC-67-046A/B.
IProcessing Station for vendor ling station for vendor processing.
l 1pervices processing.
l l
1 I
I I
i g
I I
I i
1 l
8 I
l l
1 1
I l
l 3
I I
I I
CHANGES TO THE PCP, KEV 3 IPcgelsectionl rrom i
To I
neason
'l I
I I
I i
r-l 5 l 5.2.3 l
g g
3 l
l a.
l4 RWCU filter /demineralizer back-ch RWCU filter /demineralizer gRevised to reflect current mode l
l lvach consists of approximately ackwash consists of approximatelygof ope ation.
g l
l l1,100 gallons of slurry with an
,100 gallons of slurry with g
g s
l l
l average of 35 lbs. (dry vt.)
ppproximately 48 lbs. (dry wi.)
g g
l l
l spent resins.
ppent resins and crud.
g g
i l
l l
l l
l b.
l Backwashes are collected and fuccessive backwashes are collectet g
l l
l settles in a phase seperator.
pnd allowed to settle in a phase g
g-l l
[ Clarified liquid is decanted until peperator. As the sludge settles g l
l l100 f t.' of settled sludge is
[the clarified liquid is decanted. g
{
]
l lobtained as annuaciated by high lrhe phase seperator is isolated g
g l
l l level alarms LAH-66-020A/B. The phen approximately 100 cubic feet g y
l l
l total number of backwashes accumu-pr sludge has accumulated.
g g
l l
l lated in one phase seperator shall l
g g
j l
l lbe limited to 65.
l l
g i
I I
l l
l l
ld.
[r* e phase seperstor 11guld level
[he phase seperator liquid level gRemove detail found in implementing g l
l l
l1s adjusted to provide a total ps adjusted to provide a total tanprocedures. Revised to reflect g
l l
l l tank batch volume of at least fatch volume <f approximately gcurrent mode of operation.
g l
i 14.500 gallons. Total batch level
{.,000 gallons.
g g
l l
lis monitored using LI-66-021A/B.
l l
g i
i I
l l
l l
j f.
[The solids slurry feed to the The solids is fed to a centrifuge femove detail found in implementing g l
l kentrifuge is controlled at for dewatering or to the External proceudres. Added external processiy l
l l18-22 gpu by FVC-67-046A/B.
frocessing Station for vendor pration for vendor processing.
g l
l l
perv. ices processing.
l l
l 1
I l
l l
l 6
l5.2.4 pry Active Waste
~
pils/ Sludge peleteddescriptionofdryactive g
- b. Wastes are collected...
Sludges and oils...
yaste processing. Scope of PCp g
l l
[
pntails processing and packaging of g l
l b.
Compressible wastes...
).
Oils and sludges...
pet radioactive waste. DAW falls g
f.Certainwetwsstes
,"nd Eon-compressible vastes...
g g
l l
l l
pludges.
g i
I I
I I
l 1
I l
'l l
l-I l
l l
I I
I I
l l
I I
I i
l
l CHANGES T'1 THE PCP. REV 3
-, l Page Sectton Frone 3,
l I
i
- R j
l 6
5.3.1 The 0.5-6% solids slurries dis-The 0.5-6% solids slurries g emove detail found in implementin j
f cussed in section 5.2 shall be l discussed in section 5.2 are gprocedures.
I 8
l
' fed to a centrifuge at 18-22 gpm.
fed to a centrifuge at a con-g d
I The flow rate will be controlled trolled flow rate for devatering, l
by FVC-67-046A/B. Actual flow g
rate can be vnirified by observing l
g j
g
- FIC-67-046A/B (local).
l l
i i
I I
2 l
l5.3.2 A centrif9te pond setting of 3.0
- Operating variables such as Combined sections 5.3.2 and 5.3.3. l t
shall be use1 for resin dewaterfng. centrifuge pond setting, bearing Remove detail found in implementiny This pond setting phall be main-temperatures, equipment vibra-procedures.
l tained.for all devatering tion, and differential torque l
operations.
.are monitored to ensure optimum g a
centrifuge operation and g
j g
compliance with the free standin 1 g
water criteria.
l l
g g
1 1
l Proper centrifuge operation shall
't l
5.3.3 The dewatered resin is packaged Section combined with 5.3.2.
l l
l Le observed.
(Refer to the in appropriately selected liners Added section discussing attempts l f
l l
sharples centrifuge instruction or II!gh InteRrity Containers
.to minimize void spaces in I
j i
l manual, 8031-M-73-14-5).
Bearing (HIC). Process systems level gcontainer.
I l
temperatures, equipment vibratica probes extending into the linersg g
4 l
and differential torque are alarme.1 or IIIC's ensure that void g
at levels that may adversely affee t spaces within the container l
dewatering performance.
are minimized to the extent l
g
! practical.
l J
g g
l l
I i
l l
I l
7 l 5.3.4 The design of...
g eleted, added to section 5.4.2.b.
D I
i l
l k
7-9l 5.4 Product Cent rol l 10CFR61 Impicmentat f on
' Title Change f
l l
7-9 ! 5.4.1 I
Waste Classification lThis section was revised to provid
=
l more detail concerning the sampling g
4 g
g g
and analysis for scaling factors a(d I the use of the computer program l
J' PAKRAD for waste classification.
j i
3
CHANGES TO THE PCP. CEv 3 i
i
{
lPege'Sectton' From j
l To Reason
.4.2 I
)
7-9 5
j~
Waste Stability I This section added to control the I package waste stability in I
[
g g
g g
g accordance with 10CFR61.56.
}
I I
l l
l
'5.4.3 lSection added concerning package Labeling l
g 7
g l
l l labeling.
g I
I5.4.4 l
l l
I I
Shipment Manifests lSection added concerning use of l
manifests for the transport and l
transfer of radioactive waste.
5.4.5
' Quality Control Program Section added concerning implement l
l l
gation of the quality control pro-g I
l gram and the NRB audit.
g 1
1 I
I I
i l
9
, 5.5 Procedure Control Administrative Control Title Change l
}
I 5.5.1 Processing solid radioactive
, Processing of solid radioactive IAdded requirex nt that personnel l
waste shall be performed by vaste shall be performed by are properly trained.
g g
gqualified operating personnel.
properly trained and qualified j l
operating personnel.
i g
g I
[
l5.5.2 Processing of radioactive spent Processing of radioactive waste gEditorial changes.
l i
l
, resins shall be performed in shall be performed in accordocel t
I
'accordance with approved operating with approved Operating and/or l
l procedures.
l I
Radwaste procedures.
I l
5.5.3 Procedurer shall bq based en Procedures for processing, IEditorial changes added requirement g
g documented test data which demon-containerization, and transport of 5.5.4.
j
{
strate the ability to achieve gof waste shall ensure that g
l l
' acceptable product moisture contenq specific DOT, NRC, and burial g
g l
l as specified by applicable agenclet g
l l
1
. site requirements are satisfied {
g l
1 I
I 5.5.4 IProcedures for processing and Changes to implementing procedur4s Adoed to 5.5.3, replaced with l
I I
Icontainerirstion of wastes shall are reviewed to ensure continuedl requirement to check revisions I
l
{
ensure that specific burial site compliance with the Process to implementing procedures against i
requirements are satisfied.
Control Program.
the PCP.
F_ _ __
)
g CHANGES TO THE PCP. CEV 3 9
IPage Section From i
To Reason I
I l
9
'5.5.5 Sufficient documentation shall begRecords of all data, I
- tests, gEditorial Chan as.
I l
maintained to demonstrate com-analysis results, and records g
o l
l l pliance of solid radwaste pro-of training, inspection, and l
l g
l l
l cessing with the Process Control aud2ts are maintained in l
- Program, l
accordance with plant QA l
l l
l 1
procedures for record retention.1 l
l
! ny changes to the Solid 1
5.5.6 A
g g
Radwaste Process Control Program Deleted, moved to section 4.1.1 I
shall be approved by the Plant l Operations Review Committee (PORC) g i
I g
k l
l 6.0 RECORD l
l ATTAC11MENTS. TA3LES, FICURES l Deleted, previously stated in l
l l
l section 5.5.5 added listing of l
l Waste Classification...
6.1 Process Control Program Iprocedures that implement the I
l l
Implementing Procedures.
IPCP l
1 l
l 1
I l
i l
i I
I i
I I
l I
I l
1 i
I I
1 I
i I
I I
l i
I i
l i
I 1
l I
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I i
h I
I s
I I
i I
1 I
i
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l 9
l j
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' f~ i. ~, r-- s ; <., ; ~:' ~ r *%
LGS - Pcp l t. !n
,1
.1
,..)
J'.
,$'.,j;J & ') i u. ~.: 2.s Rev. 3
.u
.. - 3 Page 1 ef 11 l
T)' j,1 v-,..;[
= xs /1,,;,
,~
3 d'1.V3 N
d 0/- o +'-pr LIMERICK GENERATING s;ATION UNITS 1 AND 2 PHILADELPHIA ELECTRIC COMPANY joLID RADWASTE SYSTE3 PROCESS CONTROL PROGRAM
_[ g APPROVAL:
/
PLANT MANAGER l PORC MEETING:
87-130 DATE:
12/30/87 M
e LGS - PCP Rev. 3 Page 2 of 11 BNS/lmh 1.0 PURPOSE l
This program pro,vides guidance and boundary conditions for preparation of specific proc'edures for processing, sampling, analysis, packaging and shipment of solid radwaste in accordance with State and Federal Regulatory requirements.
2.0 SCOPE This program is applicable to the Limerick Generating Station solid radwaste 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 Branch Technical Position ETSB 11-3, Rev. 2 3.4 Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification 2.5 Low Level Waste Licensing Branch Technical Position on Waste Form l 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 i
l l 3.8 Barnwell Waste Management Facility Site Disposal Criteria 3.9 State of Washington Radioactive Materials License No. NN-1019-2 1 4.0 GENERAL Plant Technical Specification 3/4.11.3 requires the Solid Radwaste Processing System to be used in accordance with a Process Control Program to meet transportation and disposal site requirements.
i LGS - PCP Rev. 3 Page 3 of 11 BWS/imh l
It is the intent of the Process Control Program to provide reasonable assurance of meeting these regulations and to i
demonstrate compliance with 10CFR61 by:
e l
Defining the various waste streams Establishing a set of process parameters that affect solidification and developing operational controls for l
l those parameters.
Implementing a Waste Classifica'.lon System in accordance with 10CFR61 and applicable Regulatory Guidance.
r Providing an appropriate Quality Control Program as required by 10CFR20.311 i
l 4.1 REVIEW, APPROVAL, CHANGES i
4.1.1 Changes to the Process Control Program shall be j
reviewed and approved by the Plant Operations Review Ccmmittee in accordance with Technical Specifications 6.5.1 and 6.13.
I 4.1.2 Changes shall be submitted to the Nuclear Regulatory Commission in the Semi-Annual Radioactive Effluent Release Report for the period in which the change was r
made in accordance with Technical Specification 6.13.
I l 4.2 USE OF VENDOR SERVICES 4.2.1 Vendor services may be used to solidify or dewater any radioactive waste stream provided the services are performed with an acceptable Process Control l
l Program inaccordance with A-99, Control of the i
j Radwaste Process Control Program.
If the vendors's Process Control Program is used the requirements of i
Sections 5.2 and 5.3 of this Process Control Program may not be applicable.
j i
t
[
i t
l i
L L
F 1
LGS - PCP Rev. 3 Page 4 ef 11 BWS/ inh l 5.0 IMPLEMENTATION The Process Control Program shall be implemer.ced by the use of approved plant procedures which provide the step-by-step direction for the operation of the process systems and shipment of waste to a licensed burial site.
A list of plant procedures which implement the Process Control Program is given in Table 6.1.
l 5.1 WASTE STREAMS l
5.1.1 CONDENSATE FILTER /DEMINERALIZER SLUDGE The contaminated waste product generated by the backwash of the condensate filter deminerali=ers 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.
l 5.1.2 WASTE SLUD1E 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 nolids and corrosion products.
l 5.1.3 REACTOR WATER CLEANUP FILTER /DEMINERALIZER SLUDGE A contaminated waste product generated by the backwash of the Reactor Water Cleanup filter deminerali=ers consisting of contaminated powdered ion exchange resins at varying degrees of exhaustion, fibrous filter media, and small concentrations of various solids and corrosion products.
5.1.4 DRY ACTIVE WASTE Dry wastes consists of air filters, miscellaneous paper, rags, etc., from contaminated areas; contaminated clothing, tools, and equipment parts that cannot be effectively decontaminated; and solid laboratory wastes.
&GS - PCP l
Rev. 3
)
Page 5 of 11 BWS/1r.h l
l 5.1.5 OILS / SLUDGES-WET RADIOACTIVE WASTES 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 l
5.2.1 CONDENSATE FILTER /DEMINERALIZER SLUDGE a.
Each condensate filter /demineralizer backwash con =Asts of approximately 9,000 gallons of slurry with approximately 315 lbs (dry we.) spent resins and crud.
b.
Successive backwashes are collected and allowed to settle in a Condensate Phase Separator.
As the sludge settles the clarified liquid is decanted.
The phase separator is isolated when approximately 160 cubic feet of sludge has accumulated.
c.
The settled sludge is allowed to decay in preparation for dewatering while further i
backwashes are routed to alternate phase l
separators.
1 l
d.
The phase separator liquid level is adjusted to provide a total tank batch volume of l
l approximately 8,100 gallons.
e.
Phase separator contents are recirculated for a j
minimum of 30 minutes to mix contents of the vesstl, resulting in a homogenous resin slurry of 61 (dry wt.) or less total solids.
f.
The solids slurry is fed to a Centrifuge for dewatering or to the External Processing Station for vendor services processing.
5. 2 '. 2 WASTE SLUDGE a.
Each backwash from a radwaste or fuel pool filter deminerali:er consists of approximately 1,500 gallons of slurry, with approximately 60 lbs.
(dry wt.) spent resins and crud (may contain charcoal overlay).
LGS - PCP Rev. 3 Page 6 of 11 BWS/lmh l
b.
Each backwash from a radwaste demineralizer consists of approximately 1,500 galler.s of slurry, with an average of 2,125 lbs. (dry wt.)
spent resins (may contain charcoal overity).
l c.
Successive backwashes from radwaste filter deminerall:ers, radwaste deminerali:ers, and fuel pool filter /demineralizers are collected in the Waste Sludge Tank until apprcximately 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, rasulting 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 concentration.
Periodic radwaste demineralizer backwashes will increase the solids level to approximately 3% (dry wt. )
for one bed or 6%(dry wt.) for two beds.
The solids slurry is fed to a centrifuge for e.
dewater3ng or to the External Processing Station for vendor servicea processing.
f.
Waste Sludge Tank contents r 1so be sent to a condensate phase separator fur processing in accordance with Section 5.2.1.
l 5.2.3 REACTOR WATER CLEANUP FILTER /DCMINERALI ER SLUDGE l
a.
Each RWCU filter /demineralizer backwash consists of approximately 1,100 gallons of slurry with approximately 48 lb. (dry vt.) 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.
The phase separator is isolated when approximately 100 cubic feet of sludge has accumulated.
The settled sludge is allowed to decay in c.
l preparation for dewatering, while further backwashes are routed to the alternate phase separator.
LGS - PCP Rev. 3 Page 7 of 11 BWS/1=h d.
The phase separator liquid level is adjusted to provide a total tank batch volume of l
approximately 4000 gallons, e.
Phase separator contents are recirculated for a l
minimum of 30 minutes to mix contents of the vessel, resulting in a' homogeneous resin slurry of 6% (dry wt.) or less total solids.
f.
The solids slurry is fed to a centrifuge for dewatering or to the External Processing Station for vendor services processing.
5.2.4 OILS / SLUDGES a.
Sludges and oils csnerated during operation and maintenance a:e collected in containers in appropriate approved areas throughout the plaat.
The filled and labeled containers are sealed and moved to a controlled-access enclosed area for temporary storage, b.
Oils and sludges can be solidified in appropriate containers by vendor supplied equipment in l
accordance with approved vendor process control procedures.
c.
Certain wet wastes may be allowed to dry and be treated as dry active waste.
l 5.3 DEWATERING PROCESS CONTROL l
l 5.3.1 The 0.5-61 solids slurries discussed in Section 5.2 are fed to a centrifuge at a controlled flow rate for dewatering.
5.3.2 Operating variables such as centrifuge pond setting, bearing temperatures, equipment vibration, and differential torque are monitored to ensure optimum centrifuge operation and compliance with the free standing water criteria.
5.3.3 The dewatered resin is packaged in 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.
=
LGS - PCP Rev. 3 Page 8 of 11 BWS/imh l 5.4 10CFR61 IMPLEMENTATION l
5.4.1 WAETE CLASSIFICATION a.
For dewatered resin, waste classification shall be based upon isotopic analysis and the use of scaling factors for hard to measure isotopes.
During each container fill, a sample of resin is taken and an isotopic analysis is performed.
A detailed analysis is performed on an annual basis by an independent commerical laboratory to identify scaling factors via ST-0-066-731-0, ST-0-066-732-0.
b.
For dry active waste (DAW), waste classification shall be based upon isotopic analysis and the use of scaling factors for Reactor Water Cleanup resin along with DAW dose-to-curie conversion.
c.
For cils/ sludges waste classification shall be based upon isotopic analysis and the use of scaling factors for hard to measure isotopes.
A detailed analysis is performed on each batch to be processed and packaged.
d.
A computerized waste classification and shipping program, PAKRAD, 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.
l S.4.2 WASTE STABILITY l
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 radioactive 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-0-066-733-0.
In addition to the annual verification, the free standing water is determined whenever process changes occur that may significantly alter system dewatering performance.
0 LGS - PCP Rev. 3 Page 9 of 11 BWS/lmh 3.
To prevent accumulation of radiolytically generated ecmbustible gases in greater than Type A radioactive waste packages containing water and/or organic substances, one or more of the following n.easures are taken The container is equipped with a vent to prevent accumulation of such gases.
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 shipment time.
l The cask cavity will be inerted.
4.
Experience has demonstrated that utility waste streams do not contain or generate toxic gases, vapors, or fumes and do not contain hazardous, biological, pathogenic, or infectious materials.
i l
l b.
WASTE STABILITY 1.
Dewatered resin required to be stabilized is packaged in High Integrity Containers (HIC) i that have been certified to meet the i
stability requirements of 10CFR61.56(b).
The HICs are handled and stored in a manner such that their ability to provide stabilization 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.
l 5.4.3 C'ABELLING Each package of waste shall be clearly labelled to identify waste classification.
e
~
LGS - PCP Rev. 3 Page 10 of 11 BWS/lmh l
5.4.4 SHIPMENT MANIFESTS Each waste shipment shall be accompanied by a shipping manifest giving a physical description of the waste, the volume, the radionuclide identity and quantity, the total radioactivity, the principal chemical form, and waste class.
l 5.4.5 QUALITY CONTROL PROGRAM The quality control program consists of required a.
use of plant procedures which implement the Process Control Prograr.and requirements of the Corporate Quality Assuranco Program.
Audits by persoinel 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 by the Nuclear Review Board in accordance with Plant Technical Specification 6.5.2.
l 5.5 ADMINISTRATIVE CONTROL 5.5.1 Processing of solid radioactive waste shall be l
performed by properly trained and qualified operating personnel.
5.5.2 Processing of radioactive waste shall be performed in accordance with approved Operating and/or Radwaste l
procedures.
5.5.3 Procedures for processing, containerization, and transport of waste shall ensure that specific DOT, NRC, and burial site reqvirements are satisfied.
5.5.4 Changes to implementing procedures are reviewed to ensure continued compliance with the Process Control Program.
5.5.5 R'ecords of all data, tests, analysis results, and records of training, inspection, and audits are maintained in accordance with plant QA procedures for 1
record retention.
l l 6.0 ATTACRMENTS, TABLES, PIGURES l 6.1 Table 6.1 Process Control Program Implementing Procedures.
l l
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LGS - PCP Rev. 3 Page 11 of 11 BWS/imh ATTACHMENT 6.1 Process Control Program Implementing Procedures l A-99 Control of the Radwaste Control Program HP-713 General Packaging, Marking and Labeling Requirements for Radioactive Materials for Shipment l HP-722 Determination of Radioactive Quantity l HP-900 General Requirements for Shipping Radioactive Materials l RW-101 Administration of Packaged Radioactive Waste l RW-106 Review of Vendor Topical Report for Waste Processing RW-130 Administrative Controls for PAKRAD - A Packaged Radwaste Management and Tracking Code l RW-220 Exclusive Use Shipment l S66.8.D RWCU Phase Separator Decanting l S66.8.C Centrifuging RWCU Phase Separators l S66.8.F Centrifuging Waste Sludge Tank l S67.8.A Operating the Resin Fill Stations
$67.8.A Equipment Alignmant for Operation of a Solid Radwaste (COL)
Centrifuge l S67.8.B Condensate Phase Separator Decanting l S67.8.G Centrifuging Condensate Phase Separators ST-0-066-731-0 Periodic Sampling and Analysis Program for the Determination of Abundance Factors ST-0-066,-732-0 Periodic Determination and Update of Abundance Factors for Gamma Emitting Isotopes ST-0-066-733-0 Sampling and Analysis of Dewatered Resins for the Determination of Free Standing Liquid
CHANGES T7 THE PCP. IEV 4 i
P_ag e Section From To Rea m i
I I
l 2
3.10 Chen Nuclear Systems. Inc.
l Utilized Chen Nuclear as a l
c I evatering vendor.
l g Topical Report RDS-1000 d
l l
gRadioactive Waste Dewatering l
l l
System RDS-25506-01-NP.
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l 4 l 4.2.2 l
In lieu of the inplant system l Utilized Chem Nuclear as a O
I processing described in la 4evatering vendor.
g g
saction 5.2 and 5.3 the Chem l
l g
g
! uclear Rapid Devatering System l
N g
g RD3-1000 may be utilized. A l
l description of'the Chem NuclearI I
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equipeient and process method may I
l l
be found in Topical Report g
I l
l l RDS-25506-01-NP previously g
I l submitted to the NRC.
l g
I l
12 Attach-RW-430 External Processing Added Chem Nuclear Procedure to l
g g ment Station Resin Transfer and list of implementing procedures.
l l
g 6.1 Dewatering Test using Chem l
l l
l l
Nuclear Equipment and 14-215 l
l l
l (or smaller) liners.
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RW-431 External Processing IAdded Chem Nuclear procedure to l
- "E l
Station Resin Transfer and I list of implementing procedures.
l l
Dewatering Test using Chem I
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l Nuclear Equipment and 21-300 I
l liners.
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3884009370 nav 4
Page 1 of 11 BWS/l h V
'~'* tr C0 LIMERICK GENERATING STATION UNITS 1 AND 2 PHILADELPHIA ELECTRIC COMPANY SOLID RADWASTE SYSTEM PROCESS CONTROL PROGRAM APPROVAL:
PLANT MANAGER PORC MEETING:
FI" #d/
DATE: /-/M/F
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Page 2 of 11
(
BWS/lmh 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.
2.0 SCOPE This program is applicable to the Limerick Generating Station solid radwaste processing system.
3.0 REFERENCES
3.1 49 CFR Parts 170 through 178 3.2 10 CFR Parts 20, 50, G1 and 71 3.3 Standard Review Plan 11.4, Rev. 2, including Branch 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 Unvironmental Control Hadioactive Material License No. 097 3.8 Barnwell Waste Management Facility Site Disposal Criteria 3.9 State of Washington Radioactive Materials Licen No. WN-1019-2 3.10 Chem Nuclear Systems Inc. Topical Report RDS-1000 Radioactive Waste Dewatering System RDS-25506-01-NP 4.0 GENERAL i
Plant Technical Specification 3/4.11.3 requires the Solid l
Radwaste Processing System to be used in accordance with a Process Control Program to meet transportation and disposal site requirements.
Rev. 4 Page 3 of 11 C g\\
BWS/lmh 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 affect solidification and developing operational controls for those parameters.
Implementing a Waste classification System in accordance with 10CFR61 and applicable Regulatory Guidance.
Providing an appropriate Quality Control Program as required by 10CFR20.311 4.1 REVIEW, APPROVAL, CRANGES 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.
4.1.2 Changes shall be submitted to the Nuclear Regulatory Commission in the Semi-Annual Radioactive Effluent Release Report for the period in which the change was made in accordance with Technical Specification 6.13.
4.2 USE OF VENDOR SERVICES 4.2.1 Vendor services may be used to solidify or dewater any radioactive waste stream provided the services are performed with an acceptable Process Control Program inaccordance with A-99, Control of the Radwaste Process Control Program.
If the vendors's Process Control Program is used the requirements of Sections 5.2 and 5.3 of this Process Control Program may not be applicable.
4.2.2 In lieu of the inplant system processing described in Section 5.2 and 5.3 the Chem Nuclear Rapid Dewatering System RDS-1000 may be utilized.
A description of the Chem Nuclear equipment and process method may be found in Topical Report RDS-25506-01-NP previously submitted to the NRC.
Rev. 4 Page 4 of 11
[-
C BWS/imh 5.0 IMPLEMENTATION The Process Control Program shall be implemented by the use of approved plant procecures which provide the step-by-step direction for the operation of the process systems and shipment of waste to a licensed burial site.
A list of plant procedures which implement the Process Control Program is given in Table 6.1.
5.1 WASTE STREAMS 5 1.1 CONDENSATE FILTER /DEMINERALIZER GLUDGE The contaminated waste product generated by the backwash of the condensate filter domineralizers 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 WASTE SLUDGE 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 FILTER /DEMINERALIZER SLUDGE A contaminated waste product generated 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 corrosion products.
2 5.1.4 DRY ACTIVE WASTE I
Dry wantes consists of air filters, miscellaneous paper, rags, etc., from contaminated areast contaminated clothing, tools, and equipment parts that cannot be effectively decontaminated; and solid laboratory wastes.
1
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Page 5 of 11
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BWS/imh Q:?
d 5.1.5 OILS / SLUDGES-WET RADIOACTIVE WASTES 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 a.
Each condensate filter /demineraliser backwash consists of appraximately 9,000 gallons of slurry with approximately 315 lbs (dry wt.) spent resins and crud.
5.
Successive backwashes are collected and allowed to settle in a Condensate Phase Separator.
As the sludge settles the clarified liquid is decanted.
The phase separator is isolated when approximately 160 cubic feet of sludge has accumulated.
c.
The settled sludge is allowed to decay in preparation for dewatering while further backwashes are routed to alternate phase separators.
d.
The phase separator liquid level is adjusted to provide a total tank batch volume of approximately 8,100 gallons.
Phase separator contents are recirculated for a e.
minimum of 30 minutes to mix contents of the vessel, resulting in a homogenous resin slurry of 6% (dry wt.) or less total solids.
f.
The solids slurry is fed to a Centrifuge for dewatering or to the External Processing Station for vendor services processing.
5.2.2 WASTE SLUDGE a.
Each backwash from a radwaste or fuel pool filter domineralizer consists of approximately 1,500 gallons of slurry, with approximately 60 lbs.
(dry wt.) spent resins and crud (may contain charcoal overlay).
'k/['
Rev. 4 s
09 <r/ U L
Page 6 of 11 BWG/lmh b.
Each backwash from a radwaste domineraliser consists of approximately 1,500 gallons of slurry, with an average of 2,125 lbs. (dry wt.)
spent resins (may contain charcoal overlay).
c.
Successive backwashes from radwaste filter domineralizers, radwaste domineralizers, and fuel pool filter /demineralizers are collected in the Maste 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.
I During normal operation the Waste Sludge Tank contains only the radwaste and fuel pool filter domineraliser backwashes which result in a 0.5%
(dry wt.) total solids concentration.
Periodic i
radwaste domineraliser backwashes will increase the solids level to approximately 3% (dry wt.)
for one 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 i
for vendor services processing.
4 f.
Waste Sludge Tank contents may also be sent to a cond'.nsate phase separator for processing in accordance with Section 5.2.J.
5.2.3 REACTOR WATER CLEANUP FILTER /DEMINERALIZER SLUDGE a.
Each RWCU filter /demineralizer backwash consists i
of approximately 1,100 gallons of slurry with approximately 48 lb. (dry wt.) spent resins and crud.
b.
Successive backwashea are collected and allowed to settle in a phase soprator.
As the sludge settles the clarified liquid is decanted.
The phase separator is isolated when approximately 100 cubic feet of sludge has accumulated.
n.
The settled sludge is allowed to decay in i
preparation for dewatering, while further backwashes are routed to the alternate phase separator.
t E
. ', v/
Rev. 4 l
s r. N ' ! A ~' {#
Page 7 of 11 U
BWS/lmh d.
The phase separator liquid level is adjusted to provide a total tank batch volume of approximately 4000 gallons.
e.
Phase separator contents are recirculated for a minimum of 30 minutes to mix contents of the vessel, resulting in a homogeneous resin slurry of 6% (dry wt.) or less total solids.
f.
The solids slurry is fed to a centrifuge for dewatering or to the External Processing Station for vendor services processing.
5.2.4 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-access 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.
5.3 DEWATERING PROCESS CONTROL 5.3.1 The 0.5-6% solids slurries discussed in Section 5.2 l
are fed to a centrifuge at a controlled flow rate for dewatering.
l S.3.2 Operating variables such as centrifuge pond setting, bearing temperatures, equipment vibration, and differential torque ere monitored to ensure optimum centrifuge operation and compliance with the free standing water criteria.
5.3.3 The deuatered resin is packaged in 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, r
2 i
I
,I a. J)'4'[
Rev. 4
, ' W,{/
BWS/imh C
Page 8 of 11 5.4 10CFR61 IMPLEMENTATION 5.4.1 WASTE CLASSIFICATION.
a.
For dewatered resin, waste classification shall be based upon isotopic analysis and the use of scaling factors for hard to measure isotopes.
During each container fill, a sample of resin is taken and an isotopic analysis is performed.
A detailed analysis is performed on an annual basis by an independent commerical laboratory to identify scaling factors via ST-0-066-731-0, ST-0-066-732-0.
aste (DAW), waste classification b.
For dry activt w
shall be based upon isotopic analysis and the use of scaling factors for Reactor Water Cleanup resin along with DAW dose-to-curie conversion.
c.
For oils /siddges waste classification shall be based upon isotopic analysis and the use of scaling factors for hard to measure isotopes.
A detailed analysis is performed on each batch to be processed and packaged.
d.
A computerized waste classification and shipping program, PAKRAD, 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.
5.4.2 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 radioactive 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-0-066-733-0.
In addition to the annual verification, the free standing water is determined whenever process changes occur that may significantly alter system dewatering performance.
, ( 's i f_j)h\\f Rev. 4
'.!c -
Page 9 of 11
^ 'ti> b BWS/Imh 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 shipment 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.
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 stabilization 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.
5.4.3 LABELLING Each package of waste shall be clearly labelled to identify waste classification.
I I
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Rev. 4 V
u Page 10 of 11 BWS/imh 5.4.4 SHIPMENT MANIFESTS Each waste shipment shall be accompanied by a shipping manifest giving a physical description of the waste, the volume, the radionuclide identity and I
quantity, the total radioactivity, the principal chemical form, and waste class.
5.4.5 QUALITY CONTROL PROGRAM t
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 by the Nuclear Review Board in accordance with Plant Technical Specification 6.5.2.
5.5 ADMINISTRATIVE CONTROL 5.5.1 Processing of solid radioactive waste shall be performed by properly trained and qualified operating personnel.
i 5.5.2 Processing of radioactive waste shall be performed in accordance with approved Opsrating and/or Radwaste procedures.
5.5.3 Procedures for processing, containerization, and transport of waste shall ensure that specific DOT, NRC, and burial site requirements are satisfied.
l 5.5.4 Changes to implementing procedures are reviewed to ensure continued compliance with the Process Control Program.
5.5.5 Records of all data, tests, analysis results, and I
I records of training, inspection, and audits are maintained in accordance with plant QA procedures for record retention.
6.0 ATTACHMENTS, TABLES, FIGURES 6.1 Table 6.1 Process Control Program Implementing Procedures.
_r l
J'dl Rev. 4 Page 11 of 11 BWS/lmh ATTACRMENT 6.1 Process Control Program Implementing Procedures A-99 Control of the Radwaste Process Control Program HP-713 General Packaging, Marking and Labeling Requirements for Radioactive Materials for Shipment HP-722 Determination of Radioactive Quantity HP-900 General Requirements for Shipping Radioactive Materials RW-101 Administration of Packaged Radioactive Waste RW-106 Review of Vendor Topical Report for Waste Processing RW-130 Administrative Controls for PAKRAD - A Packaged Radwaste Management and Tracking Code RW-220 Exclusive Use Shipment RW-430 External Processing Station Resin Transfer and Dewatering Test Using Chein Nuclear Equipment and 14-215 (or smaller)
Liners RW-431 External Processing Station Resin Transfer and Dewatering Test Using Chem Nuclear Equipment and 21-300 Liners 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 Fill Stations S67.8.A Equipment Alignment for Operation of a Solid Radwaste (COL)
Centrifuge S67.8.B Condensate Phase Separator Decanting S67.8.G Centrifuging Cor.densate Phase Separators ST-0-066-731-0 Periodic Sampling and Analysis Program for the Determination of Abundance Factors ST-0-066-732-0 Periodic Determination and Update of Abundance Factors for Gamma Emitting Isotopes ST-0-066-733-0 Sampling and Analysis of Dewatered Resins for the Determination of Free Standing Liquid
MM lP gglSzctioni From To l
Re son i
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2 l 3.11 l
l Stock Equipment Co. Topical gUtilized LN Technologies as a i
l-l l
l l Report Quick Dry Process for l dewatering vendor.
g l
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l Dewatering Bead Resin and g
.g l
l l
l Filter Sludge, SRS-003-P Rev. O g
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[ Utilized LN Technologies as a l
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l Processing described in Section gdewatering vendor.
g
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l l5.2 and 5.3 the LN Technologies / g g
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l Stock Equipment Co. equipment and g g
g l process method may be found in l
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lpreviously submitted to the NRC.
g g
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121 Attach-l l
i PW-440 LN Technologies / Stock gadded LN procedure te list of l
l ment l
l 16.1 l
l Equipment Co. Quick Dry Pewateringgimplementing procedures.
g l System Setup and Removal.
g 1
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12l Attach-l l
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PW-441 External Processing StationgAdded LN procedure to list of g
l l 6.1 l
Pesin Transfer and Dewatering Test l implementing procedures.
g g
lJsing LN Technologies / Stock l
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l Fquipment Co. Quick Dry Devateringl g
Hystem.
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JOOJU4MVJV LGS - PCP Rev. 5 Page 1 of 13 BNS/lah
[
LIMERICK GENERATING STATION UNITS 1 AND 2 PRILADELPHIF. ELFCh1C COMPANY SOLID RADNASTE SYSTDI PROCESS CONTROL PROGRAM
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LCS - PCP Rev. 5 Page 2 of 13 BWS/Imh
?
1.0 PURPOSC This prgram provides guidance and boundary conditions for e
I preparation of specific procedures for processing, sampling, analysis, packaging and shipment of solld radweste in accordance with State and rederal Regulatory requirements.
g 2.0 SCOPE This program is applicable to the Limerick Generating I
$tation solid radwaste processing system.
i I
3.0 REFEREMCES I
3.1 49 CPR Parts 170 through 178 l
3.2 10 CTR Parts 20, 50, 61 and 71 i
3.3 Standard Review Plan 11.4, Rev. 2, including Branch l
Technical Posit f on ETCB 11-3, Rev. 2 l
3.4 Low Level Waste Licensing Branch Technical Position on I
Radioactive Waste Classification 3.5 Low Level Waste Licensing Branch Technical Position on Waste Form t
\\
l 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 3.8 Barnwell Waste Management racility Site Disposal Criteria 3.9 State of Washington Radioactive Materials Licen No. WW-1019-2 3.10 Chem Wuclear Systems Inc. Topical Report PDS-1000 Radioactive Waste Dewatering System RDS 'iS06-01-NP 3.11 Stock Equipment Co. Topical Report Quick Ury Process for l
Dewatering Bead Resin and Pilter Sludge, SRS-003-P Rev. 0.
1 p
a 9
LGS - PCP Rev. 5 Page 3 of 13 3WS/Imh 4.0 GENERAL Plant Technical Specification 3/4.11.3 requires the Solid Radweste Processing System to be used in accordance with a i
i Process Control Program te meet transportation and disposal site requirements.
It is the intent of the Process Control Prgram to provide reasonable assurance of meeting the regulations and to demonstrate compilance with 10CrR61 by:
Defining the various waste streams 4
i Establishing a set of process parameters that affect i
solidification and developing operational controls for those parametera.
4 Implementing a Waste Classification System in accordance with 10CFR61 and applicable Regulatorf Guidance.
Providing an appropriate Quality Control Program as l
required by 10CFR20.311 4.1 REVIEW, APPROVAL, CHANGES 4.1.1 Changes to the Process Control Program shall be reviewed and approved by the Plant Operations Review l
Committee in accordance with Technical Specifications l
6.5.1 and 6.13.
t 4.1.2 Changes shall be submitted to the Nuclear Regulatory I
Commission in the Semi-Annual Radioactive Eftluent Release Report for the period in which the change was made in accordance with Technical Sgecification 6.13.
l l
4.2 USE OF VENDOR SERVICES 1
4.1.1 4
Vendor services may be used to solidify or dewater i
any radioactive waste stream provided the services are performed with an acceptable Process Control i
Program inaccordance with A-99, Control of the i
l Radwaste Process Control Program.
If the vendora's 1
Process Control Program is used the requirements of i
Sections 5.2 and 5.3 of this Process Control Program may not be applicable.
i 4.2.2 In lieu of the inplant system ptocessing described in Section.5.2 and 5.3 the Chen Nuclear Rapid Dewatering System RDS-1000 may be utilized.
A description of j
the Chen Nuclear equiptJnt and process method may be
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LCS - PCP Rev. 5 Page 4 of 13 BWS/1mh found in Topical Report RDS-25506-01-NP previously submitted to the NRC.
i l
4.2.3 In lieu of the Inplant System Processing described in Section 5.2 and 5.3 the LN Technologies / Stock Equipment Co. Quick Dry Process may be utilised.
A tescription of the LN Technologies / Stock Equipment Co. equipment and process method may be found in Topical Report SRS-003-P Rev. O, previously submitted to the NRC.
5.0 IRPLitMENTATION r
The Process Control Program shall be implemented by the use
)
of approved plant procedures which provide the step-by-stop direction for the operation of the process systems and shipment of waste to a licensed burial site A list of s
plant procedures which implement the Process Control Program is given in Table 6.1.
4 5.1 NASTE STR:AMS J
5.1.1 CONDENSATE FILTER /DEMINERALIEER SLUDGE The contamina*ed waste product generated by the backwash of the condensate filter de-dneralizers consisting of contaminated powdered ion exchange resins at varying degrees of exhau'stion, fibrous filter media, carbon overlay material, and small s
concentrations of various solids, activated and non-activated corrosion products.
5.1.2 NASTE SLUDGE The contaminated waste product generated by the i
backwash of the liquid radwaste and fuel pool filters and desineralizers consisting of contaminated powdered ion enchange resins and bead resins at s
varying degrees of exhaustion, fibrous filter media, carbon overlay material and small concentrations of various solids and corrosion products.
j 5.1.3 REACTOR WATER CLEANUP FILTER /DEMINERALIEER SLUDGE A contaminated waste product generated by the t
backwash of the Reactor Water Cleanup filter desiners11:ers consisting of contaminated powdered j
lon exchange resins at varying degrees of exhaustion, 4
t 1
LGS - PCP Rev. 5 Page 5 of 13 BWS/Imh fibrous filter media, and small concentrations of various solids and corrotilon products.
,i 3.1.4 DRY ACTIVE WASTE t
Dry wastes conwists of air filters, miscellaneous I
pape r, rag s, etc., from contaminated areas contaminated clothing, tools, and equipment parts that cannot be effectively decontaminated; and solid laboratory wastes.
5.1.5 OILS / SLUDGES-WEr RADIOACTIVE WASTES Oils consist of non-reclainable contaminated clis and I
greare of various grades both synthetic or otherwise in free form or containing various amounts of solid material.
Studge consists et sump dewatering sludges, Ellter sollds, strainer sol /ds and other wet solids too large to be handled by conventional dewatering techniques.
5.2 PROCl!SS DESCRIPTION 5.2.1 CONDENSATE PILTER/DF3tINERALIZER SLUDGE Each condensate filter /decineraliser backwash a.
consists of opproximately 9,000 gallons of elurry with approximately 310 lbs (dry wt.) spent resins at.d crud.
b.
Successive backwashes are collected and allowed
\\
ti scttle in a Condensate Phase Seperator.
As the sludge settles the clarified liquid is decanted.
The phase separator is isolated when approximately 160 cubic feet of sludge has accumulated.
The settled sludge is allowed to decay in c.
preparation for dewatering while further backwashes age routed to alternate phase sepa ra 7.o r s,
d.
The phase separator liquid level is adjusted to provide a total tank batch volume of approximately 8,100 gallones.
e.
Phase neperator contents are recirculated for a minianu of 30 minutes to mix contents of the vessel, resulticg in a homogenous resin slurry of 6% (dry wt.) or less total solids.
Y
)
l Rev. 5 Page 6 of 13 RWS/1mh f.
The solids slurry is fed to a Centrifuge for dewatering or to the External Processing Station for vendor services processing.
5.2.2 WASTE SLUDGE
.l 1
Ea:h backwash from a radwaste or fuel pool filter a.
demineraliser consists of approximately 1,500 I
gallons of slurry, with approximately 60 lbs.
i (dry wt. ) spent resins and crud (may contain charcoal overlay).
I b.
Each backwash f rom a radwaste domineraliser consists of approximatelf 1,500 gallons of slurry, with an average of 2,125 lbs. (dry wt.)
i spent resins (may contain charcoal overlay).
Successive backwashes from radwaste filter c.
i domineralizers, radwaste demineralisers, and fuel pool filter /demineralizers are collected in the Waste Sludge Tank until approximately 12,000 j
gallons of 11guld 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 deelneralizer backwashes which result in a 0.5%
(dry wt.) total solids concent6ation.
Periodic radweste demineraliser backwashes will increase the solids level to approximately 3% (dry wt.)
for one bed or 6%(dry wt.) for two beds.
The solids slurry is fed to a centrifuge for e.
dewatering or to the External Processing Station for vendor services processing.
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 ?!LTER/DEMINERALIEER SLUDGE Each RWCU filter /demineraliser backwash consists a.
of approximately 1,100 gallons of slurry with approximately 48 lb. (dry wt.) spent resins and i
crud.
.-_..,,_----.-.---,v-,-------c--
e
-. - - - - ~,,.
LGS - PCP Rev. 5 Page 8 of 13 BWS/Imh centrifuge operation and compliance with the free standing water criteria.
5.3.3 The dewatered resin is packaged in appropriately selected liners or High Integrity Containers (HIC).
Process system level probes extending into the liners or NICs ensure that vold spaces within the container are miniaised to the extent practical.
j 5.4 10CrR61 IMPLEMENTATION
+
l 5.4.1 WASTE CLASSIFICATION a.
For dewatered resin, waste classification shall be based upon isotopic analysis and the use of scaling factors for hard to measure imotopes.
During each container fill, a sample of resin is taken and an isotopic analysis is performed.
A l
detailed analysis is performed on an annual basis by an independent commerical 12boratory to identify scaling factors via ST-0-066-731-0, ST-0-066-732-0.
l l
b.
For dry active waste (DAW), waste classification i
shall be based upon isotopic analysis and the use I
of scaling factors for Reactor Water Cleanup resin along with DAW dose-to-curie conversion.
c.
For oils / sludges waste classification chall be based upon isotopic analysis and the use of scaling factors for hard to measure isotopes. 'A detailed analysis is performed on each batch to be processed and packaged.
l d.
A computerized waste classification and shipping program, PARRAD, is used to determine waste classification f rom the isotopic analysis and scaling factors.
Manual methods may be used if the computer system is not available.
5.4.2 WASTE STABILITY a.
MINIMUM STABILITY RBQUIREKENTS l
1.
Waste at Limerick Generating Station is packaged in metal containers (drums, boxes, liners) or High Integrity Containers.
In no case chall radioactive waste be packaged in cardboard or fiberboard boxes for burial.
==
l I
,-------.------,,,,--n,
.---a,
LCS - PCP Rev. 5 Page 9 of 13 BWS/ inh 2.
Dewatered resin is sampled as a minimum annually te verify that the free r,tanding water content of the packaged product is within the limits established by applicable regulatory limits via 57-0-066-733-0.
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 organi: substances, one or more i
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 hydtgen generation is limited to a solar quantity that would be no more than 54 by volume of the secondary container gas vold at 3TP over a period of time that is twice l
the expected shipment time.
L The cask cavity will be inerted.
4.
Experience has demonstrated that utility waste streams do not contain or generates toxic gas, vapors, or fumes and do not t
cor.tain hazardous, biological, pathogenic, or infectious materials.
b.
WASTE STABILITY a
1.
Dewatered resin required to be stabilized is Packaged in High Integrity Containers (NIC) that have been certified to meet the stability rquirements of 10CFR61.56(b The HICs are handled and stored in a manner).such 1
that their ability to provide stabilization l
is not compromised.
The chemical and physical properties of the resin in no way i
compromises the integrity of the container.
2.
All reasonable efforts are made to eliminate unnecessary void spaces within the waste packages.
l I
i 1
i t
4
LGS - PCP Rev. 5 Page 10 of 13 BNS/1mh um 5.4.3 LABELL1HG Each package of waste shall be clearly labelled to i
identify waste classification.
5.4.4 SHIPMENT MAH1 RESTS Each waste shipment shall be accompanied by a shipping manifest giving a physical description of the waste, the volume, the radionuclide identity and quantity, the total radioactivity, the principal cheelcal form, and waste class.
5.4.5 QUALITY CONTROL PROGRAM The quality control pregram consists of required a.
use of plant procedures which implement the i
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 loplementing procedures are audited once per 24 months by the Nuclear Review Board in accordance with Plant Technical Specification 6.5.2.
5.5 ADMINISTRATIVE CONTROL 5.5.1 Processing of solid radioactive waste shall be A
performed by properly trained and qualified operating personnel.
5.5.2 Processing of radioactive waste shall be performed in accordance with approved Operating and/or Radweste procedures.
l 5.5.3 Procedures for processing, containerization, and transport of waste shall ensure that specific DOT, WRC, and burial site requirements are satisfied.
5.5.4 Changes to implementing procedures are reviewed to 4
ensure continued compliance with the Process Control i
Program.
5.5.5 Records of all data, tests, analysis results, and records of training, inspection, and audits are maintained in accordance with plant OA procedures for record retention.
i I
ME I
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i 9
L
L48 - PCP Rev. 5 Page 11 of 13 BWS/1mh 6.0 ATTACEMDrTS, TABLES, FIGURES 6.1 Table 6.1 Process Control Program implementing Procedures.
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LCS - PCP Rev. 5 Page 12 of 13 BWS/imh
]
m<
.a'ACRMENT 6.1 Process Control Program Implementing Procedures A-99 Control of the Radwaste Process Control Program RP-713 Ceneral Packaging. Marking and Labeling Requirements for Radioactive Materials for shipment i
RP-722 Determination of Rrdioactive Quantity 57-900 General Requirements for Shipping Radioactive Materials RW-101 Administration of Packaged Radioactive Waste RW-106 Review o! Vendor Topical Report for Waste Processing RW-130 Administrative Controls for PARRAD - A Packaged Radweste Management and Tracking Code RW-220 Exclusive Use Shipment l RW-230 Core Sample of Liners and HIC's RW-430 Eaternal Processing Station Resin Transfer'and Dewatering Test Using Chen Nuclear Equipment and 14-215 (or smaller)
Liners t
RW-431 External Processing Station Resin Transfer and Dewatering Test using Chen Nuclear Equipment and 21-300 Liners s
RW-440 LN Technologies / Stock Equipment Co. Quick Dry Dewatering System Setup and Removal RW-441 External Processing Station Resin Transfer and Dewatering Test Using LN Technologies / Stock Equipment Co. Quick Dry Dewatering System 566.0.3 RWCU Phase Separator Decanting 866.8.C Centrifuging RWCU Phase Separators 966.8.F Centrifuging Waste Sludge Tank 567.0.A Operating the Realn Fill Stations 567.0.A equipment Alignment for Operation of a Solid Radwaste (COL)
Centrifuge 567.0.5 Condensate Phase Separator Decanting om L
LCS - PCP Rev. 5 Page 13 of 13 BWS/Imh a
867.8.0 Centrifuging Condensate Phase Separators 87-0-066-731-0 Periodic Sampling and Analysis Program for the Determination of Abundance Factors ST-0-066-732-0 Periodic Determination and Update of Abundance Factors for Gamma Emitting Isotopes 87-0-066-733-0 Sampling and Analysis of Dewatered Resins for the Determination of Free Standing Liquid I
9 e.
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l 2 l 3.12 Nuclear Pacific. Inc. Topical l Utilized Nuclear Pacific as a l
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[UtilizedNuclearPacificasa l
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processing described in sections l dewatering vendor.
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5.2 and 5.3, the Pacific l
Nuclear Systems dewatering l
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equipment may be utilfred. A I
g description of the Pacific l
l l
Nuclear equipment and process l
- method may be found in Topical g
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g I
previously sumbitted to the NRC.l g
12 ! Attach I g
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g RW-420 External Processing Added Nuclear Pacific procedure toI l
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Station Resin Transfer and list of implementing procedures.
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I Nuclear dontainers and E'quipmentg g
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3882051780 Rev. s Page 1 of 13 l
TJG/KJC/lmh J
CD v 9,
4 4
e LIMERICK GENERATING STATION UNITS 1 AND 2 PHILADELPHIA ELECTRIC COMPANY SOLID RADWASTE SYSTEM PROCESS CONTROL PROGRAM APPROVAL:
1 A
/
TLANT MANAGER '
3/21 pp, PORC MEETING: ((?- 7 i DATE:
\\
Rev. 6 Page 2 of 13
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TJG/KJC/lmh C0"V 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.
2.0 SCOPE This program is applicable to the Lirerick Generating Station solid radwaste 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 Branch Technical Positicn ETSB 11-3, Rev. 2 3.4 Low Level Waste Licensing Branch Techn, cal 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 3.6 Barnwell Waste Management Facility Site Disposal Criteria 3.9 State of Washington Radioactive Materials Licen No. WN-IOl9-2 3.10 Chem Nuclear Systems Inc. Topical Report RDS-1000 Radioactive Waste Dewatering System RDS-25506-01-NP 3.11 Stock Equipment Co. Topical Report Quick Dry Process for 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.
Rev. 6 O
Page 3 of 13 l
TJG/KJC/Imh 4.0 GENERAL Plant Technical Specification 3/4.11.3 requires the Solid Radwaste Processing System to be used in accordance with a Process Control Program to 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 affect solidification and developing operational controls for those parameters.
Implementing a Waste Classification System in accordance with 10CFR61 and applicable Regulatory Guidance.
Providing an appropriate Quality Control Program as required by 10CrR20.311 4.1 REVIEW, APPROVAL, CHANGES 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.
4.1.2 Changes shall be submitted to the Nuclear Regulatory Commission in the Se:ni-Annual Radioactive Ef fluent Release Report for the period in which the change was made in accordance with Technical Specification 6.13.
4.2 USC OF VENDOR SERVICES l
4.2.1 Vendor services may be used to solidify or dewater I
any radioactive waste stream provided the services are performed with an acceptable Process Control Program inaccordance with A-99, Control of the Radwaste Process Control Program.
If the vendors's Process Control Program is used the requirements of Sections 5.2 and 5.3 of this Process Control Program may not be applicable.
4.2.2 In lieu of the inplant system processing described in Section 5.2 and 5.3 the Chem Nuclear Rapid Dewatering System RDS-1000 may be utilized.
A description of the Chem Nuclear equipment and procmss method may be b
f l
I l
nOV RevM V
Page 4 of 13 I
l TJG/KJC/1mh found in Topical Report RDS-25506-01-NP previously submitted to the NRC.
4.2.3 In lieu of the Inplant System Processing described in Section 5.2 and 5.3 the LN Technologies / Stock Equipment Co. Quick Dry Process may be utilized.
A description of the LN Technologies / Stock Equipment Co. equipment and process method may be found in Topical Report SRS-003-P Rev. O, previously submitted to the NRC.
4.2.4 In lieu of the inplant system processing described in Sections 5.2 and 5.3, the Pacific Nuclear Systems dewatering equipment may be utilized.
A description of the Pacific Nuclear equipment and process method may be found in Topical Report TP-02-P-A Rev. 1, previously submitted to the NRC.
5.0 IMPLEMENTATION The Process Control Program shall be implemented by the use of approved plant procedures which provide the step-by-step direction for the operation of the process systems and shipment of waste to a licensed burial site.
A list of plant procedures which implement the Process Control Program is given in Table 6.1.
5.1 WASTE STREAMS 5.1.1 CONDENSATE PILTER/DEMINERALIZER SLUDGE Tne contaminated waste product generated by the backwash of the condensate filter demineralizers consisting of contaminated powdered ion exchange recins 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 WASTE SLUDGE 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.
Rev. 6 C0DV Page 5 of 13 l
TJG/KJC/Imh
~
5.1.3 REACTOR WATER CLEANUP FILTER /DEMINERALIZER SLUDGE A contaminated waste product generated by the backwash of the Reactor Water Cleanup filter demineralizers consis'cing of contaminated powdered ion exchange resins at varying degrees of exhaustion, fibrous filter media, and small concentrations of various solids and corrosion products.
5.1.4 DRY ACTIVE WASTE Dry wastes consists of air filters, miscellaneous paper, rags, etc., from contaminated areas; contaminated clothing, tools, and equipment parts that cannot be effectively decontaminated; and solid laboratory wastes.
5.1.5 OILS / SLUDGES-WET RADIOACTIVE WASTES Oils consist of non-reclaimable contaminated oils and grease of various grades both synthetic or otherwise in free form or containing various amounts of ;olid 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 a.
Each condensate filter /demineralizer backwash consists of approximately 9,000 gallons of slurry with approximately 315 lbs (dry wt.) spent resins and crud.
,k Ay, b.
Successive backwashes are collected and allowed W
to settle in a Condensate Phase Separator.
As the sludge settles the clarified liquid is decanted.
The phase separator is isolated when approximately 160 cubic feet of sludge has accumulated.
c.
The settled sir.dge is allowed to decay in preparation for dewatering while further lackwashes are routed to alternate phase separators.
d.
The phase separator liquid level is adjusted to provide a total tank batch volume of approximately 8,100 gallons.
D Rev. 5 Page 6 of 13 l
TJG/KJC/lmh c.
Phase separator contents are recirculated for a minimum of 30 minutes to mix contents of the vessel, resulting in a homogenous resin slurry of 6% (dry wt.) or less total solids.
l f.
The solids slurry is fed to a Centrifuge for dewatering or to the External Processing Station for vendor services processing.
5.2.2 WASTE SLUDGE
~
1 a.
Each backwash from a radwaste or ftsi pool filter l
demineralizer consists of approxi',t-f 1,500
~
l gallons of slurry, with approximat-50 lbs.
(dry wt.) spent resins and crud
(.,
' 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 wt.)
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 minuter to mix contents o!!
the vessel, resulting in a homogeneous resin slurry ranging from 0.5 to 6% (dry wt.) total solids.
During normal operation t'.. Naste Sludge Tank contains only the radwaste and fuel pool filte.'
demineralizer backwashes which result in a 0.5)
(dry wt.) total solida concentration.
Periodiv radwaste demineralizer backwashes will increase l
the solids level to approximately 3% (dry wt.)
for one 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 processing.
f.
Waste Sludge Tank contents may also be sent to a condensate phase separator for processing in accordance with Section 5.2.1.
+
Rev. 6 Page 7 of 13 l
TJG/KJC/lmh 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.
The phase uejarator is isolated when approximately 100 cubic feet of sludge has accumulated.
c.
The settled sludge is allowed to decay in preparation for dewatering, while further backwashes are rouced to the alternate phase separator, d.
The phase separator liquid level is adjusted to provide a total tank batch volume of approximately 4000 gallons.
e.
Phase separator contents are recirculated for a minimum of 30 minutes tc mix contents of the vessel, resulting in a homogeneous resin slurry of 6% (dry wt.) or less total solide.
f.
The solids slurry is fed to a centrifuge for dewatering or to the External Processing Station for vendor services processing.
5.2.4 OILS / SLUDGES a,
Sludges and oils generated during operation and maintenance are collected in containers in appropriate approved areas throughcut the plant.
The filled and labeled containers are sealed and moved to a controlled-access 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.
L.
Rev. 6
[) g g 0
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TJG/KJC/lmh 5.3 DEWATERING PROCESS CONTROL 5.3.1 The 0.5-6% solids slurries discussed in Section 5.2 are fed te a centrifuge at a controlled flow rate for dewatering.
5.3.2 Operating variables such as centrifuge pond setting, bearing temperatures, equipment vibration, and differential torque are monitored to ensure optimum centrifuge operation and compliance with the free standing water criteria.
5.3.3 The dewatered resin is packaged in appropriately celected 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.
,5.4 10CFR61 IMPLEMENTATION 5.4.1 WASTE CLASSIFICATION a.
For dewatered resin, waste classification shall be based upon isotopic analysis ar.d the use of scaling factors for hard to measure isotopes.
During each container fill, a sample of resin is taken and an isotopic analysis is performed.
A detailed analysis is performed on an annual basis by an independent commerical laboratory to identify scaling factors via ST-0-066-731-0, ST-0-066-732-0.
b.
For dry active waste (DAW), waste classification shall be based upon isotopic analysis and the use of scaling factors for Reactor Water Cleanup resin along with DAW dose-to-curie conversion.
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 performed on each batch to be processed and packaged.
d.
A computerized waste classification and shipping program, PAKRAD, 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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Page 9 of 13 TJG/KJC/lmh S.4.2 WASTE STABILITY a.
MINIMUM STABILITY REQUIREMENTS 1.
Waste at Limerick Generating Station is packaged !n metal containers (drums, boxes, liners) or High Integrity Containers.
In no case shall radioactive 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 entablished by applicable l
regulatoty limits via ST-0-RRR-733-0.
In addition to the annual verification, the free standing water is determined whenever process changes occur that aay 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 cos.tainer 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 shioment time.
The cask cavity will be inerted.
4.
Experience has demonstrated that utility waste streams do not coi'tain or generate toxic gas, vapors, or ful.ies and do not contain hazardcus, biolog] cal, pathogenic, or infectious materials.
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
I C
Rev. 6 I
v Page 10 of 13 l
l TJG/KJC/lmh HICs are handled and stored in a manner such that their ability to provide stabilization 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 apaces withir. the waste packages.
5.4.3 LABELLING Each package of waste shall be clearly labelled to identify waste classification.
5.4.4 SHIPMENT MANIFESTS i
Each waste shipment shall be accompanied by a shipping manifest giving a physical description of the waste, the volume, the radionuclide identity and quantity, the total radioact)vity, the principal chemical form, and waste class.
5.4.5 QUALITY 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 Qualicy Assurance Program.
Audits by personnel independent of the activities are performed and reviewed by appropriate management personnel.
l b.
In addition, the Process Control Program and l
implementing procedures are audited once per 24 l
months by the Nuclear Review Board in accordance with Plant Technical Specification 6.5.2.
5.5 ADMINISTRATIVE CONTROL 5.5.1 Processing of solid radioactive waste shall be performed by properly trained and qualified operating personnel.
5.5.2 Processing of radioactive waste shall be performed in accordance with approved Operating and/or Radwaste procedures.
5.5.3 Procedures for processing, containerization, ar.d transport of waste shall ensure that specific DOT, NRC, and burial site requirements are satisfied.
W Rev. 6 l
Page 11 of 13 s.
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TJG/KJC/1mh l
l 5.5.4 Changes to implementing procedures are reviewed to ensure continued compliance with the Process Control Program.
5.5.5 Records of all data, tests, analysis results, and records of training, inspection, and audits are maintained in accordance with plant OA procedures for record retention.
6.0 ATTACHMENTS, TABLES, PIGURES 6.1 Table 6.1 Process Control Program Implementing Procedures.
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Rev. 6 Page 12 of 13 v
l TJG/KJC/lmh ATTACHMENT 6.1 Process Control Program Implementing Procedures A-99 Control of the Radwaste Process Control Program HP-713 General Packaging, Marking and Labeling Requirements for Radioactive Materials for Shipment HP-722 Determination of Radioactive Quantity HP-900 General Requirements for Shipping Radioactive Materials RW-101 Administration of Packaged Radioactive Waste RW-106 Review of Vendor Topical Report for Waste Processing RW-130 Administrative Controls for PAKRAD - A Packaged Radwaste Management and Tracking Code RW-22V Exclusive Use Shipment RW-230 Core Sample of Liners and HIC's RW-420 External Processing Station Resin Transfer and Dewatering Test Using Pacific Nuclear Containers and Equipment RW-430 External Processing Station Resin Transfer and Dewatering Test Using Chem Nuclear Equipment and 14-215 (or smaller)
Liners RW-431 External Processing Station Resin Transfer and Dewatering Test Using Chem Nuclear Equipment and 21-300 Liners RW-440 LN Technologies / Stock Equipment Co. Quick Dry Dewatering System Setup and Removal RW-441 External Processing Station Resin Transfer and Dewatering Test Using LN Technologies / Stock Equipment Co. Quick Dry Dewatering System S66.8.B RWCU Phase Separator Decanting S66.8.C Centrifuging RWCU Phase Separators S66.8.P Centrifuging Waste Sludge Tank S67.8.A Operating the Resin Fill Stations
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Page 13 of 13 TJG/KJC/lmh S67.8.A Equipment Alignment for Operation of a Solid Radwaste (COL)
Centrifuge S67.8.B Condensate Phase Separator Decanting S67.8.G Centrifuging Condensate Phase Separators l ST-0-RRR-731-0 Periodic Sampling and Analysis Program for the Determination of Abundance Factors um l ST-0-RRR-732-0 Periodic Determination and Update of Abundance Factors for Gamma Emitting Isotopes l
l ST-0-RRR-733-0 Sampling and Analysis of Dewatered Resins for the l
Determination of Free Standing Liquid l
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I CHAtlGE5 TO THE PCP. REV 7
- Dage.Sectton From I
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3.13 Westinghouse-Ilittman Nuclear, Utilized liittman as a dewatering g
g g Inc. Topical Report vendor.
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g l STD-R-05-011P-A, Mobile l
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l Incontainer Dewatering ar.d l
l Solidification System.
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In Ifeu of the inplant system Utilized Ilittman as a devatering i
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processing described in sections vendor.
I 5.2 and 5.3, the Westinghouse-i I
liittman Nuclear dewatering g
equipment may be utilized.
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A description of the Westinghousa-l g
g liittman equipment and procesa l
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method may be found in Topical l*
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Report, STD-R-05-OllP-A, j
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previously submitted to the NRC.I I
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I Figure 6.1 Solid Radwaste Added diagram depicting plant Hanagement System Process Flow
, process flow paths.
Diagram.
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g 12 gAttach I l
g lRW-410 External Processing l' Added Ilittman procedure to list of l I
l gment l Station Resin Transfer and l implementing procedures.
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Dewatering Test Using Westinghoule-1 l
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liittman Containers and Devaterink I
I Esguipmen t.
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3884054440 lgs - PCP Rev. 7 I-l Page 1 of 14 TJG/KJC/rls1 4
i l
l LIMERICK GENERATING STATION UNITS 1 AND 2 PHILADELPHIA ELECTRIC COMPANY SOLID RADWASTE SYSTEM
- .g.
.es s
qTdh g
s APPROVAL:
p&
4 PLAtM' RANAGER 7 "'
PORC MEETING:
ff -Oh[ DATE: f
[
J
LGS - PCP Rev. 7 Page 2 of 14 l
TJG/KJC/dsl
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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.
2.0 SCOPE This program is applicable to the Limerick Generating Station solid radwaste processing system.
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3.0 REFERENCES
3.1 49 CFR Par *s 170 through 178 1
3.2 10 CFR Parts 20, 50, 61 and 71 3.3 Standard Review Plan 11.4, Rev.
2, including Branch Technical Position ETSB 11-3, Rev. 2 kkl' 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 3.8 B'arnwell Waste Management Facility Site Disposal Criteria 3.9 State of Washington Radioactive Materia 1s Licen No. RN-IO19-2 3.10 Chem Nuclear Systems Inc. Topical Report RDS-1000 Radioacudve Waste Dewatering System RDS-25506-01-NP 3.11 Stock Equipment Co. Topical Report Quick Dry Process for 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.
LGS - PCP Rev. 7 Page 3 of 14 l
TJG/KJC/dsl 3.13 Westinghouse-Hittman Nuclear, Inc. Topical Report STD-R l OllP-A, Mobile Incontainer Dewatering and Solidification System.
4.0 GENERAL P.lant Technical Specification 3/4.11.3 requires the Solid Radwaste Processing System to be used in accordance with a Procese Control Program to meet transportation and disposal site r-guirements.
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 vaste streams Establishing a set of process parameters that affect solidification and developing operational controls for l
those parameters.
l 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 4.1 REVIEW, APPROVAL, CHANGES 4.1.1 Changes to the Process Control Program shall be I
reviewed and approved by the Plant Operations Review Committee in accordance with Technical Specifications 6.5.1 and 6.13.
4.1.2 Changes shall be submitted to the Nuclear Regulatory Commission in the Semi-Annual Racioactive Effluent Release Report for the period in which the change was made in accordance with Technical Specification 6.13.
4.2 USE OF VENDOR SERVICES 4.2.1 Vendor services may be used to solidify or dewater any radioactive waste stream provided the services are performed with an acceptable Process Control Program inaccordance with A-99, Control of the Radwaste Process Control Program.
If the vendors's Process Control Program is used the requirements of Sections 5.2 and 5.3 of this Process Control Program may not be applicable.
Page 4 of 14 TJG/KJC/dsl 4.2.2 In lieu of the inplant system processing described in i
Section 5.2 and 5.3 the Chem Nuclear Rapid Dewatering Systen RDS-1000 may be utilized.
A description of the Chem Nuclear equipment and process method may be found in Topical Report RDS-25506-01-NP previously submitted to the NRC.
4.2.3 In lieu of the Inplant System Processing described in Section 5.2 and 5.3 the LN Technologies / Stock Equipment Co. Quick Dry Process may be utilized.
A description of the LN Technologies / Stock Equipment Co. equipment and pr: cess method may be found in Topical Report SRS-003-P Rev. O, previously submitted to the NRC.
4.2.4 In lieu of the inplant system processing described in Sections 5.2 and 5.3, the Pacific Nuclear Systems dewatering equipment may be utilized.
A description of the Pacific Nuclear equipment and process method may be found in Topical Report TP-02-P-A Rev.
1, previously submitted to the NRC.
4.2.5 In lieu of the inplant system processing described in Sections 5.2 and 5.3, the Westinghouse-Hittman Nuclear dewatering equipment may be utilized.
A
..5-description of the Westinghouse-Hittman equipment and process method may be found in Topical Report, STD-R-05-OllP-A, previously submitted to the NRC.
5.0 IMPLEMENTATION The Process Control Program shall be implemented by the use of approved plant procedures which provide the step-by-step direction for the operation of the process systems and shipment of waste to a licensed burial site, A list of plant procedures which implement the Process Control Program is given in Table 6.1.
5.1 WASTE STREAMS 5.1.1 CONDENSATE FILTER /DEMINERALIZER SLUDGE The contaminated waste product generated by the backwash of the condensate filter demineralizers consisting of contaminated powdered ion exchange resins at varying degrees of exhaustion, fibrous filter media, carbon everlay material, and small concentrations of va.rious solids, activated and non-activated corrosion products.
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Rev. 7 l,,,
l Pace 5 of 14
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TJG/KJC/ds1 5.1.2 WASTE SLCLGE 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 FILTER /DEMINZRALIZER SLUDGE A contaminated waste product generated by the bacxwash 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 corrosion products.
5.1.4 DRY /.JTIVE WASTE Dry wastes consists of air filters, miscellaneous paper, rags, etc., from contaminated areas; I
contamino'.ed clothing, tools, and equipment parts gjf that cannot be effectively decontaminated; and solid pv laboratory wastes.
5.1.5 OILS / SLUDGES-NET RADI0 ACTIVE WASTES oils consist of non-reclaimable contaminated oils and greast-of various grades both synthetic or otherwise in free form or containing various amounts of solid mattrial.
Sludge consists of sump dewatering sludges, filter solids, strainer solids and other wet solids toc large to oe 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 315 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 the clarified liquid is decanted.
The phase separator is isolated when approximately 160 cubic feet of sludge has accumulated.
Page 6 of 14 TJG/KJC/ds1 The settled sludge is allowed to decay in c.
preparation for dewatering while further backwashes are routed to alternate phase separators.
d.
The phase separator liquid level is adjusted to provide a total tank batch volume of approximately 8,100 gallons.
Phare separator contents are recirculated for a l
e.
minimum of 30 minutes to mix contents of the vessel, resulting in a homogenous resin slurry of 6% (dry wt.) or less total solids.
f.
The solids slurry is fed to a Centrifuge for dewatering or to the External Processing Station for vendor services processing.
5.2.2 WASTE SLUDGE Each backwash from a radwaste or fuel pool filter a.
demineralizer consists of approximately 1,500 gallons of slurry, with approximately 60 lbs.
(dry wt.) spent resins and crud (may contain
- g; charcoal overlay).
Lp b.
Each backwash from a radwaste dimineralizer consists of approximately 1,500 gallons of slurry, with an average of 2,125 lbs. (dry wt.)
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 t6 mix contents of the vessel, resulting in a homogeneous resin slurry ranging from 0.5 to 6% (dry wt.) total s.
- 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 concentration.
Periodic radwaste demineralizer backwashes will increase the solids level to approximately 3% (dry wt.)
for one bed or 6%(dry wt.) for two beds.
Page 7 of 14 TJG/KJC/ds1 I
The solids slurry is fed to a centrifuge for e.
dewatering or to the External Processing Station l
for vendor services processing.
f.
Waste S*udge Tank contents may also be sent to 's condensate phase separator for processing in accordance with Section 5.2.1.
l S.2.3 REACTOR WATER CLEANUP FILTER /DEMINERALIZER SLUDGE Each RWCU filter /demineralizer backwash consists a.
of approximately 1,100 gallons of slurry with approximately 48 lb. (dry wt.) spent resinc and crud.
b.
Successive backwashes are collected and allowed to settle in a phase separator.
As the sludge settles the clarified liquid is decanted.
The phase separator is isolated when approximately 100 cubic feet of sludge has accumulated, The settled sludge is allowed to decay in c.
preparation for dewatering, while further backwashes are routed to the alternate phase 3,
separator.
d.
The phase separator liquid level is adjusted to provide a total tank batch volume of approximately 4000 gallons.
Phase separator contents are recirculated for a a.
minimum of 30 minutes to mix contents of the vessel, resulting in a homogeneous resin slurry of 6% (dry wt.) or less total solids.
f.
The solids slurry is fed to a centrifuge for I
(
dewatering or to the External Processing Station for vendor services processing.
5.2.4 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-access enclosed area for temporary storage.
b.
Oils and sludges can be solidified in appropriate contair,ars by vendor supplied equipment in accordance with approved vendor process control procedures.
LGS - PCP Rev. 7 Page 8 of 14 I.
TJG/KJC/dsl c.
Certain wet wastes may be allowed to dry and be treated as dry active waste.
5.3 DEWATERING PROCESS CONTROL 5.3.1 Tne 0.5-6% solids slurries discussed in Section 5.2 are fr.d to a centriluge at a controlled flow rate for dewatering.
5.3.2 Operating variables such as centrifuge pond setting, bearing temperatures, equipment vibration, and differential torque are monitored to ensure optimum centrifuge operation and compliance with the free standing water criteria.
3.3.3 The dewatersd resin is packaged in 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.
5.4 10CFR61 IMPLEMENTATION 5.4.1 WASTE CLASSIFICATION h7
- .?
For dewatered resin, waste classification shall a.
be based upon isotopic analysis and the use of scaling factors for hard to measure isotopes.
During each container fill, a sample of resin is taken and an isotopic analysis is performed.
A detailed analysis is performed on an annual basis by an independent commerical laboratory to identify 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 factois for Reacto.r Water Cleanup resin along with DAW dose-to-curie convtrsion.
l For ollaisludges waste classification shall be c.
based upon icotopic analycia and the use of
' scaling factors for hard to measure isotopes.
A detailed analysis is performed on each batch to be precessed and pachaced.
d.
A computerized wasto classification and shipping program, PAFRAD, is used to determine waste classification from the isotopic analysis and scaling factors.
Mar.ual methods may be used if l
the computor syster is not available.
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Rev. 7 l
l Page 9 of 14 TJG/KJC/dsl i
I 5.4.2 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 radioactive 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 p
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 i
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 shipment 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.
Page 10 of 14 I
TJG/KJC/dsl b.
WASTE STABILITY I
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(h The HICs are handled and stored in a manner).such that their ability to provide stabilization is not compromised.
The chemical and physical properties of the resin in no way compromises the integr.4.ty of the container.
2.
All reasonable efforts are made to eliminate unnecessary void spaces within the waste packages.
5.4.3 LABELLING Each package of waste shall be clearly labelled to identify waste classification.
5.4.4 SHIPMENT MANIFESTS Each waste shipment shall be accompanied by a 3
shipping manifest giving a physical description of the waste, the volume, the radionuclide identity and quantity, the total radioactivity, the principal chemical form, and waste class.
5.4.5 QUALITY CONTROL PROGRAM The quality control program consists of required a.
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 by the Nuclear Review Board in accordance with Plant Technical Specification 6.5.2.
Page 11 of 14 TJG/KJC/dsl 5.5 ADMINISTRATIVE CONTROL 5.5.1 Processing of solid radioactive waste shall be performed by properly trained and qualified operating personnel.
5.5.2 Processing of radioactive waste shall be performed in accordance with approved Operating and/or Radwaste procedures.
5.5.3 Procedur?s for processing, containerization, and transport of waste shall ensure that specific DOT, NRC, and burial cite requirements are satisfied.
5.5.4 Changes to implementing procedures are reviewed to ensure continued compliance with the Process Control Program.
i 5.5.5 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.
[.-5!
6.0 ATTACRMENTS, TABLES, FIGURES 6.1 Table 6.1 Process Control Program Implementing Procedures.
6.2 Figure 6.1 Solid Radwaste Management System Process Flow
- Diagram, s
Page 12 of 14 TJG/KJC/dsl ATTACHMENT 6.1 Process Control Prepram Implementino Procedures A-99 Control c.' the Radwaste Piccess Control Program HP-713 General Packaging, MarKin. and LabeAing P.equiremants for Radioactive Materials fo-
'hipment HP-722 Determination of Radioactive Ou<,.ity HP-900 General Requirements for Shipping Aadioscrive Materials RW-101 Administration of "ackaged Radioactive Waste RW-106 Review of Vendor Topical Report for Waste Processing l
RW-130 Administrative Controls for PAKRAD - A Packaged Radwaste Management and Tracking Code RW-220 Exclusive Use Shipment g
RW-230 Core Sample of Liners and HIC's RW-410 External Processing Station desin Transfer and Dewatering Test Using Westinghouse-Hittman Containers and Dewatering Equipment RW-420 External Processing Station Resin Transfer and Dewatering Test Using Pacific Nuclear Containers and Equipment RW-430 External Processing Station Resin Transfer and Dewatering Test Using Chem Nuclear Equipment and 14-215 (or smaller)
Liners RW-/.31 External Processing Station Resin. Transfer and Dewatering Test Using Chem Nuclear Equipment and 21-300 Liners RW-440 LN Technologies / Stock Equipment Co. Quick Dry Dewatering Systym Setup and Removal RW-441 External Processing Station Resin Transfer and Dewatering Test Using LN Technologies / Stock Equipment Co. Quick Dry Dewatering System S66.8.3 RWCU Phase Separator Decanting S66.8.C Centrifuging RWCU Phase Separetors
Rev. 7 Page 13 of 14
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l TJG/KJC/dsl S66.8.F Centrifuging Waste Sludge Tank S67.8.A Operr. ting the Resin Fill Stations S67.8.A Equipment Alignment for Operation of a Solid Radwaste (COL)
Centrifuge S67.8.B Condensate Phase Separator Decanting S67.8.G Centrifuging Condensate Phase Separators ST-0-RRR-731-0 Periodic Sampling and Analysis Program for the Determination of Abundance Factors ST-0-RRR-732-0 Periodic Determination and Update of Abundance Factors for Gamma Emitting Isotopes ST-0-RRR-733-0 Sampling and Analysis of Dewatered Resins for the Determination of Free Standing Liquid
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PHILADELPHI A ELECTRIC COM PANY LIMERICK GENER ATING STATION P. O. BO X A S AN ATOG A, PENNSY LV ANI A 19464 (215) 3 2 71200, EXT, 3000 August 29, 1988 oa^Hau w.'ritcH u....."..'.l.".'.*1'...,,.
Docket No. 50-352 l
l Mr. W. T. Russell, Regional Administrator Region I U.S. Nuclear Regulatory Commission Attention: Document Control Desk l
Washington, DC 20555
SUBJECT:
Semi-Annual Effluent Release Report No. 8 j
January 1, 1988 through June 30, 1988 Limerick Generating Station Unit 1
Dear Mr. Russell:
Enclosed are two copies of the Semi-Annual Effluent Release Report No. 8 for the period January 1, 1988 through June 30, 1988 for Limerick Generating j
Station Unit 1.
This report is being submitted in compliance with the Technical Specification 6.9.1.8 of Operating License NPF-39 and Regulatory Guide 1.21 to fulfill the requirements of Regulatory Guide 10.1.
Very truly yours, 3
3
///,
/
y,
[ f l b, lc Attachment cc.
Addressee T. J. Kenny, Senior Resident Site Inspector