ML20082N006
| ML20082N006 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/30/1991 |
| From: | Dubiel R, Leitch G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9109060137 | |
| Download: ML20082N006 (51) | |
Text
.-
PIIILADELPIIIA ELECTRIC COMPANY LIMERICK GENEllATING STATION P. O. ILOX 2300 POTIY!'OWN, l'A 19464 W20 (215) 327 IKO, lWT. yKO August 28, 1993 GR4WJ M. LUTCH grg/24,, Docket 11os. 50-352 50-353 License lios. 11PF-39 11PF-8 5 U. S. 11uclear Regulatory Commission Attnt Document Control Desk Washington, DC 20555
Subject:
Limerick Generating Station, Units 1 and 2 Semi-Annual Ef fluent Release Report lio. 14, January 1, 1991 through June 30, 1993 Gentlemen:
Enclosed is the Semi-Annual Effluent Release Report flo. 14, for Limerick Generating Station (LGS), Un!.to 1 and 2, for the period January 1, 1991 to June 30, 1991.
These reports are being submitted in accordance with the LGS Technical Specification Section 6.9.1.8 and 10CFR50.36(a).
Very t uly yours, f )
/ l]
KWM/ds Enclosures cc T. T. Martin, Administrator, Region I, US!1RC (w/ enclosure)
T. J. Kenny, US!1RC Senior Resident Inspector, LGS (w/ enclosure) 9109060137 010630 1
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LIMERICK GENERATING STATION L
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i PHILADELPHIA ELECTRIC COMPANY i LIMERICK CENERATING STATION UNITS NO. 1 AND 2 DOCKET NO. 50-352 (Unit 1)
DOCKET NO. 50-353 (Unit 2) ;
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t
. i SEMI-ANNUAL EFFLUENT RELEASE-REPORT r NO. 14 JANUARY 1, 1991 THROUGH JUNE 30, 1991 l
Submitted to The United Staten Nuclear Regulatory Commission '
Pursuant to
+
Facility Operating License NPF-39 (Unit 1) and NPF-85 (Unit 2) ;
I L
A.- }L R. W. Dubiel, Services Superintendent i e
- . , -. __ - _ _ _ _ _ _ - _ - _ _ -1
i c
TABLE OF CONTENTS e
i t
I. Introduction II. Tables A. Summary of Radioactive Gaseous Effluents B. Summary of Radioactive Liquid Effluents s
C. Solid Waste Disposition Report i
i III. Attachments A. Supplemental Information - Assumptions Used in Report Generation B. Administrative revisions to the Process Control Program-(PCP)' '
I r
1 I
?
,i C
. . i l
I. INTRODUCTION This submittal complies with the format described in l 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 !
reports A summary of the gaseous and liquid effluent releases for the report period. Where "0.00E+00" is used, it i denotes the less than detectable level for the given ;
isotope. '
Composite particulate air samples, counted for beta emitters (eg. Sr-89, St-90), are submitted to an offsite vendor laboratory-for analysis. Since data for the second quarter particulate air samples were not '
available at the time this repirt was prepared, it will be necessary to submit an add *1um in the future if second quar,ter particulate air samples results are
.- reported >LLD. ;
i Since Limerick Technical Specification limits for ;
liquid and gaseous effluent releases are stated in i terms of quarterly and annual offsite doses, " percent ;
technical specification limit" is given as 0.00E+00. .
A summary of solid waste dispositioned during the i 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 L transportation, destination, type of container, total container volume, and solidification agent.
Explanation of the change which incorporated Process I Control Program (PCP) revison 11 into a Radwaste procedure (RW-800).
f 5
I
4 II. TABLES A.
SUMMARY
OF RADIOACTIVE GASEOUS EFFLUENTS January 1, 1991 to June 30, 1991 1
1 4
- S2,TE
- -L2MER8CK WNI T :' U1 -
USER: MART DATE:'08/OS/91 16!00
. EFFLUENT AND WASTE DISPOSAL REPORT
--...--~~------------------------.-
.0ASEOUS EFFLUENTS --
EUMMATION OF AtL REL EASE?
-.-----._--_-----..-..----- ...----_---------- i
- UNITS : OUAF TER ! CUARTER *EIT. TOTSL:
. 1 rc e. 0 c. e
. . . . -.m ~. ,
A. FISSION AMD ACTIVATION GAGEG
- 1. TOTAL RELEASE : CI : 0.250Et02 : 0.43?E400 : 0 " E+0 *
-!2. AVERAGE RELEASE :UCI/SEC: 0.321E+01 : 0.533E401 :
! RATE FOR PERIOD : : 1
- 3. PERCENT OF TECHNICAL: *
. : 0.000E+00 : 0.000E+00 :
- SPECIFICATION LIMIT : : : 1 P. ZODINES t 1. TOTAL IODINE-131 : CI : 0.000Ef00 0.000Ef00 1 0.453E+02 2.' AVERAGE RELEASE
- UCI/SEC: 0.000Et00 : 0.000EiOO :
- RATE FOR PERIOD : : : :
- 3. PERCENT OF TECHNICAL: % : 0.000E+00 : 0.000E+00 :
- SPECIFICATION LIMIT : : :
C. PARTICULATES l 1. PAR 7ICULATES WITH : CI : 0.203E-04 : 0 000E+00 0.453E+02 :
- -- HALF-LIVES 'S DAYS : : : :
-: 2. AVERAGE RELEASE UCI/SEC: 0.261E-05 l'O.000E400 :
- RATE-FOR PERIOD : : : 1
': 3. PERCENT OF TECHNICAL: % 0.000Et00 : 0.000E+00 :
SPECIFICATION LIMIT : : : :
- 4 GROSS ALPHA : CI : 0.000E+00 : 0.000E+00
- :RADI0 ACTIVITY : : :
D. TRITIUM
- 1. TOTAL RELEASE : CI : 0.000Ef00 : 0.000Et00 : 0.453E+02
! 2. AVERAGE RELEASE UCI/SEC: 0.000E+00 : 0.000E+00 :
- - RATE'FOR PERIOD : : : :
3.' PERCENT OF TECHNICAL: % : 0.000E+00 : 0.000Ef00 :
- SPECIFICATION LIMIT : : : 1 a
[ ENTER t C'3 TO ERASE SCREEN AND CONTINUE : C l
.-- ~ , -- .. - -. . - . - - - . - _ . -
PAGE 1 0F 12 *
--SITE: LIMERICK '
UNIT -U1 USER: MART DATE:'08/08/91 14:01 EFFLUENT AND WASTE. DISPOSAL REPORT
-GASEOUS EFFLUENTS FOR RELEASE POINT!
1 NORTH STACK CONTINUOUS MODE ,ATCH MODE
- NUCLIDES
- UNITS : QUARTER : QUARTER : UUARTER : QUARTER c !. RELEASED : : 1 : 2 : 1 : 2 -:
l ..----------.---------------------------------_--- ..----------_------_
- 1. FISSION GASES
- l AP41 : CI : 0.000EiOO : 0.000E+00 : 0 000E+00 : 0.000E+00 1 l AR83M : CI : 0 000Ef00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
! KR85M CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0.000E+00
! KR85 : CI : 0.000Et00 0.000E+00 : 0.64BE-03 0.000Ef00 :
ll : NR87 : CI : 0.000E+00 0 000E+00 1 0.000E+00 1 0.000EiOO :
i KR88 : CI : 0.000E+00 0.000E+00 1 0.000E+00 : 0.000EiOO :
- KR89 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 0.000Ef00 :
~~--
- KR90 : CI : 0.000Ef00 0.000E+00 0.000E+00 : 0.000Ef00 :
.: XE131M : CI : 0.000E+00 : 0.000Ef00 0.000E+00 : 0.000E+00 XE133M : CI : 0.000E+00 0.000EiOO : 0.000E+00 : 0.000E+00 :
- XE133 : CI : 0.000E+00 : 0.394E+02 l 0.000Ef00 : 0.120Ef01 :
.:- XE135M : CI : 0.000E+00 0.000E+00 : 0.000E+00 0.000EiOO :
- XE135 : CI : 0.000Ef00 : 0.127Et01 : 0.000E+00 : 0.161E-04 :
L : XE137 : CI :-0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- XE138 : CI : 0.000Ef00 0.000E+00 : 0 000E+00 : 0.000E+00 :
l -; TOTAL FOR ; : : : :
l : PERIOD : CI : 0.000E+00 : 0.104E+02 : 0 44SE-03 : 0.120Ef01 :
I : (ABOVE) : : : : : 1 ENTER [ C J TO ERASE SCREEN AND CONTINUE : C l
,r, - - , - -
.- . . . . - . - . - - - ~. . . . - . - . .-. - .-
1 PAGE 2 0F-12 P
- 'SIVE! L f MERICK l r
UNIV: U 2 :
USER: MART: !
. DATE: 08/08/91 16:01 '
-EFFLUENT AND WASTE DISPOSAL REPORT F
GASEQUS EFFLUENTS FOR RELEASE = POINT: 1 NORTH STACN 1 i
?
CONTINUOUS MODE BATCH MODE I t
- NUCLIDES : UNITS : OUARTER : OUARTER : QUARTER : QUnRTER :
- RELEASED
- :
1 : 2 : 1 : 2 :
-2. 10 DINES
[
i I131 : CI : : 0.000E+00 1 0.000Ef00 : 04000E+00 :
_______________________0.000E+00 ______________________________________ ..__..___. ,!
- I133 : CI : 0.000E+00 : 0.000Ef00 0.000Et00 : 0.000Ef00 : I
- TOTAL FOR : : : : : : *
- PERIOD : CI : 0.000Ef00 : 0 000Ef00 1 0.000E+00 : 0.000E+00 :
- (ABOVE) : : : : : l I
- 3. PARTICULATES i C14 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 0.000E+00 : *
- CR51 : CI : 0.000Ef00 : 0.000E+00-: 0.000E+00 : 0.000E+00 : I,
- MN54 : CI : 0.000E+00 : 0.000E+00 0.000Ef00 : 0.000E+00 : .!
______________________._______________________________________________ i
- FE59 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 : 04000Ef00 : :
_______________________________________________________________..______ j C058 : CI : 0<000Ef00 : 0.000~+00 : 0.000Ef00 1 0.000E+00 : >
t
=
- C060 : CI : 0.000Ef00 : 0.000E+00 : 0.000E+00 0.000E+00 ZN65 : CI : 0.000E+00 0.000E+00 : 0.000Et00 : 0.000E+00 : [
j
': -SR89 : CI : 0.000E+00 : 0.000E+00 0.000EiOO : 0.000E+00 : ;
- SR90 : CI : 0.000E+00 0.000E+00-: 0.000E+00 : 0.000E+00 : ,
! ZR95 : CI : 0.000E+00 : 0.000Ef00 : 0.000E+00 : 0.000E+00 :
-: SB124 : CI : 0.000E+00 : 0.000Et00 : 0.000E+00 : 0.000E+00 : :
____________________________________._________________________________ }
- RCS134 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 0.000Ef00 : ,
j
-: CS136 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0.000Ef00 : :
! CS137 : CI : 0.000Et00 : 0.000E+00 ; 0.000E400 : 0.000E+00 :
t, ENTER'E C ] TO ERASE SCREEN AND CONTINUE : C f
" w V
d PAGE 3 0F 12 = ' '
TSITE! L8MERICK '
UNIT!:Ua USER: MART DAVE: 08/08/91 16:02
- EFFLUENT AND UASTE DISPOSAL REPORT
-GASEQUS EFFLUENTS FOR RELEASE POINT! 1 NORTH STACN CONTINUQUS MODE BATCH MODE
- . -NUCLIDES : UNITS : QUARTER : QUARTER CUARTER : QUARTER :
- RELEASED : : 1 : 2 : 1 : 2 :
- 3. PARTICULATES-(CONTD)
- BA140 : CI : 0.000E+00 : 0.000E+00 1 0.000E+00 : 0.000E+00 :
CE141 : CI 0.000E+00 : 0 000E+00 0.000E+00 1 0.000Ef00 :
- CE144 : CI ! 0.000Ef00 : 0.000L+00 : 0.000E+00 0.000E+00 1 1 TOTAL FOR : : : : : :
PERIOD * - : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Et00 :
- (ABOVE) : : : : :
ENTER CC ] TO ERASE SCREEN AND CONTINUE : C l
~ I l
1 1
1 l
i
PAGE 6 0F 12
. 'SfTE!:LZMERICK UN!T: U1:
USER: MART
. DATE: 08/08/91 16:02 EFFLUENT AND WASTE' DISPOSAL REPORT
.----------a ------------,---------
GASEOUS EFFLUENTS FDR RELEASE POINT: 2 UNIT 1 - SOUTH STACK CONTINUQUS MODE PATCH MODE
- NUCLIDES i UNITS : QUARTEP : QUARTER : GUARTER : QUARTER :
-RELEASED : 1 : 2 : 1 : 2 :
- 1. FISSION GASEG
! AR41 : CI : 0.000E+00 : 0.000E+00- 0.000E+00 : 0.000E+00
c .---------------------------------------....---
- KR83M : CI : 0.000E+00 0.000E+00 : 0.000Ef00 : 0.000E+00 :
NR85M : CI : 0.000Ef00 0.000Ef00 : 0.000E+00 : 0.000Ef00 :
cn------------- ~.---------------------------------------
- NR85 : CI : 0,00)E+00 0.000E+00 : 0.000E+00 : 0.000E+00 :
KR87 : CI : 0.000E+00 0.000Ef00 : 0.000Ef00 : 0.000Et00 :
KR88 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
21 KR89 : CI : 0.000E+00 : 0.000E400 : 0.000E+00 : 0.000Ef00 :
- - NR90 ': CI : 0.000E+00 : 0.000EiOO-: 0.000E+00 0.000E100 :
- XE131M : CI : 0 000E+00 : 0.000E+00 0.000Ef00 : 0.000E+00 :
- XE133M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
XE133 : CI : 0.247E+02 : 0.937E-01 0.000E+00 ; 0.000E+00 :
- XE135M : CI : 0.000E+00-: 0.000E+00 : 0.000Ef00 : 0.000E+00
- XE135 : CI : 0.000E+00 ; 0.652E-02 : 0.000Ef00 : 0.000Ef00 :
- XE137 : CI : 0.000Ef00 0.000E+00 : 0.000E+00 0.000Ef00 :
- XE138 : CI : 0.000E+00 : 0.000F+00 : 0.000Ef00 : 0.000E+00
- - TOTAL FOR : : : : : :
PERIOD : CI : 0.217Et02 : 0.100E+00 : 0.000Et00 : 0.000E+00 :
(ABOVE) -: : : : : :
- ENTER E C ] TO ERASE SCREEN AND CONTINUE : C
PAGE 5 0F 12 *
- SITE: LfMERZCK '
UNITt U1 USER! MART DATE: 08/08/91 16:03
- EFFLUENT AND WASTE DISPOSAL REPORT OASEOUS EFFLUENTS FOR RELEASE POINT: 2 UNIT 1 - SOUTH STACK CONTINUOUS MODE BATCH MODE NUCLIDES : UNITS : QUARTER : QUARTER ! CUARTER : QUARTER :
=
RELEASED : : 1 : 2 : 1 : 2 : ;
- 2. 10 DINES
- 1131 : CI 0.000E+00 ; 0.000Ef00 : 0.000Ef00 1 0.000Ef00 :
I133 : CI : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 : 0 000Ef00 :
l TOTAL FOR~: : : : : :
- PERIOD : CI : 0.000E+00 0.000E+00 : 0.000E+00 0.000E+00 :
. (ABOVE) : : : : :
t
- 3. PARTICULATES .
!' C14 : CI : 0 000Et00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CRS1 : CI : 0 000Ef00 : 0.000E+00 : 0.000Ef00 1 0.000Ef00 :
! MN54 : CI : 0.000E+00 : 0.000E+00 0.000Ef00 : 0.000Ef00 :
--___--__._____-___--____--______-__.n_--____________...____---___---- ,
! FE59 : CI : 0.000E+00 : 0.000Ef00 1 0.000Ef00 0.000E+00 :
C058 : CI : 0.000Ef00 0.000E+00-: 0.000E+00 1 0.000E+00 : ;
- C060 : CI : 0.000Ef00 : 0.000Ef00 : 0.000E+00 : 0.000Ef00 : t i
- ZN65 -: CI : 0.000E+00-: 0.000E+00 : 0.000Et00 : 0.000Ef00 : !
- SR89 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- SR90 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 0.000E+00 :
ZR95 : CI : 0.000E+00 0.000Ef00 : 0.000Ef00 0.000E+00 : >
_______-___________-- _______________..______________ -----______ ..__ i
- SB124 : CI l' O.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 : '
t
- CS134 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 : ;
CS136 : CI : 0.000E400 0.000E+00 : 0.000Ef00 0.000E+00 :
-___-_____-_____-__-____.______.-___.______--____--_.-__-___-_____-__ r
- CS137 : CI : 0.000Ef00 : 0.000Ef00 0.000E+00 : 0.000Ef00 : !
i ENTER E C J TO ERASE SCREEN AND CONTINUE : C i t
. PA0E 6 0F 12 !
, SITE:' LIMERICK e UNIV: U1 l' USER! MART '
. 'DATE: 09/08/91.16:03-EFFLUENT AND WASTE-DISPOSAL REPORT i h
OASEOUS EFFLUENTS FOR RELEASE POINT! 2 UNIT 1 - SOUTH STACN :
CONTINUOUS MODE PATCH MODE F
_.--.__- __ ______ ____-- .-__----.._--.---..__._____. ________...____ ?
t
- NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER : >
.: RELEASED : 1 : 2 : 1 : 2 : i t
- 3. PARTICULATES (CONTD) I t
i BA140 : CI : 0.000E+00 1 0.000Et00 : 0.000Et00 : 0.000Et00 : :
________________________________.__.--______ .__ _____.. .... ___. __ t
- CE141 : CI : 0.000E+00 0.000E+00 0.000E+00 0.000E+00 : !
-______________ __________________________..__---__- _______ ________ i 1: CE144 : CI : 0.000E+00 : 0.000E+00 1 0.000E100 : 0.000E400 : 1
..--_-________________________________. __------__.____..,_______.--___ j
- 70TAL FOR : : : : : : !
- PERIOD CI : 0.000E+00 : 0.000Et00 : 0.000Ef00 : 0.000Ef00 *
- (ABOVE)
- : : : : !
I P
ENTER CC 1 ;] ERASE SCREEN AND CONTINUE : C !
i I
t h-f i-e i
- 6 i
I t
. -j
.i
[
r
+
PAGE 7 0F 12 *
- S3TE: LIMERICK
- UNIT: U1 USER! MART DATL:~08/08/91 16:03 '
EFFLUENT AND WASTE DISPOSAL REPORT GASEQUS EFFLUENTS FOR RELEASE POINT! 3 UNIT 2 SOUTH STACK CONTINUOUS MODE BATCH MODE
-! NUCLIDES : UNITS : QUARTER : QUARTER : GUARTER : QUARTER :
- RELEASED : : 1 : 2 : 1 : 2 :
' 1. FISSION GASES
.........___~______..___. _______.___...__.......... __.. ________ __.
- AR41 : CI : 0.000E+00 1 0.000E+00 : 0.000Ef00 : 0.000Ef00 :
- KR83M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
KR85M ! CI : 0.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 :
i NR85 : CI : 0.000Et00 1 0.000Ef00 0.000E+00 0.000E+00 :
XR87 : CI : 0.000Ef00 1 0.000E+00 0.000Ef00 0.000E+00
. KR88 : CI -
0.000E+00 : 0.000E+00 ; 0.000E+00 0.000Ef00 :
KR89 : CI : 0.000E+00 : 0.000Ef00 : 0.000Ef00 : 0.000E+00 :
! NR90 : CI : 0.000E+00 1 0.000E+00 : 0.000E+00 1 0.000E+00 :
XE131M : CI : 0.000E+00 0.000E+00 0.000E+00 : 0.000E+00 :
- XE133M CI : 0.000E+00 : 0.000ff00 : 0.000E+00 0.000E+00 :
- XE133 : CI : 0.288E+00 : 0.000E+00 : 0.000E+00 0.000E+00 :
-: XE135M -1 CI : 0.000E+00 0.000Ef00 : 0.000Ef00 0.000E+00 :
! XE135 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 XE137 : CI : 0.000Ef00 0.000Ef00 ! 0.000Ef00 : 0.000E+00 :
8 XE138 : CI : 0.000Ef00 0.000E+00 : 0.000Ef00 : 0.000E+00 :
l TOTAL FOR l- : ! ! ;
- - PERIOD CI : 0.288E+00 ; 0.000Et00 : 0.000Ef00 : 0.000E+00 .
! (ABOVE) : : : : :
ENTER-t C ] TO ERASE SCREEN AND CONTINUE : C h
. PAGE 8 0F 12
.-
- SITE) LIMERICK i
-UNIT! U1 l USER! MART c DATE! 08/08/91-16:04 EFFLUENT AND WASTE DISPOSAL REPORT
~ 0ASE00S EFFLUENTS FOR RELEASE POINT: 3 UNIT 2 - SOUTH STACK CONTINUOUS MODE BATCH MODE NUCLIDES : UNITS : QUARTER : OUARTER : CUARTER : QUARTER RELEASED : : 1 : 2 : 1 : 2 :
- 2. 10 DINES I131 : CI : 0.000Et00 0.000Et00 ! 0.000E+00 0.000EF00
- I133 : CI : 0.000Ef00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
- - TOTAL FOR : : : : : :
- PERIOD : CI : 0.000E+00 : 0.000Et00 : 0.000E+00 0.000EF00 :
- (ABOVE) : : : : :
- 3. PARTICULATES CI4 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 0.000E+00 :
i CR51 : CI :-0.000Ef00 0.000E+00 0.000Et00 : 0.000Ef00 :
MN54 : CI : 0.858E-05 : 0.000E+00 0.000E+00 0.000E+00
- FE59 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 0.000E+00 :
- C058
- CI : 0.000E+00 0.000E+00 : 0.000E+00 0.000Ef00 :
C060 : CI : 0.117E-04 : 0.000Ef00 0.000E+00 : 0.000E+00 :
2N65 : CI : 0.000E+00 : 0.000E+00 : 0.000E+0e : 0.000E+00 :
- SR89 : CI : 0.000Ef00 : 0.000E400 : 0.000E+00 0.000E+00 1
- SR90 : CI : 0.000E+00 : 0.000Ef00 1 0 000E+00 : 0.000E+00 :
- ZR95 : CI : 0.000E+00 : 0.000Ef00 : 0.000Ef00 : 0.000E+00 :
- SB124 : CI : 0.000E+00 : 0.000E+00 0.000E400 0.000Ef00 CS134 : CI : 0.000Et00 : 0.000Ef00 : 0.000E+00 : 0.000E+00 :
- CS136 : CI : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 . 0.000Et00 :
- CS137 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C 1
1
PAGE 9 0F 12 '
SITE -LINERICK '
UN27: U1 USER: MART
~
DAVE: 08/08/91 16:04 EFFLUENT AND UASTE DISPOSAL-REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 3 UNIT 2- SOUTH STACN CONTINUQUS MODE FATCH NODE
- NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
RELEASED : : 1 : 2 : 1 : 2 :
- 3. PARTICULATES (CONTD)
! BA140 : CI : 0.000Ef00 : 0 000E+00 : 0.000E+00 : 0.000Et00 :
- CE141 : CI : 0.000E+00 : 0.000Ef00 : 0.000E+00 1 0.000Ef00 :
- CE144 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 1 0.000E400
! TOTAL FOR : : : : : :
PERIOD CI : 0.203E-Oi 0.000Et00 0.000E+00 0.000E+00 *
(ABOVE) : : : : :
ENTER C C ] TO ERASE SCREEN AND CONTINUE : C 4
. . PAGE 10 0F 12
. S2?E: -LIMERICK UNIT: U1 USER! MART
. DATE: 08/08/91 16:05 EFFLUENT AND WASTE DISPOSAL REPORT OASEOUS EFFLUENTS FOR RELEASE POINT: 4 HOT MAINTENANCE SHOP CONTINUQUS MODE 14 A T C H MODE
- NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
- RELEASED : ! 1 : 2 : 1 : 2 :
- 1. FISSION GASES
! AR41 : CI : 0.000Ef00 : 0.000E+00 0.000E+00 1 0 000E+00 :
! KR83M : CI : 0.000Ef00 0.000E+00 : 0.000Ef00 0.000E+00 :
KR85M : CI : 0.000E+00 1 0.000E+00 : 0.000f+00 : 0.000E+00 ;
KR85 : CI : 0.000E+00-: 0.000Ef00 : 0.000Ef00 : 0.000Et00 :
- - NR87 : CI : 0.000E+00 : 0.000E+00 0.000Ef00 1 0.000E+00 :
KR88 : CI ! 0.000E+00 ; 0.000E+00 0.000Et00 0.000EF00 :
KR89 : CI : 0.000E+00 : 0.000Ef00 0.000E+00 0.000EtOO :
! KR90 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0.000E+00 :
XE131M : CI : 0.000E+00 : 0 000Ef00 0.000E+00 0.000E+00 :
! XE133M : CI : 0.000E+00 0.000Ef00 : 0.000L+00 : 0.000E+00 ;
XE133 : CI : 0.000Ef00 0.000E+00 1 0.000Ef00-: 0.000E+00 :
- XE135M : CI : 0 000E+00 0.000Ef00 : 0.000E+00 1 0.000Ef00 :
- XE135 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
XE137 CI : 0 000Ef00 : 0.000E+00 1 0.000E+00 : 0.000Ef00 :
- XE138 : CI : 0.000E+00 : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 :
-TOTAL FOR : : : : : :
PERIOD : CI : 0.000E+00 0.000Et00 : 0.000Ef00 : 0.000E+00 :
(ABOVE) : : : : : :
- ENTER't C ] TO ERASE SCREEN AND CONTINUE : C 3
i
. - . ~ .- - . . .. -- - .. - -- .
PAGE 11 0F 12 UNIT: 01
. USER: MART .
DATE: 09/08/91-16:05 EFFLUENT AND WASTE DISPOSAL REPORT GASEQUS EFFLUENTS FOR RELEASE POINT: 4 HOT MnINTENANCE SHOP CONTINUOUS MODE PATCH NODE NUCLIDES : UNITS : QUARTER : OVARTER : QUARTER : QUARTER :
- RELEASED : 1 : 2 1 : 2 :
- 2. 10 DINES
' _: 1131 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
1133 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 1 0.000E+00 :
- - TOTAL FOR : : : : : :
- PERIOD CI : 0.000E+00 1 0.000E+00 ! 0.000E+00 : 0.000E+00 : )
- (ABOVE) : : : : :
- 3. PARTICULATES
- C14 : CI : 0.000E+00 : 0 000E+00 0.000E+00 : 0.000E+00 ,
CR51 : CI : 0.000E+00 0.000E+00 : 0.000E+00 : 0.000E+00 : ,
- MN54 : CI : 0.000Ef00 : 0.000E+00 0.000E+00 0.000E+00 :
FE59 : CI : 0.000Ef00 ! 0.000E+00 : C 000Ef00 0.000E+00 :
r
- - C058 : CI : 0.000E+00 0.000Ef00 0 000E+00 0.000E+00 : 5
-: C060
- CI : 0.000E+00 1 0.000Ef00 ! 0.000E+00 0.000Ef00 :
___------_______________._____.-__ __-____.________ ___ ___-_______.__ r
-ZN65 : CI : 0.000Ef00 ; 0.000E+00 0 000E+00 : 0.000E+00 :
SR89 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 1 0.000E+00 : ,
SR90 : CI : 0.000Ef00 : 0.000E+00 0.000E+00 : 0.000Ef00 :
! ZR95-
- CI : 0.000Ef00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
i SB124. : CI : 0.000E+00 : 0.000Ef00 1 0.000E+00 : 0.000Ef00 i
! CS134- CI : 0.000Ef00 : 0.000E+00 : 0.000Ef00 : OiOOOE+00 ! ;
- CS136 : CI : 0.000E+00 : 0.000Ef00 : 0.000E+00 1 0.000E+00 :
t
[
-____-.________---________-____--__._______-_-c.-___._-_____-_______
t
- CS137 : CI : 0.000E+00 : 0.000Ef00 : 0.000E+00 0.000E+00 : +
l t
ENTER C C] TO ERASE SCREEN AND CONTINUE : C t
p i
. _ _ . . __ _ _ _ . - . -_. .~_. _ . . . - - - - - . . _ _ _
.-- PAGE 12 0F 12
.- SITE: LINERICK UNIT U1 i USER: MART 4
DATE -08/08/91 16:06
- EFFLUENT AND WASTE DISPOSAL REPORT 1
GASEOUS EFFLUENTS _FOR RELEA9E POINT! 4 HOT MAINTENANCE SHOP CONTINUOUS MODE BATCH MODE
- NUCLIDES : UNITS : GUARTER . QUARTER : QUARTER : QUARTER :
! RELEASED : .: 1 1 2 : 1 : 2 :
- 3. PARTICULATES (CONTD) i BA140 '
CI : 0.000E+00 : 0.000E400-: 0.000Ef00 0.000E+00 :
CE141 : CI : 0.000E+00 0.000E+00 0.000E+00 : 0.000E+00
- CE144 : CI : 0.000E+00 0.000Ef00-: 0.000Ef00 : 0.000E+00 :
! TOTAL FOR : : : : : :
PERIOD : CI : 0.000E+00 0.000Ef00 : 0.000Et00 : 0.000E+00 :
(ABOVE) : : : : : :
ENTER C C 3 -TO ER ASE SCREEN A>'D CONTINUE : C e
. . ~. - . ..- . . . .- - , . . - ..- . . _
e II. TABLES B.
SUMMARY
OF RADIOACTIVE LIQUID EFFLUENTS January 1, 1991 to June 30, 1991 4
i 4, .
a
.'. UNIT:-U1 ;
USER: MART DATE: 08/08/91 16:06 EFFLUENT-AND WASTE DISPOSAL REPORT
. - }
LIQUID EFFLUENTS --
SUMMATION OF ALL RELCASES-
______.-_-_--_-__________________-_ ....____- 'l
.-___.._________________ ...__________________ l
- UNITS : QUARTER QUARTER EST. TOTAL: :
- : 1 : 2 : ERROR: % :
b A. FISSION AND ACTIVATION PRODUCTS ,
-__-____--___--__---________------_-_....._____~___-____-________-__.- .
1._ TOTAL RELEASE (EXCL.: CI : 0.185E-02 : 0.192E-01 : 0.630Ef01 ; i
- TRIT., GASES, ALPHA): : : : :
- 2. AVERAGE DILUTED UCI/ML- 0.2640-07
- 0.122E-06 : [
- CONC. DURING PERIOD : : : : !
- 3. PERCENT OF
- % : 0.000Ef00 0.000E+00 : !
- APPLICABLE LIMIT : : : :
3 l .B. TRITIUM- -
- 1. TOTAL RELEASE : CI : 0.607Ef01 : 0.516E+01 : 0.630E+01 : :
. _________________.. ________________-_______._______.._______ .________ r
- 2. AVERAGE DILUTED UCI/ML : 0.330E-04 :.0.327E-04 :
- CONC. DURING PERIOD : : : :
- 3. PERCENT OF : % : 0.000E+00 : 0.000E+00 : !
- APPLICA3LE LIMIT : : : : <
C. DISSOLVED AND ENTRAINED GASES 9
- 1. TOTAL RELEASE : CI : 0.132E-01 : 0.198E-01 : 0.630Ef01 : i
- 2. AVERAGE DILUTED !UCI/ML
- 0.719E-07 : 0.125E-06 : i CONC. DURING PERIOD : : : :
- l
- 3. PERCENT OF : % 0.3'.d-01 : 0.624E-01 : f 1
l : APPLICABLE LIMIT : : : :
l -
l c L D. GROSS ALPHA RADI0 ACTIVITY L 1. TOTAL RELEASE : CI : 0.000Et00 : 0.000E+00 : 0.000E+00 : l k
-E. VOLUME WASTE RELEASED l LITERS : 0.645E+07 : 0.608E+07 : 0.000E+00 :
- (PRIOR TO DILUTION) : : : : .
F. VOLUME DILUTION WATER LITERS : 0.184Ef09 : 0.158Et09 : 0.000Et00 :
- USED DURING PERIOD
- : : : :
i E N T E R . C ___C 3_TO. ERASE SCREEN AN@._G0HT3 NUT 3 C. _. -
1 PAGE 1 0F 5 -
- SITE!'L2MERICK'
- UNZT U1 USER: MART DATE 08/08/91 16:06 EFFLUENT AND WASTE D!SPOSAL REPORT L20dID EFFLUENTS FOR RELEASE POINT! 1 LIQUID RAD WASTE DISCHARGE TO SCHUYLKILL CONTINUOUS MODE BATCH MODE
- NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
- RELEASCD : : 1 : 2 : 1 : 2 :
- H3 : CI : 0.000E+00 : 0.000E+00 : 0.607C+01 : 0.516E401 :
r.
C14 i CI : 0.000E+00 : 0.000E+00 : 0.000L+00 : 0.000Ef00 1
-NA24 : CI : 0.000E+00 : 0.000Ef00 0.000Ef00 : 0.000E+00 :
! P32 : CI : 0.000Et00 : 0.000E+00 : 0.000E+00 1 0.000E+00 :
- CR51 .: CI : 0.000E+00 1 0.000E+00 0. 71E-02 : 0.980E-02 :
- NN54 : CI : 0.000Ef00 : 0.000Ef00 : 0.222E-03 : 0,136E-02 : .
- MN56 : CI : 0.;.0E+00 0.000E+00 : 0.000E+00 : 0.000Ef00
- FE55- : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- FE59 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0.257E-04 :
- C058 : CI : 0.000E+00 : 0.000E+00 1 0.187E-04 0.100E-02
- C060 : CI : 0.000E+00 : 0.000E+00 : 0 636E-03 : 0.164E-02 :
- NI63 : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0.000E+00 :
HI65' : CI : 0.000E+00 0.000Ef00 : 0.000Ef00 0.000E+00 l CU64 : CI : 0.000E+00 : 0.000E+00 ; 0.000E+00 : 0.000Ef00 :
- ZN65 : CI : 0.000E+00 : 0.000E+00 : 0.226E-02 0.36SE-02 :
- ZN69 : CI : 0.000E+00 : 0.000Ef00 : 0.000E+00 1 0.000E+00 :
- - BR83 : CI : 0.000E+00 : 0.000Ef00 ; 0.000Ef00 : 0.000E+00 :
-: - BR84 : CI : 0.000Ef00 1 0.000E+00 0.000Ef00 : 0.000E+00 : !
.....------------------- 1
- BR85 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
I ----------------------------------------------------------------------
ENTER-C C 3 TO ERASE SCREEN AND CONTINUE : C
s 1
l PAGE 2 0F 5
. SITE ' LIMERICK {
' UNIT: U1 USER! MART
, DATE: 08/08/91 16:07 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 1 LIQUID RAD WASTE DISCHARGE TO SCHUYLNILL CONTINUOUS MODE BATCH MODE NUCLIDES : UNITS ! GUARTER : QUARTER
- GUARTER : QUARTER :
- RELEASED : 1 : 2 : 1 : : :
LIQUID EFFLUENTS (CONTD)
RB86 : CI : 0.000E+00 0.000E+00 : 0 . 0 0 0 7. + 0 0 : 0.000E+00 1
- RB88 : U! 0.000E+00 0.000E+00 : 0.000E+00 1 0.000Ef00 :
RB89 ! CI : 0.000E+00 1 0.000E400 : 0.000Ef00 : 0.000Ef00-SR89 : CI : 0.000E+00 : 0.000Ef00 0.0002+00 : 0.000Ef00 SR90 : CI : 0.000Ef00 1 0.000Ef00 : 0.000E400 : 0.000E+00 :
-: SR91 : CI : 0.000E+00 0.000E+00 : 0.000E+00 : 0.000E+00
_----- - ----------s .______---_.-----._--...--------------
.SR72- : CI 0.000E+00 0.000E+00 : 0.000E+00 : 0.000Et00 :
- Y90 : CI : 0.0COE+00 0.000E+00 0.000Ef00 : 0.000Ef00 :
- .Y91M : CI : 0.000E+00 : 0.000E+00 0.000E+00 0.000E+00 :
! Y91 : CI : 0.000E+00 : 0.000Ef00 : 0.000E+00 : 0.000E+00 :
- Y92 : CI : 0.000E+00 : 0.000E+00 : 0 000E+00 : 0.000E+00 :
- Y93 : CI : 0.000E+00 : 0.000E400 0.000E+00 : 0.000E+00 :
- ZR95 : CI : 0.000E+00 : 0.000E+00 0.000Ef00 0.498E-05 :
- ZR97 : CI- 0.000E+00 : 0.000E+00 1 0.000E+00 : 0.000E+00 NB95 : CI : 0.000E+00 0.000Ef00 0.000E+00 0.498E<05 :
- M099 -
- CI : 0.000E+00 : 0.000E+00 0.000E400 : 0 000E400 1
- TC99M : CI : 0.000E+00 0.000E+00 1 0.214E-05 : 0.117E-03 '
l TC101 : CI 0.000Ef00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
p-ENTER C C J TO ERASE 3CREEN AND CONTINUE : C 1
a i
PAGE- 3 0F 5 . .
i SITE: LIMERICK UNIT: U1
-USER:-MART DATE: 08/08/91 16:07 -
EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT! 1 LIQUID RAD WhSTE DISCHARGE TO SCHUYLKILL '
CONTINUOUS MODE DATCH MODE
- - _ _ _ _ _ _ _ _ _ _ _ _ . . . . - _ . - - - - _ _ _ _ - _ _ _ - - _ r
- NUCLIDES : UNITS : GUARTER : QUARTER : QUARTER ! OUARTER :
RELEASED : : 1 : 2- l 1 LIQUID EFFLUENTS (CONTD)
RU103 : CI 0 000E+00 1 0.000E+00 : 0.0000+00 : 0.000E+00 :
- RU105 : CI : 0.000Ef00 : 0.000E+00 0.000E+00 1 0.000E+00 : ,
---__- ___________--___---___-___-_-______.---__---___.__-_-____-____- 3
- RU106 : CI : 0.000Ef00 0.000E400 : 0.000E+00 : 0.000E+00 ;
AG110M : CI : 0.000Ef00 : 0.000E+00 0.000Ef00 : 0.000E+00 :
i TE125M : CI : 0.000Et00 : 0.000E+00 1 0.000E+00 : 0.000E+00 :
- TE127M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE127 : CI : 0.000Ef00 : 0.000Ef00 : 0.000E+00 : 0.000E+00 :
l : TE129M : CI : 0.000Ef00 : 0.000E+00 : 0.000Ef00 : 0.000E+C0 :
- TE129 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
l L TE131M : CI : 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0.000Ef00 :
j ________-_-______--_.---___.-_______-___ ---___-_._--__..--___________
l
- . TE131 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
- TE132 : CI : 0.000Ef00 1 0.000E+00 : 0.000E+00 : 0.000E+00 l I130 : CI : 0.000E+00 : 0.000E+00 ; 0.000E+00 : 0.000E+00 :
l : I131 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
( .--___-_________________--________________--__-_________ -__.--. _-___
I
- CI I132 : : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
1
! I133 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
\
- I134 : CI : 0.000E+00 0.000Ef00 0 000E+00 : 0.000E+00 :
- I135 : CI : 0.000E+00 0.000Ef00 : 0.000E+00 : 0.000E+00 :
- ENTER C C] TO ERASE SCREEN AND CONTINUE
- C i
l
r 1
, 1 ,- PAGE 4 0F 3
. SITE: L?MERICK
- UNIT: U 1_ ;
USER: NART DATE -08/08/91 16:08 EFFLUENT AND WASTE DISPOSAL REPORT ;
LIQUID EFFLUENTS FOR RELEASE POINT: 1 LIQUID RAD WASTE DISCHARGE TO SCHUYL NILL ! >
1 CONTINUOUS MODE BATCH MODE !
NUCLIDES : UNITS : GUARTER : QUARTER : QUARTER : QUARTER : 1 F
- RELEASED : 1 : 2 : 1 : 2 :
i 6
LIQUID EFFLUENTS (CONTD)
~
- CS134
- CI : 0.000i+00 : 0.000E+00 : 0.000E+00 0.462E-03 : ;
CS136 : CI 1 0.000E+00 1 0.000Ef00 0.000Et00 : 0.000Ef00 : f
_____________________________._________________.._______________..-._____ i
- CS137 : CI : 0.000E+00 0.000E+00 : 0.423E-05 : 0.115E-02 : l
- CS138 : CI : 0.000Ef00 1 0.000E400 l-0.000E+00 : 0.000E+00 : l BA139 : CI : 0.000E+00 0.000E+00 0.000Et00 ! 0.000Et00 r i
- BA140 : CI : 0.000E+00 0.000E+00 : 0.000E+00 : 0.000E+00 : '
___________________________ ____________________c_____________________
- BA141 : CI : 0.000E+00 : 0.000E+00 ! 0.000E+00 : 0.000E+00 : ;
BA142 CI '
- - : : 0.000E+00 : 0.000E+00 : 0.00 0.000Et00 :
___________________________________________________.0E+00 __________________ 1
- LA140 : CI : 0.000Ef00 0.000E+00 0.000EiOO : 0.000E+00 : ;
! LA142 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CC141
- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : !
- CE143 : CI : 0.000E+00 0.000E+00 : 0.000E+00 1 0.000E+00 :
- CE144 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.142E-04 : i PR143 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
______________________________________________________________________ t f
- PR144 : CI : 0 000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : i t
)
- - ND147 : CI ! 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : ;
- - AS76 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 0.000Ef00 : ;
r
- W187 : CI : 0.000E+00 : 0.000E+C0 : 0.000Ef00 : 0.000E+00 a 1
ENTER C C ] TO ERASE SCREEN AND CONTINUE : C I
T
- . . _ - . .. . ~ . . ._ -- -. - . - - - . - _ - . - - -. ._-
i i
PAGE 3 0F 5 *
- l SITE -. LIMERICK i
UNIT: U1 !
USER: MART DATE: 08/08/91-16:09 ' i EFFLUENT AND WASTE DISPOSAL REPORT
- i.
L! QUID EFFLUENTS FOR RELEASE POINT! 1 LIQUID RAD WASTE DISCHARGE TO SCHUYLNILL I i CONTINUOUS MODE PATCH MODE :
__ ----- ..-_-_------------_-.....---_...__-----_ --------__...-- i l NUCLIDES : UNITS : GUARTER
- OUARTER : QUARTER : QUARTER : !
- RELEASED. : : 1 ; 2 : 1 : 2 : I
_____--------.._..---_-----------. -_.------ .-----____.---__---.__. F LIQUID EFFLUENTS (CONTD) !
NONE : CI : 0.000Ef00 : 0.000E+00 : 0.000E400 6 0.000E+00 -
_.... -----__-_--_ --------.. -----___.-_ ---------------------- t
___-- ------- _--____-________-_______----- __.-_-____--_______..._--.. )
! TOTAL FOR. : ! : : : : ;
- PERIOD
- CI : 0.000Ef00 ' O.000E+00 : 0.607Ef01 : 0.518Ef01 :
- (ABOVE) ! : : : : : i
[
........n------....--------_---_______..--_.... _.-----___ ,
- XE-133 : CT : 0.000E+00 : 0.000Ef00 : 0.737E-02 : 0.143E-01 :
- XE-135 : CI : 0.000E400 1 0.000Ef00 1 0.586E-02 0.552E-02 :
I
.. .---,...--+--------------_--_--_-__----------_- . ___-----_---- ,
i EFFl.UENT RELCASE
SUMMARY
CPTIONS j a TrAMINA' h 2 -- ACCUMUL GASEQUS RELEASES '
3 -- ACCUMUL .fE LIQUID RELEASES 5 c
4 - PRINT WASTE
SUMMARY
REPORT '
s-ENTER OPTION SELECTION C 1-4-J : 9 l
1 t
I 5
6 6
v 5
v 4
e f a
b b
... \ .
II. TABLES C. SOLID WASTE DISPOSITION REPORT January 1, 1991 to June 30, 1991 -
A f
9 0
9 9
\
I' 5
PAK 17 4 f
)
i l
f i
SOLID ETE AND 1RRADIATED REL SHIPENTS i PERIOD 0!'01/91 TO 87/01/91 A. SOLID WASTE SHIPPED FFSITE FOR BURIAL OR DISPOSAL (NOT 1RRADIATED FUEL) l
- 1. TYPE OF WASTE UNIT IRROR, 1 6 MONTH PERIOD
)
L i
- a. SPENT RESINS '!LTER SLUDGES, m3 2.81E+02 : ;
EWORATORBbiTOMS,ETC.- C1 2.72E+42 251 !
m3 2. 2E+41 'l G. DRY C W .7SS!BLE CONTAM!$TED EQJIPENT, WASTE,ClETC. 4.88E+00 251 i
- c. IRRADIAID C31PGETS, a3 8.80C+40 '
CONTR3. RODS, ETC. Cl 8.8EE+40 i
- d. OTER (DESCRIBE) a3 2.08E+00 .
. CRD FILTERS 4 TRASH Cl 1.19E+41 251 &
.690RTIONS 7 TE WASTE IS PROCESSED BY OFFSITE WNDORS (QURDREX, SES) .
ACTIVITY IS ESTIMTED. . ,
l 1
e 6
L' .
PAGE 2 0F 4
- 2. EST!mTE OF MJOR WCL!DE COMPOS!TI(N (BY TYPE OF mSTE)
CATEGORY A - SPENT RESINS CATEGORY B - DRY COMPRESSIBLE CATEGORY D " CRD FILTERS, 8 FILTER SLUDES, EVAPORATDk WSTI CONTARINATED TRASH BOTTOMS, ETC. EQUlPENT, ETC.
ISOTOPE WASTE (1 ASS A WASTE CLASS A WASTE Q. ASS A ACTIVITY 1 ASUNDANCE ACT!vlTY 1 ABLNDANCE ACTIVITY 1 ABUNDi4Cc Cl Cl Cl Zn-55 7.02E+01 25.761 2.59E+00 53.091 4.20C+00 35.251 Cr-51 1.38E42 47.711 6. 8E-85 0.001 2.41E+00 20.221 Cs-137 1.81E*01 6.641 1.18E 80 24.191 2.80E40 16,781 Cs-134 9.14E+M 3.351 6.48E-91 13.121 1. 01E+M 8. 481 1-131 8.NE46 8.Bei 8.80E40 8.801 9.80E+90 8.801 Co-64 1.32E+01 4.841 1.L8E-91 3.281 7.14E-91 5.991 Co-58 1.01E+41 3.711 2.03E-92 9.421 3.69E-91 1.191 Fe-55 9.38E+90 3.411 1.99E-01 4.681 5.7tE-91 4.791 Sr-89 0.00E+00 0.001 1.58E-92 0.311 1.12E-93 0.011 C-14 6.63E42 0.821 6. 4M43 0.13% 2.78E44 0.801 Mn-54 1.15E+41 4.221 2.40E-92 9.491 5.69E41 4.701 Nb-95 0.00E40 0.001 2. 40E43 8.851 2.34E-93 8.821 H-3 1.01E-91 0. 041 1.19E-03 0.021 7.12E-95 0.001 Ba/La-140 0. 00E+M 0.001 0. 0M+00 0.891 0.00E40 0.001 N1-63 7.76E-91 0.281 3.3M-92 0.681 7.27E42 0.611 118e 0. 00E+M 0.001 8.8eE40 0.001 3.68E-97 0.001 Ag Zr- 95 9.80E+00 8.801 8. NE +90 8.001 8.80E+00 8.001 P-32 8.80E+00 8.801 5.30E43 0,111 3.72E43 8. 031 Sr-90 4.09E43 0.001 3. E18E-94 0.011 8.26E-94 0.011 Co-242 0. 00E+M 0, Bel 4.61E-96 0.001 4.61E-96 8*
Pu-241 8.40E40 8.891 0,80E+90 8.801 0,80E+90 0.001 1-129 0,80E+90 6.891 9. 00E40 8. M1 8.00E+00 8. Oft
. . Tc-99 0.00E+00 0.891 0.00E+00 0.001 0.80E+00 0.001 Nb-94 0. 88E+M 0.001 0. 00E+M 0.801 0. 00E+M 0.001 Nt-59 2.78E43 v.891 0,80E+00 8.801 8.00E+00 0,801 Co-57 0,80E+90 8.801 8.80E+90 0,801 8.00E+00 8.801 te-141 9.00E+00 8.891 8.00E+00 0,801 0,80E+90 8.801 Ce-144 0.9E+M 0.801 1.20E43 0.021 1.17E43 0.011 TOTALS 2.72E+92 100.861 4.88E+90 100,801 1.19E41 100.8et ACTIVITY 15 ESTIMATED.
CATEGORY A (37 TYPE A LSA 01 CATEGGRY C (NO SHIPENTS E)17 T A LSAll CATEGORY B (19 TYPE A LSA)...EtCATEBORYCIS1RRADIATEDC CONTRCL RODS, ETC. CATEGCRY 6 (0) TYPE A LSA). NOTE: CATEGORY D IS CRD FILTERS AND TRASH.
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_ u. _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ . . _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ , _ . _ _ _ _ _ _ _ _ _ _ _ _ ,
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PAGE 3 0F 4 *
- 3. SOLID WASTE DISPOSli!ON NUMKR OF 21PENTS MDDE OF TRANSPORTATION DEST!NRTION
'8 TRJCK LITRICK TO imRM1L 7
TRUCK GJADREI TO MPMELL 6 TRUCK SEG TO MkNIELL 1 TRUCK SES TO R!DLAND 4
TRUCK SES TO KATTY e
r e
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. P%E 4 Of 4
- 9. !FR@!ATED ITL SH PENTS (DISRE!!!DN)
M,MKR Or DH]f(NTS E (F TRIMPORTAi!CN DESf!WT10N NO SHIPENTS M COMMENTSt 2 Sn!PTNTS KRE M FrJR Ll(R!CK TO Qu@'O FOR PROCESSING.
8 SH!fENTS KRE %DE FMM Ll(RICK TO SE6 FOR PROCESSING.
NO SOLID!FICATIONS WERE W .
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IZZ. A,TTACHMENTS -
A. SUPPLEMENTAL INFORMATION Facility: Limerick Generating Station - Units 1 and 2 Licenses NPP-39 (Unit 1) and NPP-85 (Unit 2)
- 1. Regulatory Limits (Technical Specification Limits)
A. Noble Gases:
1 1 500 mRems/Yr - total body " instantaneous" limits 1 3000 mRems/yr - skin per Tech Spec 3.11.2.1 and ODCM Control 3.3.2
- 2. $ 10 mRads - air gamma quarterly air dose limits 5 20 mRads - air beta per Tech Spec. 3.11.2.2 and ODCM Control 3.3.3
- 3. < 20 mRads - air gamma - yearly air dose limits E 40 mRads - air beta
~ per Tech Spec. 3.11.2.2 and ODCM Control 3.3.3 B. Iodines, tritium, particulates with half life > 8 dayst
- 1. $ 1500 mRems/yr - any organ " instantaneous" limits (inhalation path) per Tech Spec. 3.11.2.1 and ODCM Control 3.3.2 .
- 2. $ 15 mRems - any organ quarterly dose limits per Tech. Spec. 3.11.2.3 and ODCM Control 3.3.4
- 3. 5 30 mRems - any organ - yearly dose limits per Tech. Spec. 3.11.2.3 and ODCM Control 3.3.4 C. Liquid Effluents:
- 1. Concentration < 10CPR20 " instantaneous" limits per Appendix B, Ta51e II, Col. 2 Tech. Spec. 3.11.1.1 and ODCM Control 3.2.2
- 2. $ 3 mRems - total body quarterly dose limits per 5 10 mRems - any organ Tech. Spec. 3.11.1.2 and ODCM Control 3.2.3
- 3. $ 6 mRems - total body - yearly dose limits per 5 20 mRems - any organ Tech. Spec. 3.11.1.2 and ODCM Control 3.2.3
- 2. Maximum Permissible Concentrations Per LGS ODCM Control 3.2.2, MPCs-are not used to calculate permissible release rates and concentrations for gaseous releases.
Tne MPCs specified in 10CFR20, Appendix B, Table II, Column 2 for identified nuclides are used to calculate permissible release rates and concentrations for liquid releases, t
{
- 3. Avorogo Enorgy r Based on gaseous effluent releases for the report period, average beta energy is 0.104 MeV and sverage gamma energy is 0.034 MeV. "
- 4. Measurements and Approximations of Total Radioactivity A. Fission and Activation Gases t l
The method used is the Canberra Series 90 Counting System; GS --Gas Marinelli. !
e B. Iodinet
\
The method used is the Canberra .3 ries 90 Counting System !
CH - Charcoal Cartridge. !
C. Particulate:
The method used is the Canberra Series 90 Counting System I PT - Air Particulate Sample, 47 mm filter. !
D. Liquid Effluents:
The method used is the Canberra Series 90 Counting System I and the RadWaste Liquid Discharge Pre-Release Method with ;
a 3.5 liter Marinelli. t i
- 5. Batch Releases !
l A. Liquid Q1 02 k
- of Batch Releases 75 159 !
i Total time period for batch releases,
- 5301 10947 !
Maximum time period for a batch release,
- 94 125 i r
Average time period for batch release,
- 70.68 68.85 !
Minimum time period for a batch release,
- 43 30 l
'r Average stream flow (Schuylkill River) 1.07E6 6.72E5 during periods of release of effluents l into a flowing stream, gpm l l
l
- a Minutes ,
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. - . . _ - . , - . . - - ~ .. .- . . . - - ~ , - . . - . _ . _ . . - , , .--
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+ l D. Gesnoun 01 02
- of Batch Releases: 1 6
) Total Time period for batch releases,
- 60 6180 Maximum time period for a batch release, a 60 1560 Average time period for batch release, a 60 1030 Minimum time period for a batch release,
- 60 420 i
- = Minutes
- 6. Abnormal Releases A. Liqui,d 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 5 = City of Philadelphia Crew Course l
4
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- I 283. ATTACHMENTS 1 l
D. PROCESS CONTROL PROGRAM (PCP), REVISION 9 The Solid Radwaste Process Control Program (PCP) has been incorporated into the Radwaste procedure series. A copy of RW-800 is included in this report. The following summarizes changes made to i the PCP in the process of converting it into RW-800: !
- 1. Section 6.1.1 was added to clarify the processing of non-ccontaminated waste.
t 2.
Section 6.1.5 was added to indicate the method of dry active waste !
(DAW) processing.
l
- 3. I Section 6.1.7 was added to indicate the technique for irradiated i reactor component processing. !
- 4. Section 6.1.8 was added to address miscellaneous filters processing.
s
, 5. Section 6.3.1.2 was resvised to allow use of smears taken at various ;
plant locations for DAW classification. I I
- 6. Sections 6.3.1.3 - 6.3.1.5 were added to clarify classification techniques for oily waste, irradiated components, and miscellaneous ,
filtcts.
- 7. Section 6.3.1.6 was added to address a new Surveillance Test for !
inspecting new isotopic data (ST-ORRR-734-0). !
- 8. Section 6.3.1.7 was added to address future waste generation.
4 l
- 9. Section 6.4.2.1 was revised to describe the technique for providing long term vertical stability to polyethylene high integrity f l
containers (HICS). .
- 10. Section 6.5 was revised to provide additional controls for re' rising ;
the PCP beyond those controls needed for revising other "RW-series" i procedures, t
- 11. Section 7.11 was added to describe rather than list the documents I considered "PCP Implementing Procedures". ;
- 12. Section 7.20 refers to new Surveillance Test (ST-0-RRR-734-0) i referred to in item 7 above. i
- 13. Attachment 8.2 was added to clarify various definitions of terms use in the PCP. '
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RW-800, Rev. O, i ,
Pago 1 of 19 .
NJH/ WPM /KJC/ds1 m , . -s . ,,
i P!!!LA00' PH! A P'.COTR!C COMPANY L MERICK GENERAT!NG STATION (f / /g/['Q l RW-S00 SOLID RADWASTC SYSTru PROCESS CO!aTROL PROGRAv. (PCP) 1.0 P'J R P OS E Plant Technical Specif!:st::n : 4.11.3 requires the Sclid Radwaste Processing System :: be used in accordance with a Process Control Program to meet transportation and disposal s:te requirements. This program provides guidance and boundary conditions for preparation of specific procedures f: processing, sampling, analysis, packaging and snipment of solid radwaste in accordance with State and Federal Regulatory requirements.
1.1 This program is applicable to the Li'merick Generating Station Solid Radwaste Processing System. It is the intent of the Process Control Program to provide reasonable assurance of meeting the regulations and to demonstrate ecmpliance with 10CTR61 by:
- a. Defining the various waste streams.
- b. Establishing a set of process parameters that affect solidification and developing operational controls for those parameters.
- c. Implementing a Waste classification System in accordance with 10CFR61 and applicable Regulatory Guidance,
- d. Providing an appropriate Quality Control Program as required by 10CFR20.311.
- e. Implementing procedures for processing, containerization and transport of waste to ensure specific DOT, NRC, and burial site requirements are satisfied.
2.0 RESPONSIBILITY NOTE: The station operating organization is outlined in'section 13.2 of the UFSAR. ,
2.1 PORC is responsible for reviewing all revisions to the'P,CP.
2.2 The Plant Manager is responsible for approving all revisions to the PCP.
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RW-800, Rev. O !
- Page 2 of 19 r NJH/WrM/KJC/dsl
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2.3 The Nuclear Quali+y Assurance Department performs audits to !
ensure compliance with the Quality Arsurance Plan.
I 2.4 All PECo and PECo contract personnel are responsible for ;
implementation of precedures and good practices so as to
- provide quality Assurance and maintain exp;sures ALARA.
2.5 The Engineer-Radwaste is resp:nsible for:
2.5.1 Compliance with this Pr::ess Centr:1 Program.
2.5.2 Record keeping and document control of shipping and processing data. ;
i 2.5.3 Assuring that radwaste personnel are appropriately l trained and qualified.
t 2.5.4 Coordinating reviews and revisions to this document I and corresponding implementing procedures.
2.5.5 Reviews and revisions to this PCP and its [
implementing procedures.
l 2.6 The Superintendent-Operations is responsible for
. 2.6.1 Providing trained personnel to operate appropriate h radwaste process equipment. j 2.6.2 Defining those Operations positions which require i training, i 2.7 The Superintendent-Training is responsible for: [
2.7.1 Development and implementation of performance-based t training for designated personnel utilizing the Training Systems Development (TSD) model in accordance with Training Division procedures.- !
t 3.0 PREREQUISITES 3.1 Prior to revising or deleting a PCP implementing procedure, ,
the_ preparer-shall review the procedure against the PCP to i ensure that there is no compromise or conflict. !
r l -3. 2 Prior to a modification to an inplant liquid radwaste r processing system the individual responsible for the MOD ;
l shall review to ensure that it is not in conflict with or i l compromises the PCP. When conflict or compromise is i l identified it shall be resolved. .
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RW-800, Rev. O, i .
Page 3 of 19 .
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-. 3.3 Processing of solid radicactive .recte chall be performed by qualified and tra:ned perscnnel. Training records for operators of mobile vendor prccessing units shall be maintained by the Encineer Radwaste wnile the vendor is active on-site. These reccrds sha'.; be sent to the Nuclear Reentds Management System after the vendor has completed work on-site.
3.4 Vend t services may be used for radicactive waste processing provided :ne serv;ces are governed by an NRC approved Topical Repcrt. Processing of radioactive waste by on-site vendors snall be performed in accordance with applicable Topical Report, procedures and NRC guidance.
3.5 The Topical Reports of vender supplied radwaste processing systems shall undergo review by the Engineer-Radwaste (or designee). The review shall ensure the vendor supplied system will be compatible with plant operations and that the Topical Report has been submitted to the NRC for review. The review shall be performed in accordance with applicable RW procedures. Management review shall include a review of plant-to-vendor equipment interface.
3.6 On-site processing radioactive waste shall be performed in accordance with approved station procedures.
3.7 Quality Assurance shall be maintained as defined by the Limerick Quality Assurance Plan.
4.0 PRECAUTIONS 4.1 Revisions to the PCP (RW-800) must be reviewed by PORC and approved by the Plant Manager (Ref. 7.19).
'4.2 Sections of the PCP (RW-800) referring to Generic Letter 89-01 (Ref. 7.18) shall not be deleted without the approval of the Engineer-Radwaste.
4.3 The Process Control Program (RW-800) 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.
4.4 Changes to the PCP (RW-800) 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. This shall be done in accordance with ODCM Section I3.6.
4.5 Changes to resin dewatering implementing procedures or systems shall require verification that the free standing water content of the packaged product is within the limits established by regulatory limits via ST-0-RRR-733-0.
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RW-800, Rev. 0 Pago 4 of 19 NJH/WFM/KJC/dsl
. . 4. 6 When processing does_nmt meet disposal site and shipping and transportation requirements, shipment shall be suspended and the Drocess Contrcl Program (RW-800), the implementing procedures and/cr the solid waste system shall be corrected as necessary to prevent recurrence (Ref.
7.18).
4.7 When processing is not performed in accordance with the Process Control Program, the impreperly precessed wacte in each container shall be reprocessed to conform to PCP (RW-800) requirements and appropriate administrative action shall be taken to prevent recurrence.
5.0 APPARATUS N/A 6.0 PROCEDURE Vendor services may be used to process any radioactive waste stream provided the services are performed with an acceptable Process Control Program.
. 6.1 Process Description All waste streams are defined in Attachment 8.2.
Processing of solid radioactive waste shall be performed by properly trained and qualified operating personnel.
6.1.1 NON-CONTAMINATED WASTE - Processed as ordinary (non-radioactive) waste and is disposed of in accordance with applicable station procedures.
6.1.2 CONDENSATE TILTER /DEMINERALIZER SLUDGE 6.1.2.1 Each condensate filter /demineralizer i
backwash consists of approximately 9,000 gallons of slurry with approximately 350 lbs. (dry wt.) spent resins and crud.
6.1.2.2 Successive backwashes are collected and allowed to settle in a Condensate Phase Separator. As the sludge settles, clarified liquid is decanted.
6.1.2.3 For centrifuge dewatering of the' settled sludge, the phase separator is isolated when approximately 240 cubic feet of
, sludge has accumulated.
i HW-800, Rev. O. *
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!JJH/ WPM /PJC/dsl I l
i t 1.S 4 Ter vend:r Jewatering of the c.ettled !
sludge, tne pnase separater is asciated !
when approximately 400 cubic feet rf _!
sludge has accumulated.
l 6.1.2.5 Tne settled sludge is ready for dewatering wh11e further backwashes are rcuted to alternate phase separaters.
6.1.2.6 ne pnase separator contents are recirculated for a minimum of 30 minutes to mix contents of the vessel, resulting in a homogenous resin slurry. (For centrifuge dewatering, the mixture should not exceed 5% dry weight concentration.
Ter Vender dewatering a higher concentration can be acheived.
6.1.2.7- Tne solids slurry is then fed to a centrifuge or to the External Processing Station for dewatering as appropriate.
6.1.3 h'ASTE SLUDGE 6.1.3.1 Each backwash from a radwaste or fuel pool filter demineralizer consists of approximately 1,500 gallons of slurry, with approximately 60 lbs. (dry wt.) ,
spent resins and-crud.
6.1.3.2 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).
6.1.3.3 Successive backwashes from radwaste 4
filter demineralizers, radwaste demineralizers, and_ fuel pool filter /demineralizers are collected in the Waste Sludge Tank until approximately 12,000 gallons cf liquid and resin sludge are accumulated.
n RW-800, Rov. 0 page 6 of 19 NJH/WTM/KJC/ds1 4
6.1.J.4 .The Waste Slud:e Tank contents are recirculated f er a minimum of 45 minutes
, to mix contents of the tank, resulting in-a hemogeneous resin slurry ranging frcm 0.5 to 61 (dry wt.) total solids.
Dur!,ng norma' operation the Waste Sludge Tank contains only the radwaste and fuel pool filter deminerall:er backwashes
' which result in a 0.5'. (dry wt.) total solids concentration. Periodic radwaste deminerali:er backwashes will increase the solids level to approximately 3% (dry wt.) for one bed or 6% (dry wt.) for two beds.
6.1.3.5 The solids slurry is fed to a centrifuge I 3
for dewatering or to the External '
Processing Station for dewatering as appropriate.
6.1.3.6 Waste Sludge Tank contents may also be sent to a condensate phase separator for processing in accordance with Section, 6.1.4 REACTOR WATER CLEANUP FILTIR/DEMINERALIZER SLUDGE t 6.1.4.1 Each RWCU filter /demineralizer backwash consists of approximately 1,100 gallons of slurry with approximately 48 lb. (dry wt.) spent resins and crud.
6.1.4.2 Successive backwashes are collected and allowed to settle in a phase separator.
As the sludge settles the clarified liquid is decanted.
6.1.4.3 For centrifuge dewatering of_the settled sludge, the phase separator is isolated when approximately 140 cubic feet of sludge has accumulated.
6.1.4.4 For vendor dewatering of the settled sludge, the phase separator is isolated when approximately 160 cubic feet of sludge has accumulated.
6.1.4.5 The settled sludge is ready for dewatering while further backwashes'are routed to alternate phase separators.
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RW-600, Rov. A 8 Page 7 of-19 .;
NJH/WrM/KJC/ds1 ;
I 6.1.4.6 7 5 e. phcsc--reparator contents are f
recirculated for a minimum of 30 minutes to mix centents et the vessel, resulting in a homogeneus resin slurry. (ror centrifuge dewatering. the mixture should :
net exceed 5\ dry weign: concentration. :
T:t Vendor dewatering, a higher !
cencentrat10n can be ach:eved). !
6.1.4.7 Tne sclids slurry is then fed to a centrifuge or the External Processing :
Station for dewatering as appropriate. !
I Note: Resan sludges fr:r different waste streams and different units may be mixed to optimi:e packaging and j enaracterization, h: wever, these quantities shall be ;
documented. t 6.1.5 DRY ACTI\E WASTE (DAW) !
i 6.1.5.1 DAW is processed by an off-site vendor j prior to disposal. >
I 6.1.6 OILY WASTE l' 6.1.6.1 Oily waste generated daring operation and *!
maintenance is 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. i 6.1.6.2 Oily waste can be solidified in !
appropriate containers by vendor supplied .i equipment in accordance-with approved !
vendor process control procedures. !
't 6.1.6.3 Oily waste may be processed through ;
decontamination to levels which may be e free released as non-contaminated !
material or non-contaminated waste. The' !
contaminated byproducts of this ,
decontamination process may be processed I as DAU. -
l 6.1.6.4 Oily waste may be shipped off-site for i processing by appropriate vendors on the !
PECo evaluated vendors list. !
i l
m--w_ g.. , _ v. - , , w,.-e,, - - - - - - . , -
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- w. ,,,,.m,%%,....e,,,--m-_-,- ,-i-,,,
. ,m.:.,,, 1-y,-,---e., - - - - ,
RW-000, Rev. 0 8
Pago 8 of 19 ,
NJH/WFM/XJC/ds1 I 6.1.7 !RRADIATCD RCACTOR COMPONENTS 6.1.7.1 Irradiated reactor c mponents are campled cut as nececcary, loaded inte liners in ace:rdance w tn applicable station precedures.
6.1.5 MISCCLLANCO'JS TILTERS 6.1.8.1 CRD filters are leaded into appropriate containers and shipped for burial in accordance with applicable station procedures.
6.2 DEWATERING PROCESS CONTROL 6.2.1 Centrifuge Resin Sludge Dewatering 6.2.1.1 The 0.5-61 solids slurries' discussed in Section 6.1 are fed to a centrifuge at a controlled flew rate for dowatering.
6.2.1.2 Operating variables such as centrifuge pond setting, bearing temperatures, equipment vibration, 1 differential torque are monitored insure optimum centrifuge operation and compliance with the free standing water criteria.
6.2.1.3 The centrifuged 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.
6.2.2 Vendor Resin Sludge - tering 6.2.2.1 The slurries discussed in Section 6.1 are fed to Vendor dewatering systems at approximately 30 to 50 gpm via the External Processing Station located in the Radwaste Truck Bay.
6.2.2.2 Vendor-dewatering operating variables such as waste type, process time, pump suction pressure, blower inlet pressure, ambient temperature and percent relative humidity are monitored to ensure optimum operation and compliance with the free
, standing water criteria for burial.
RW-800, Rov. O. . .
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. 6.2.2.3 Vendor dowe+ered resin is packaged in appropriately celected liners or High Integrity Containers (H:C). Process system level probes and/or video cameras mounted within the fill head ensure the liner cr HIC is filled witnout undue void spaces to the maximum extent practical.
6.2.2 Appreved Resir Sludge Dewatering Venders 6.2.3.1 T:: Vender dewatering described in Section 6.1 and 6.2 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 NP-A previously submitted to the NRC.
6.2.3.2 F:r Vendor dewatering described in Section 6.1 and 6.2 the LN Technologies / Stock Equipment Co. Quick Dry Process may be utilized. A description of the LN Technologies / Stock Equipment Co. equipment and p"ocess method may be found in Topical Report SRS-003-P, previously submitted to the '
NRC.
6.2.3.3 for Vendor dewatering described in
- Sections 6.1 and 6.2, 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, previously submitted to the NRC.
6.2.3.4 For Vendor dewatering described in Sections 6.1 and 6.2, the Westinghouse-
.. Hittman Nuclear dewatering equipment may be utilized. A 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.
6.3 10CRF61 IMPLEMENTATION 6.3.1 Waste Classification - A computerized waste classification and shipping program, RADMAN, 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 or not applicable,
RW-800, Rev. 0 Page 10 of 19 l
l NJH/WrM/KJC/dsl 6.3.1.1 Pt DCWATERCS RCSIN, waste classifteation
- sha!! be based upon dese-to-curie calculati n and the use of ccalinc facters frr hard to .meacute isotopes.
After each centa:ner fill, appropriate dese rates are :btained and entered into cadran.
6.4.1.2 10: DRY ACTIVE WASTC (DAW), waste classificati:n shall de based upon isetcpic analysis and the use of scaling factors for waste sludge er representative smears along with dese-to-curie conversion.
6.3.1.3 Ter O!LY WASTC, waste classification chall be based upon isotopic analysis and the use of scaling factors for hard to measure isotepes. A detailed analysis is performed on each batch to be processed and packaged. Actual oil samples or an appropriate surrogate may be used for classification.
6.3.1.4 for irradiated reactor components, waste
,. classification is performed through direct sampling analysis or by activation analysis. This is performed on a case by case basis.
6.3.1.5 for MISC. Filters, waste classification i
shall be based upon dose to curie calculation and the use of scaling factors for hard to measure isotopes.
6.3.l'.6 A detailed analysis is performed annually to identify isotopic abundances and scaling factors through use of ST-0-RRR-731-0, ST-0-RRR-732-0, and ST-0-RRR-734-0.- ;
l 6.3.1.7 Radionuclide concentrations and classification of future waste shipments are expectea to be similar to those of previous shipments for each specific waste stream. Values are available from shipment manifest forms.
6.4 WASTE STABILITY
. 6.4.1 Minimum Stability Requirement l
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6.4.1.1 Waste at=.imerick Generating Statien is t packaged in meta, :ntainers (drums, l coxes, liners) ct Hipn Integrity C ntainers. :n n care shall radioactive ('
wacte de packsged in cardb:ard or ;~
fiberboard e:xec for burial.
t v.4.1.0 ;ewatered resin is sampled annually as a l m:nimum to verify the free standing water t c:ntent of the packaged product is within !
- ne limits established by applicable i regulatory limits via ST-0-RRR-733-0. '
In additi:n to the annual verification, the free standing water is determined i whenever process changes occur that may i significantly alter system dewatering }
. performance. Performance of ST-0-RRR- !
733-0 serves as a demonstration of system I operability and for ensuring the waste form is similar to that indicated in prequalification testing. j t
6.4.1.3 To prevent accumulation of radiolytically .
generated combustible gas in greater than i Type A radioactive waste packages I containing water and/or organic *!
substances, one or more of the following l measures are taken: !
'i 1, The container is equipped with a i vent to prevent accumulation of such !
gas. !
- 2. A determination by calculation, ;
test, or measurement is performed to- i ensure that hydrogon generation is L limited to a molar quantity that !
would be no more than 51 by volume !
of the secondary container gas void [
at STP over a period of time that is i twice the expected shipment time. ,
i
- 3. The cask cavity will be inerted. !
6.4.1.4 Experience has demonstrated that utility I waste streams do not contain or generate !
toxic gas, vapors, or. fumes and do not !
contain hazardous, biological, I pathogenic, or infectious materials.
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d RW-800, Rev. 0 Page 12 of 19 NJH/WFM/KJC/ds1
. .- C.4.1.5 Paj::act ive wartes shall have no detectable free standino liquids, N detectable free standing liquid sha!! ce defined as ret more than li cf tne volume f ne waste when the waste is in a disp:saole centainer designed to ensure stadi;:ty er n:t mere tnan 0.5% of the V:1ume cf the waste for waste processed in any tther c:ntainer. Inis is ensured usin; appropr: ate statien precedures.
6.'.2 Waste Stability 6.4.2.1 Dewatered resin requiring stabili:ation is packaged in High Integrity Containers (H1C) that have been certified to meet tne stability requirements of 10CTR61.56(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. Upon arrival at the burial site, Class B and C wastes are placed in
. concrete overpacks for increased stability.
6.4.2.2 All reasonable efforts are made to eliminate unnecessary void spaces within the waste packages.
6.4.3 Labelling 6.4.3.1 Each package of waste shall be clearly
, labelled to identify waste classification.
6.4.4 Shipment Manifests 6.4.4.1 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.
6.4.5 Quality Assurance Program r, r , - rw- ,w m v , n- e v ,m ..ev ,- , -cv ,~.t. .m, - -
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I e 0.4.5.1 7"e quality assurance prcgram :ensists o' required uce cf plant procecures unich implement the Precess Centrol Program and (
requirements Of the Ccrporate Quality i Assurance Prcgram. Audits by personnel !
independent f the act:vities are 1 performed and reviewed by appropriate li nanagenent pers;nnel.
i 6.4.5. In addition, tne Process Centrol Program i (RW-800) and implementing procedures are !
audited once per 24 months by the Nuclear Review Board in accordance with Plant Technical Specification 6.5.2. l 6.4.5.3 Administrative controls for preventing [
unsatisfactory waste forms from being .
released for shipment are described in '
I applicable station procedures.
6.5 REVISING THE PCP (RW-800) I t
Revisions to the PCP (RW-800) shall be reviewed by 6.5.1 i PORC and approved by the Plant Manager. f 6.5.2 Revisions to the PCP (RW-800) to incorporate vendor -
supplied process systems shall be performed in the i following manner: >
6.5.2.1 Prior to use of a vendor supplied system,
,the Limerick Process-Control Program (RW-800) shall be revised to address the vendor's service requirements.
6.5.2.2 For vendors who have submitted a Topical Report to the NRC for review, the .CP (RW-800) shall be revised to reference the submitted Topical Report.
6.5.2.3 For vendors who have not submitted a Topical Report to the NRC for review, the PCP (RW-800) shall be revised to include the vendors Topical Report as an attachment.
6.5.4 All revisions to the PCP (RW-800) shall be reported L to the NRC in-the Semi-Annual Effluent Release l Report in accordance with the off site dose calculation manual via ST-0-RRR-990-0.
6.6 SURVEILLANCE REQUIREMENTS FOR SOLIDIFICATION -
6.6.1 At least one representative test specimen from at least every tenth batch of waste shall be solidified. See Ref. 7.18.
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- Page 14 of 19 l NJH/WrM/KJC/dsl i 1
. 6.6.2 If any test specimen f ails t n verify l solidification, the sclidification of the batch under test shall be surpended until additienal test specimens can be cotained, alternative
- solidificati
- n parameters can ce determined and a subsequent test verifien 3011dificatien. See Ref.
7.18.
6.6.3 If :ne initial test speca.en from a batch of wa' ,
falls to verify sclidification, representative 19 : l specimens from consecutive batches shall be tes4 ed until at least three censecutive test specimens demenstrate sclidification. The Process Control Program (RW-800) shall be modified as required to ,
assure solidification cf subsequent batches. See
~
Ref. 7.18. ,
6.7 DOCUMENTATION
+
6.7.1 Records of all data, tests, anslysis results, and e
- records of training, inspection, and audits are maintained in accordance with plant OA procedures for record retention.
6.7.2 Waste classification records, waste form records, and other records required for the preparation of the semiannual Radioactive Effluent Release Report '
shall be prepared and retained in accordance with the requirements of 10CFR20, 10CFR71, 49CFR170-178, and Limerick Technical Specifications.
6.7.3 Records of processing date, test and analysis results, and results of training, inspection, and audits are retained in accordance with the LGS Quality Assurance Plan and applicable station Administrative procedures.
7.0 SOURCES AND REFERENCES 7.1 49 CFR Parts 170 threlgh 178.
7.2 10 CFR Parts 20, 50, 61 and 71.
7.3 Standard Review Plan 11.4, Rev. 2, including Branch Technical Position ETSBil-3, Rev. 2.
, 7.4 Low level Waste Licensing Branch Technical Position on Radioactive Waste Classification.
2 7.5 Low Level Waste Licensing Branch Technical Position on Waste Form.
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i 7.6 South Carolina Depa'*-ent .Sf Health and Envirenmental i Control Radioactive Materia: License No. 097. !
7.7 Barnwell Waste Management Pacility Site Dispcsal Criteria. i I
7.6 State cf Washington Radicact;ve Materials License No. WN- l
!019-2. '
7.9 Nuclear Pacific Inc. T:pical Rep:: f:r Dewatering System ,
TP-00-P-A, Rev. 1.
[
7.10 General Critera fer High :ntegrity Containers (SCDHEC). j 7.11 PCP Imp;ementing Procedures. !
7.11.1 Limerick Radwaste P.racedures (RW) [
l 7.11.; Limerick Station Test 7 7;edures (ST) l 7.11.3 Limerick System Peocedures (S) ,
Note: PCP Implementing Procedures are those listed above which !
apply directly to-processing, packaging, sampling, ,
analy ing, and shipping radwaste. ;
7.14 Nuclear QA Plan -
[
t 7.15 Chem Nuclear Systems Inc Topical Report RDS-1000 !
Radioactive Waste Dewatering System RDS-25506-01-NP-A. '
7.16 Stock Equipment Co. Topical Report Quick Dry Process for Dewatering Bead Resin and Filter Sludge, SRS-003-P, Rev.
O. i.
7.17 Westinghouse-Hittman luclear, Inc. Topical ReportSTD-R ;
Oll-A, Mobile Incontainer Dewatering and Solidification [
System._ ;
i 7.18 Generic Letter 89-01 (Implementation of Programatic Controls for Radiological Effluent Technical Specifications :
in the Administrative Controls Section of the Technical [
Specifications-and the Relocation of Procedural Details of i RETS to the-Offsite Dose Calculation Manual or to the !
Process Control Program), 1/31/89. j r
7.19 Limerick Generating Station Unit 1 and 2 Technical I Specifications, 6.5.1.6, 6.8.1, 6.13. !
l 7.20 Station Test Procedures ST-0-RRR-731-0, ST-0-RRR-732-0, ST- }
0-RRR-733-0, ST-0-RRR-734-0. !
i l
! 8.0 ATTACHMENTS 1 I
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ATTACHMENT S 2 (Page 1 Of I' DEFINITIONS
- 1. OPERAB'.E - A system, train, c mpenent er device shall be operable Or have Operability wnen it :s capable of performing its specified functients), and when all necessary. attendant instrumentati n, centrols, electrical power, eo: Jing or seal water, luorication or other auxilliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
- 2. SLUDGE - Contaminated liquid which may contain water, oil, and suspended solids, including ion exchange media and other filters.
- 3. PROCESSING - Changing, modifying, and/or packaging the commercial nuclear power plant generated wet radioactive waste into a form that is acceptable to a disposal facility.
- 4. QUALITY ASSURANCE / QUALITY CONTROL - As used in this document, " quality assurance" comprises all those planned and systematic actions necessary to provide adequate '
confidence that a structure, system, or component will perform satisfactorily in service. Quality assurance includes quality control, which comprises those quality assurance actions related to the physical characteristics of a material, structure, component, or system which provide a means to control the quality of the material, structure, component, or system to predetermined requirements.
- 5. SAMPLING PLAN - A sampling program implemented to ensure that representative samples from the feed waste and the final waste form are obtained and tested for conformance with parameters stated in the PCP and waste form acceptance criteria.
- 6. LOW-LEVEL RADIOACTIVE WASTE (LLW) - Those low-level radioactive wastes containing source, special nuclear, or by-product material that are acceptable for disposal in a l
land disposal facility. For the purposes of this definition, low-level radioactive waste has the same meaning as in the Low-Level Waste Policy Act, that is radioactive waste not classified as high-level radioactive .
waste, transuranic waste, spent nuclear fuel, or by-product material as defined in section 11e.(2) of the Atomic Energy Act (uranium or thorium tailings and waste). -
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- 7. WASTE CONTA:NER - A vessel f any chape, s;:e, and composition used to cent &in the final prccessed waste.
S. WASTE FORM - Waste in a waste centainer acceptable for disposal at a licensed disposal faci lity.
- 9. WASTE TYPES (A) NON-CONTAMINATE? WASTE - Waste containing no detectable contamination.
(B) RADIOACTIVE WASTE STREAMS CONDENSATE TILTER /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 overlay material, and small concentrations of various solids, activated and
. non-activated corrosion products.
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.
REACTOR WATER CLEANUP PILTER/DEMINERALIZER SLUDGE -
A contaminated waste product generated by the backwash of the Reactor Water Cleanup filter demineralizers consisting of contaminated powdered !
lon exchange resins at varying degrees of exhaustion, fibrous filter media, and small concentrations of various solids and corrosion products.
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.
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ATTAC!! MENT S.:
(Page 3 :t .'
0:LY WASTE-WCT RADICACT:VC WASTCS - Oils ccusis: Of non-reclaimable contaminated oils and grease of various grades both syntnetic or otherwise in free f rm or containing various amounts of solid material.
RRADIATED REACTOR COMPONENTS - Materials which have been irradiated through neutron flux frem the .
reactor. This includes but is not limited the start-up sources, LPRMS, SRMS, I RMS , channel clips i and tips. ;
CRD FILTERS - Control Rod Drive System filter media which has been contaminated by activated particles in the reactor water which are deposited on the filters through control rod drive water flow. '
- 10. PCP IMPLEMENTING FROCEDURES - Those Limerick specific RW, ST, and S procedures which apply directly to processing, packaging, sampling, analyzing, and shipping radwaste.
- 11. SOLIDIFICATION - Waste processed into the form of a free standing monolith, having no more than 0.5 percent of the '
waste volume as free liquids.
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