ML20114C045
| ML20114C045 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/30/1992 |
| From: | Helwig D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9209010119 | |
| Download: ML20114C045 (52) | |
Text
{{#Wiki_filter:-- - 392501b210 TS 6.9.1.8 a - 3 10CFR5 0. 3 6 (a ) PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION P. O. BOX 2300 SANATOGA, PA 19464-2300 (215) 327-1200 EXT. 3NO August 31, 1992 DAVID R. HELWIG VCE PRESIDENT uutncx aENrnAnna swon Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U. S. Nuclear Regulatory Commission Attn: Document Control Desk washington, DC 20555
Subject:
Limerick Generating Station, Units 1 and 2 Semi-Annual. Effluent Release Report No. 16, January 1, 1992 through June 30, 1992 Gentlemen: Enclosed is_the Semi-Annual Effluent Release Report No. 16,
- fc - Limerick Generating Station (LGS), Units 1 and 2, for the pu lod January 1, l?92 to June 30, 1992.
These reports are being submitted in accordance with the LGS Technical Specification Section 6.9.1.8 and 10CFR50.36(a). Very truly yours, d t KWM/ds Enclosures cc: T. T. Martin, Administrator, Region I, USNRC (w/ enclosure) T. J. Kenny, USNRC Senior Resident Inspector, LGS (w/ enclosure) 9209010119 920630 DR ADOCK 0500 2 ((/./-[
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-UNITS NO. 1 AND 2-DOCKET-NO. 50-352 (Unit 1)
DOCKET NO. 50-353 (Unit 2)
! SEMI-ANNUAL EFFLUENT 1.dLEASE REPORT NO.-16' JANUARY 1, 1992 THROUGH JUNE 30, 1992 .
- 9 SubmittedUto-The Uni ted' States Nuclear Regulatory Commission
-Pursuant to Facility Operating License NPF-30-(Unit 1) and NPF-85_(Unit-2)
G. L.' Roacp, Services Superintendent r-'r-r. - - -. ,c.
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- I TABLE OF CONTENTS I. Introduction II. Tables ;
A.. Summary of Radioactive Gaseous Effluents B. Summary of Radioactive Liquid Effluents C.. Solid Waste Disposition Report , III. Attachments 1 A. Supplemental Information - Assumptions Used in Report Generation , 1 B. Process Control Program (PCP) C. Radiation Monitors Out-of-Service l
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-4 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 Materialsfin Liquid and Gaseous Effluents from Light-Water J Cooled Nuclear Power Plants", Revision 1, June, 1974.
I
+ -The following information is included as Tables to thi.s report:
- A summary of the gaseous and liquid effluent releases for the report period. Where "0.00E+00" is used, it denotes the less than detectable level for the given isotope.
l-
- Composite particulate air samples, counted for beta emittersL(eg. Sr-89, Sr-90), are submitted to an offsite vendor laboratory for analysis. Since data for !
the second quarter particulate air samples-were not available at the time this report was prepared, it will be necessary to submit an addendum in the future if l_ second quarter particulate air samples results are reported >LLD..
- Since Limerick Technical Specification limits for liquid and'_ gaseous effluent releases are stated in terms of quarterly and annual offsite doses, " percent technical specification limit" is given as'0.00E+00.
n A: summary of solid waste dispositioned during the report period, toLinclude: total activity shipped by r waste. type and an estimate of-the error in the reported l_ l
-totals;-the-estimated composition of each type of waste L by_ isotope; the number of shipments, mode of transportation, destination,-type of container,-total container volume,1and solidification agent.
L
- There were no changes to the Offsite Dose Calculation Manual-(ODCM)?or Radioactive-' Waste Treatment Systems during the' report period.
- RW-800r Solid Radwaste System Process Control Program-(PCP) was revised during the-report period.
- An explanation-of why an inoperable Service Water Radiation Monitor-was not. returned to service within.
l- the time specif-ied is provided in accordance with ODCM j 3.2.l(b). . L I
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1 E,7 , 4 II.- . TABLES
,A..
SUMMARY
-OF RADIOACTIVE GASEOUS EFFLUENTS (I i I^ (' January 1, 1992 to June 30,.1992 (, t a l' l. l I l l .:.~ i .- I ;
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SITEj LIMERICK UNIV :-U1 . USER;LMART.
'DATE:'08/19/9? 07:01 EFFLUENT AND. WASTE DISPOSAL REPORT GASEDUS: EFFLUENTS - SUMMATION OF ALL RELEASES ,
, ! UNITS : QUARTER : QUARTER !EST. TOTAL:
- 1 : 2 ! ERROR %!
.A.: Y1SSIONANDACTIVATION0ASES
- -.1. TOTAL RELEASE : CI : 0.137EiO3 : 0.341E400 0.453EiO2 :
l 2. AVERAGE RELEASE :UCI/SEC 0.174Ef02 : 0.434E-01 :
- RATE FOR PERIOD : : : :
~'t 3. PERCENT OF TECHNICAL: % : 0.000Ef00 ! 0 000Ef00 1 -: SPECIFICATION LIMIT : : : 1
- 9. ZODINES
! 1. TOTAL 10 DINE-131- CI 0.357E-04 : 0.273E-03 1 0.453Et02 :
213. AVERADE RELEASE - UCI/SEC: 0 454E-05 : 0.3ABE-04 1- RATE FOR PERIOD : : :
-3. PERCENT OF TECHNICAL: % ! 0.000E400 1 0 000Ef00
.: SPECIFICATION LIMIT : : : @'.ePARTZCULATES n......__.....__............_................_____...._...............
=1. PARTICULATES WITH : CI : 0.306E-03 : 0.209E-04 0.453Ef02 :
HALF-LIVES >B DAYS : : I !
-2. AVERAGE RELEASE UCI/SEC: 0.389E-04 1 0.265E-05 l- !- RATE FOR PERIOD : ! ! !
in3.-PERCENT OF TECHNICAL: % : 0.000Ef00 l'O.000Ef00': SPECIFICATION LIMIT : : : n......._............__....................._........
- 4. OROSS ALPHA CI : 0.746E-09 : 0.000Ef00 :
l' RADI0 ACTIVITY ! : : $.,TR2 TIUM-g.._..........__.......... ..... ............~................._. _...
- -a.-TOTAL RELEASE CI : 0.000Ef00 l'0 000E+00 0.453E+02 :
a...............___.......... .... ... ........._.....................
?E2. AVERAGE RELEASE UEI/SEC: 0.000Ef00 0.000E+00 :
- . RATE FOR PERIOD : 1- :
,7 3. PERCENT OF TECHNICAL: % ! 0.000E+00 : 0.000Ef00 i: SPECIFICATION LIMIT : : ! __ ......__. _.. __......t......_____........ ..._. l: l
PAGE 1 0F 12 9 SITE: LfMERICK P TUN!T: 01 / USER!. MART DATE: 08/19/92 07:03 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FORLRELEASE POINT: 1 NORTH STACK
/ CONTINUOUS NODE BATCH MODE
- UNITS i QUARTER : QUARTER : QUARTER QUARTER s
! .NUCLIDES :
- - RELEASED : : 1 2 : 1 ! 2
- 1. FISSION GASES i AR41 : CI : 0.000Ef00 : 0.000E400 ; 0.648Ef00 0.000Ef00 :
KR83H !. CI : 0.000E400 1 0.000E400 1 0.000Ef00 1 0.000Ef00 : KR85H- 1 CI : 0.000Ef00 : 0.000Ef00 : 0.165Ef01 : 0.000Ef00
...___... .............__......~..___._ .. ..___..._______...........
0.341Ef00 ; KR85 : CI :-0.000Ef00 : 0.000Ef00 i 0.191Ef01 KR87- CI : 0.000Ef00 1 0.000Ef00 : 0.000Ef00 0.000Ef00 CI : 0.000Ef00': 0.000Ef00 0 143Ef00 ; 0.000Ef00
.KR88-
- KRB9 . CI : 0.000Ef00 : 0.000Ef00 0.000Ef00 0.000Ef00 :
- . KR90 : CI. : 0.000Ef00 0.000Ef00 0.000Ef00 0.000Ef00 :
~~ ~
~~ ~~
~~ ~~~~ "~ ~~~ ~
i XEi3EM i Ci i 676EEEidd i d76EEEidd i 5!d5dEidd i diUU6Ei66 I
- 'XE133M : CI -: 0.000Ef00 0.000Ef00 1 0.162E-02 0.000Ef00 :
t XE133 : CI : 0.000Ef00 : 0.000Ef00 0.848Ef02 : 0.000Ef00 .
; :XE135M : CI : 0.000Ef00 0.000Ef00 : 0.000Ef00 0.000Ef00 :
- XE135 :- CI : 0.000Ef00 0.000Ef00 i 0.462Ef02 : 0.000Ef00 it. XE137 : CI : 0.000Ef00 : 0.000Ef00 0.000Ef00 : 0.000Ef00 1 XE138- CI : 0.000Ef00 0.000Ef00 : 0.000Ef00 0.000Ef00 :
- : : : I o : TOTAL-FOR :
PERIOD CI : 0.000Ef00 1 0.000Et00 1 0.135Ef03 : 0.341Ef00 : l : :
- (ABOVE) :
C
- ENTER E-C ] TO ERASE SCREEN AND CONTINUE :
1
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PAGE 2 0F 12 -- S[TE: LINERICK UNIT! Ua4_ USER: LMART . DATE: 08/19/92 07:02' EFFLUENT AND WASTE DISPDSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 1 NORTH STACK t J CONTINUQUS NODE BATCH NODE
............ _____......____..............___...........__...___...... : QUARTEF: :
- UNITS : QUARTER : QUARTER ! QUARTER ,
1 .NUCLZDES 2 : ': RELEASED : : 1 : 2 1
~
1
- 2. 30D3NES:
' 1331- :. CI : 0.528E-05 : 0.000Ef00 1 0.000Ef00 : 0.000Ef00 : 't 1833 : CI : 0 000Ef00 1 0.000E+00 : 0.000E+00 : 0.000E+00 f TOTAL-FOR : : 3 .: PERZOD ;- CI : 0.528E-05 : 0.000E+00 1 0.000E+00 : 0.000E+LS : .'-(ABOVE) :
- 3. PARVICULATES
- 0.000E+00 1 0.000E+00 : 0.000E+00 0.000Ef00
- Ca4 - CI
'........__....___._............................_-__..... ....._......_ 0.000E+00 :
- CRS1 : ' CI : 0 000Ef00 0.000Ef00 0.000E+00 HN34 1. CI :-0.000Ef00- 0.000Ef00 : 0.000Ef00 : 0.000Ef00 :
- FE99 : CI- 110.000Ef00 '0.000Ef00 1 0.000E+00 0 000Ef00 :
CI : 0.090E+00~: 0.000Ef00 : 0.000Ef00- 0.000E+00 : l-.C050 :
;: C060 : -CI -!.0.000E+00 : 0.000E+00 0 000Ef00 : 0.000Ef00 :
ZN65 : CI- 0.000Ef00 1 0.000EiOO : 0.000E+00 : 0.000E+00 : SR89 - CI : 0.000E+00-:-0.000E+00 : 0.000Ef00 :-0.000E+00 : SR90 : CI' : 0.000E+00 1 0.000E+00 0.000E+00 : 0.000E+00 8
............_..............__ __....__......__.....- ..._... .....__._. 0.000E+00 :
ZR95- .CI : 0.000E+00 .0.000E+00 : 0.000Ef00 SB124 : CI 0.000E+00 : 0.000E+00-: 0.000E+00 ; 0.000Ef00 : CS134 : CI - 0.000E+00 1 0.000Ef00 : 0.000Ef00 : 0.000E+00 ! CI- 0.000E+00 : 0 000E+00 0.000E+00 0.000E+00 : CS136
- tb137 : CI : 0.000Ef00 ; 0.000E+00 : 0.000E+00 ! 0.000E+00 :
ENTERTE C 3 TO' ERASE' SCREEN AND CONTINUE : C
PAGE 3 0F 12
-SITE: LIMERICK UNIT! UI.-
-USER: MART DATE: 08/19/92 07:02 EFFLUENT AND WASTE DISPOSAL-REPORT CASE 0VS EFFLUENTS FOR. RELEASE POINT: 1 NORTH STACK
+
CONTINUOUS 80DE BATCH MODE
-: .NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
- 2 : 1 2 :
RELEASED : 1
- 3. PARTICULATES (CONTD) l- BA140 : CI : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 :
CE141 : CI : 0.000Ef00 0.000Ef00 : 0.000E400 i 0.000Ef00
- CE144 : CI : 0.000Ef00 1 0.000Ef00 : 0.0eci+00 1 0.000Ef00 :
TOTAL FOR : : : : :
- 1. PERIOD : CI : 0.000Ef00 : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 :
- -(ABOVE) !
ENTER E C 3 TO ERASE SCREEN AND CONTINUE : C 4 s j
L PAGE 4 0F 12 SITE: LIHERICK UNIT: U1 - USER: MART DATE: 08/19/92 07:02 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 2 UNIT 1 - SOUTH STACK CONTINUOUS MODE BATCH MODE r,
--...--...------.......-- ------------.... .--...----......------.--- : QUARTER OVARTER :
- QUARTER
! .NUCLIDES : UNITS : QUARTER : :
- 2 : 1 2 ,
- RELEASED : 1
- 1. FIS3!ON OAFES
---...... ..........--.... .. ..----.-...-..----...--...........-- 0.000E+00
-~:
AR41 : CI : 0 000E+00 : 0.000E+00 1 0.275E-04 , KRS3M : CI : 0.000Ef00 1 0,000Ef00 1 0.000Ef09 : 0.000E+00 1
- CI : 0.000E+00 1 0.000E+00 : 0.000Ef00 0.000E+00 !
KRBan KR83 : CI : 0.000E+00 : 0.000Ef00 : 0.000Et00 : 0.000E400
! KR87- CI : 0.000E+00 0.000EiOO : 0.000E+00 ; 0.000E+00 KR80 : CI : 0.000E+00 : 0.000Ef00 ! 0.000Ef00 1 0.000E+00
- KR89 : CI : 0.000E+00 ; 0.000Ef00 : 0 000Ef00 1 0.000Ef00 :
I KR90 : CI : 0.000E+00 : 0.000E+00 1 0.000E+00 : 0.000EiOO : XE131H : CI : 0.000E+00 1 0.000Ef00 1 0.000EiOO : 0.000E+00 : -
- XE133M CI : 0.000E+00 1 0.000E+00 1 0.000E+00 1 0.000E400 :
- XE133 : CI : 0.292Ef00 1 0.000E+00 0.688E+00 1 0.000E+00 :
- XE135H : CI : 0 000E+00 1 0.000E'00 t 0.000Et00 : 0.00CE+00 :
- XE135 : CI : 0.272E+00 : 0.000Ef00 1 0.440E+00 0 000tt00 :
XE137 : CI : 0.000E+00 0.000E400 0.000E+00 1 0.000Ef00 :
---.......---....--...---------.-------- --.....-- ----....---------- 0.000E+00 :
- - XE138 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 TOTAL FOR :
PERIOD : CI : 0.584E+00 0 000Ef00 : 0.113E+01 : 0.000E+00 : (ABOVE) : : ENTER E C 1 TO ERASE SCREEN AND CONTINUE : C
4 i PAGE 5 0F 12 SETEV L1HERICK' UNIT!7 01;. <
-USFR:: HART-311E 08/19/92 07:03 ETTLUENT AND. WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR. RELEASE POINT 2 UNIT 1 SOUTH STACK
. CONTINUOUS H'0DE BATCH HODE QUARTER QUARTER QUARTER NUCLIDES- UNITS : QUARTER :
! 2 : 1 : 2 RELEASED : 1
- 2. 10 DINES T 2131 : CI : 0.304E-04 ! 0.191E-03 : 0.814E-07 ! 0.380E-05 :
- Z133. CI- ! 0.000Ef00 1 0.490E-05 0.000Ef00 1 0.000E4te
.........._........................_;............................~,
! YDTAL TOR :
1 PERIOD ! CI : 0.304E-04 : 0.195E-03 : 0.814E-07 : 0.380E-05 : 1- (ABOVEF i : :
/3. PARTICULATES
!~ C14 : CI : 0.000Ef00 : 0.000Ef00 0.000Ef00 1 0.000Ef00 :
- CR51 : CI : 0.174E-03 0.000Ef00 ! 0 671E-04 : 0.000Ef00
- HN54 : CI- :-0.000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 :
- = FE59 : CI : 0.000Ef00 1 0.000Ef00 ; 0 000Ef00 1 0.000Ef00 :
- 'C058 : CI- 0.000Ef00 l 0.000Ef00 : 0.000Ef00 ! 0.000Ef00 :
- 1C060 : CI : 0.106E-04 : 0.544E-05 1 7: 0.000Ef00 :
._........_...........___._ ...._ ........... _0.358E-0 __..... ....... .......
- 'ZN65 . CI- ! 0 000Ef00': 0.000Ef00 :-0.000Ef00 1 0.000Ef00 :
..~..____.... . .. ________.._-_.. _____........_____ ........_......
- SR89 :~ CI : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 1 0.000Ef00 :
SR90. : 'CI 0.000Ef00 0.000Ef00.! 0.000Ef00 !.0.000Ef00 ! CI .: 0.000Ef00 : A.000Ef00 0.000Ef00 ; 0.000Ef00 :
- IR95 -
. ..__e..... _____ ................ _.............____...____, .._____
L
~;- SB124 *
'CI. ;-0.000Ef00 ! 0.000Ef00 : 0.000Ef00 1 0.000Ef00 :
t- CS134- : CI : 0.000Ef00 : 0.000Ef00 0.000Ef00 : 0.000Ef00 : l- CS136- :- CI : 0.000Ef00 : 0.000Ef00 0.000Ef00 0.000Ef00 : l- ....__._..__.._, .........____..____..._......._....__._--__ ____...._ L : CS137 : CI- 0.000Ef00 1 0.000Ef00 ; 0.000Ef00 1 0.000Ef00 : l
~ ENTER E-C 3 TO ERASE SCREEN AND CONTINUE : C
'4 PAGE 6 0F-12 SITE: L3MERICK.
- UN2T: U1. -
-USER: MART-DAid: 08/19/92 07:03 -EFFLUEPT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 2 UNIT 1 - SOU1H STACK
.' CONTINUOUS N'0DE PATCH MODE QUARTER : QUARTER :
i .NUCLIDES : UNITS : QUARTER QUARTER :
- 2 : 1 2 :
- 1
'. .. RELEASED 3.fPARTICULATES (CONTD)
- -BA140 : CI : 0.000Ef00 0 000Ef00 : 0.000Ef00 : 0.000Ef00 :
- -CE841 : CI : 0.000Ef00 : 0.000Ef00 : 0 000Ef00 : 0.000Ef00 :
l- CE144 :. CI : 0.385E-04 : 0.000E400 0.160E-04 : 0.000Ef00 : TOTAL FOR ; :
.. 1 -PERf0D : CI : 0.223E-03 : 0.544E-05 : 0.831E-04 0.000Ef00 :
Ii (SBOVE)- : : : : : ' ENTER E C-] TO ERASE SCREEN AND CONTINUE : C 1 l
l PAGE 7 0F 12 '
.S2TE: LIHERICK UN8T: U1. -
USER: MART-DATE: 08/19/92 07:04 EFFLUENT,AND WASTE DISPOSAL REPORT ; I GASEOUS EFFLUENTS FOR RELEASE POINT: 3 UNIT 2 - SOUTH STACK CONTINUOUS 80DE BATCH H0DE QUARTER : QUARTER : GUARTER !
! .NUCLIDES : UNITS : QUARTER : ,
- 2 : 1 : 2 :
-: RELEASED 1 1
- 1. FISSION GASES
_ : .AR41 : -CI ! 0.000Ef00 : 0.000Ef00 0.889E-05 0 000Ef00 :
- -KR83M : CI ! 0.000Ef00 0.000Ef00 : 0.000Ef00 0.000Ef00 !
KR85H i. CI : 0.000Ef00 0.000Ef00 1 0.000Ef00 1 0.000Ef00 :
- ~KR85 : CI : 0.000Ef00 0 000Ef00 : 0. 0~ 0E'i O O 0.000Ef00 :
.: KR87- CI : 0 000Ef00 : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 : .: KR88 : CI : 0.000Et00 : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 I KR89 : CI : 0.000Ef00 : 0.000E+00 0.000Ef00 0.000Ef00 :
t KR90 : CI- 0.000Ef00 1 0.000Ef00 0.000Ef00 0.000Ef00 : XE131H - CI : 0.000Ef00 : 0 000Ef00 1 0.000Ef00 : 0.000Ef00 :
- XE133M- ; CI- 0.000Ef00' 0 000Ef00 : 0.000Ef00 : 0.000Ef00 :
-: :XE133 - ; -CI .
0.000Ef00 0.000Ef00 0.000Ef00 1 0.626E ..._..___....__ ......____............. ....... ______.. ........ _... XE135H- : CI : 0.000Ef00-1 0.000Ef00 -0.000Ef00 0.000Ef00 1 XE135 :- CI : 0.000Ef00 0.000Ef00 0.000Ef00 0.000Ef00 :
-: XE137- - CI : 0.000Ef00 1 0.000Ef00 ! 0.000Ef00 : 0.000E400 l
- XE138 : CI : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 :
~i LTOTAL FOR:: : : : : :
' PERIOD .: -CI : 0 000Ef00 0.000Ef00 1 0.889E-05 :'0.626E-03 :
- (ABOVE) : : : :
4 ENTER E C 3 TO ERASE-SCREEN AND CONTINUE : C L: .-
- w. - _- , - .-
PAGE 8 0F 12 S1TE: LIHERICK~
- UNIT: U: .-
USER: NART DATE: 08/19/92 07:04
- EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT! 3 UNIT 2 - SOUTH STAEK
. CONTINUDUS NODE BATCH H0DE
.......__. ......__......___........... ....................__........ : QUARTER :
! .NUCLIDES -UNITS : QUARTER -! OUARTER : QUARTER ,
2 : : 2 : i RELEASED : 1 : 1
- 2. IDDINES
?! 2131 : CI 0.000Ef00 1 0.789E-04 0.000Ef00 : 0.000Ef00
- 8833 : CI : 0.000Ef00 1 0 000Ef00- 0.000Ef00- 0.000E400 :
TOTAL FOR :
. PERIOD l CI : 0.000Ef00 1 0 789E-04 : 0.000Ef00 : 0.000Ef00 :
1 (ADOVE) : :- :
-3. PARTICULATES
! C14 : CI : 0.000Ef00 1 0.000Ef00 0 000Ef00 : 0.000Ef00 !
! ! CR31 : CI : 0.000Ef00 1 0.000Ef00 _0.000Ef00 0 000Ef00 : HN34 : CI : 0.009Ef00 0.653E-05 : 0.000E+00 : 0.000Ef00
'i FC59 1: -CI :-0.000Ef00 : 0.000Ef00 : 0.000Ef00 1 0.000Ef00 i, C058 : CI : 0 240Ef00- 0.000E+00 0.000Ef00 1 0.000Ef00 :
.. .......___......._-_..........._......................... ........_ 0.000E400 :
1 CD60 : CI : 0 000Ef00 : 0.890E-05 : 0.000Ef00 IN65 : CI : 0.000Ef00 1 0.000Ef00 0.000Ef00 ! 0 000E+00
-; SR89 : .CI : 0.000Ef09 0.000E400 0.000EfC0 1 0.000Ef00
- - SR90' : CI : 0.000Ef00 ; 0.000Ef00 : 0.000Ef00 0.000E400 i 7R95 :. CI t'0.000Ef00 0 000Ef00 : 0.000Et00 1 0.000Ef00 : ~
~~ ~~ ~~~
~~ ~~~~~ ~~ '~~ ~
LI SBI24 i Ci I 5Ibb5EIbb i hI665[ib5 I 6I666EI66 i h bh65IU5 i-CS134- : CI : 0.000Ef00 0,000Ef00 -0.000Ef00 0.000Ef00 CS136 : CI : 0.000Ef00 : 0.000Et00 : 0.000E+00 1 0.000E+00 :
- CS137 :- CI .0.000E+00 0.000Ef00 : 0.000E+00 : 0.000Ef00 :
ENTER I C 3 TO ERASE SCREEN AND CONTINUE ! C
__ . _. . _ - _ _ _ . _ . - . . . - . _ . _ _ . ~ . _ . . __ _ _._ _ PAGE 9 0F 12 . SETEt LInERICK UNITizUli. USER:' HART~ DATEl 08/19/92 07:04
- EFFLUENT'AND UASTE DISPOSAL REPORT DASEOUS EFFLUENTS FOR. RELEASE POINT! 3 UNIT 2 - SOUTH STACK
-CONTINUDUS 80DE BATCH MODE 1 .NUCLIDES : UNITS i 00ARTER ! OUARTER QUARTER t DUAR~ER 1
- 2 1 1 ! 2 :
- ! RELEASED : ! 1
........................... ...........................__............_ i
- 3. PARTICULATES (CONTD) i 0 000T* I 0.000Ef00 i 0.000Ef00 1 0.000Ef00 :
- 1 BA140 - CI
!- CE141 1 -CI ! 0 00?i.sG i 0.000Ef00 1 0.000Ef00 1 0.000Ef00 i
- CE144 : CI .: 0.000E+00 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00
- TOTAL FOR i ! ! ! ; i
- PERIOD CI i 0.000Et00 1 0.154E-04 : 0.000Ef00 : 0.000Ef00 i
- -(AB0VE) i i ! ! !
ENTER I C 3 TO ERASE SCREEN AND CONTINUE 1 C
PAGE 80 0F 12 6S$EtLINEk1CK UNI?! U1,- "USERI.NART 'DATE! 08/19/92 07:05 t EFFLUENT AND WASTE DISPOSAL REPORT i
' GASEOUS EFFi.UENTS FOR. RELEASE POINT! 4 HOT MAINTENANCE SHDP 1
d I
/ CONTINUOUS MODE BATCH NODE 3 .NUCLIDES- UNITS 1 QUARTER : OUARTER GUARTER : QUARTER ! - ,
i'
'i' RELEASED : : 1 : 2 : 1 1 2
- 1. F3SSION OASES j
- ' AR41 : CI i 0.000Ef00 : 0.000Ef00 i 0.000Ef00 t 0 000Ef00 :
- - KR83H : CI ! 0.000Ef00 1 0.000Ef00 i 0.000Ef00 i 0.000Ef00 8 KR85M t CI : 0.000Ef00 1 0.000E100 ! 0.000Ef00 0 000Ef00 1 - KR83 : CI :-0.000Ef00 1 0 000Ef00 ! 0.000Ef00 t 0.000Ef00 i 2 KR872 : CI : 0.000Ef00 0.000Ef00 : 0.000Ef00 1 0.000Ef00 :
- i. KR88 i CI : 0 000Ef00 : 0.000Ef00 1 0.000Ef00 ! 0.000Ef00 t i KR89 't CI : 0.000Ef00 0.000Ef00 : 0.000Ef00 1 0.000Ef00 t
-8 KR90 : CI. 0.000Ef00 1 0.000Ef00 0.000Ef00 1 0.000Ef00 i
": XE131H 't- CI I 0.000Ef00~t 0.000Ef00 : 0.000Ef00 1 0.000Ef00 t
--U .XE133M ! CI- 11-0.000Ef00 0.000EiOO 0 000Ef00 : 0.000Ef00 i
- XEa33 : CI : 0.000Ef00 1 0.000Ef00 ! 0.000Ef00 8 0.000Ef00 !
- 7 - XE135M I CI i 0.000Ef00 ! 0.000Ef00 l 0.000Ef00 ! 0.000Ef00 :
- XE135 : CI :-0.000Ev00 1 0.000Ef00 : 0.000Ef00 0.000Ef00 :
- ? XE337 1 CI : 0.000Ef00 0.000Ef00 i 0.000Ef00 0.000Ef00 :
-1 CI. t-0.000Ef00 1 0.000Ef00 i 0 000Ef00 t 0.000Ef00 t ' _t __- .........____..
XE138 _____..._................ _ .._...______..........
- I ! : :
~ TOTAL FOR 1
- ! PERIOD : CI' 0 000Ef00 1 0.000Ef00 : 0.000Ef00 1 0.000Ef00
- 1% (ABOVE) '1 i : :
ENTER L C 3 TD EPASE. SCREEN AND CONTINUE l C
_. - _ - ~ - .. - - . .- _ - . . - - - - _ - _ - . ... PAGE :1 0F 12 SfTE'i LfMERICK UNITi U2.- USER! MART DATEi-08/19/92 07:05-EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR. RELEASE POINT: 4 HOT MAINTENANCE SHOP
. CONTINUOUS n'0DE BATCH H0DE
........._.................._ _-_......... ........................... ! OUARTER : QUARTER. ;
QUARTER ,
! .NUCLIDES 1 UNITS.! OUARTER
! 2 i i : 2 : 1 t RELEASED i 1
- 2. IDDINES 1131 CI 1 0.000E+00 1 0.000Ef00 1 0.000E+00 : 0.000E+00 :
l L ..........................._.. ......................................_ l 1133 1 CI : 0.000E+00 1 0.000E+00 t 0.000Ef00 : 0.000Ef00 t 1 i ! TOTAL FOR !
! PERIOD i CI : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000E+00 :
! (ABDVE) i i i !
/ 3. PARTICULATES
! C14 1 CI I 0.000Ef00 1 0.000Ef00 1 0 000Ef00 0.000Ef00 t
! CRS1 i CI 1 0.000Ef00 1 0.000E+00 : 0.000Ef00 1 0.000Ef00-
! MN54 i CI i 0.000Ef00 1 0.000Ef00 : 0.000EiOO i 0 000Ef00
! : FE59 : CI i 0.000Ef00 : 0.000E+00 0.000Ef00 1 0 000E+00 1 l
- C058 : CI : 0.000Ef00 : 0 000E+00 : 0 000E+00 1 0.000Ef00 1
-! CD60. : CI : 0.000E+00 1 0.000F400 1 0.000Ef00 1 0 000Ef00
- ZN65- CI- 1 0 000Ef00 1 0.000Ef00 1 0 000Ef00 1 0.000Ef00 ::
-: SRB 9 : CI : 0.000Ef00 l'0.000Ef00 :=0.00]Ef00 1 0.000Ef00 :
'SR90 l- CI : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 : 0.000Ef00 :
r-t ZR95 t CI 1 0.000Ef00 : 0.000E400. 0.000E+00 1 0.000Ef00 1
- ......-._ m......_.... ______........... __.......___.....__....... _
; SB124 : CI : 0.000E+00 1 0.000Ef00.1 0.000E+00 1 0.000Ef00 :
': Ca134 : CI : 0.( : 0Ef00 1 0.000Ef00-1 0.000Ef00 1 0.000Ef00 :
-1 CS136 : CI i 0.000Ef00 : 0.000E+00 1 0.000E+00 t 0.000E+00 :
.: CS137 : CI 1 0.000Ef00 1 0.000E+00 1 0.000Ef00 : 0.000Ef00 t C
ENTER E C J-TO ERASE SCREEN AND CONTINUE :
-r-- - - - - - - c.,., , , ,
PAGE'12 0F 12
. I Sf7E 'AIMERICK' UN!Ti U11-
-USER! MART ~ DATEt: 08/19/92 07106 l i EFFLUENT AND WASTE DISPOSAL REPORT- 1 i DASEOUS EFFLUENTS FOR. RELEASE POINT! 4 NOT MAINTENANCE SHOP
.................................... I CONTINUOUS 80DE BATCH NODE i i' .NUCL8 DES ! UNITS ! OUARTER i OUARTER ! DUARTER : QUARTER :
2 i 1 ! 2 : 1 1 RELEASED 1 1
- 3. PARTICULATES (CONTD)
L! BA140 11 CI- t 0.000Ef00 1 0 000Ef00 1 0.000E+00 1 0.000E400 : p...................................................................... i CI . : 0.000E400 0.000E400 1 0.000Ef00 1 0.000Ef00 i LI CE141
- CI i 0 000EiOO 0.000Ef00 1 0.000Ef00 0.000Ef00 t
-1 CE344
! i ; i 1_; TOTAL FOR l-PER30D ! CI : 0.000Ef00 2 0 000Ef00 : 0 000Ef00 ! 0.000Ef00 I ! !
1 (ABOVE) ! ENTEw & C 3 T0* ERASE SCREEN AND-CONTINUE : C
-l 1
;a. . i L.;! . , t i
1 I 1 '
*'t l
1
}
E. . II . TABLES ! B.-
SUMMARY
-OF RADIOACTIVE LIQUID EFFLUENTS . January 1, 1992;to June 30, 1992
+
l 1
-s.
[ i f ,[ t I.. l
SITLt L!nERICK UNITI-Ut
- ULERt_HA8T
- DATE! 08/19/92 07806 ErfLUENT.AND WASTE DISPOSAL REPORT f
LIQUID EFFLUENTS -- SunnATION OF ALL RELEASES
! UNITS I OU.AR1ER 1 OUARTER IEST. TOTALt t i 1 ! 2 1 ERRORv %1 A.' FISSION AND ACTIVATION PRODUCTS I 1. TOTAL RELEASE (EXCL.! Cl ! 0.921E-03 1 0.239E-01 1 0 630E401 1 1 TRIT.e OASES, ALPHA)! 1 1 1 I 2. AVERACE DILUTED !UCI/HL ! 0.1610-07 1 0.496E-06 i ! CONC. DURING PERIOD ! .
7 7 g7 1 APPLICABLE 1 1 i i
................ LIMIT ............... ..........................
-B.-TRI91UM
........a.............................................................
t=1. TOTAL RELEASE ! CI t 0.143E401 ! 0.606Ef01 ! 0 630E401 !
! 3. AVERADE DILUTED- IUCI/ML 1 0.250E-04 1 0.126E-03 i
- f. CONC. DURING PERIOD t t 3. PERCENT Of 1 % 1 0.000E400 1 0.000E400 1 i ! !
1 APPLICA!tLE LIMIT 1 C. DISSOLVED AND ENTRAINED DASES
=1 1. TOTAL' RELEASE i CI ! 0.145E-02 1 0.117E-02 1 0.630Ef03 1 1S 3. AVERADE DILUTED !UCI/ML f 0.255E-07 1 0.242E-07 ! ! CONC. DURING PERIOD 1 1 10 3r- PERCENT OF ! % 0.!?;E-01 : 0.121E-01 :
I ! ! !
! APPLICABLE LIMIT D.190SS ALPHA RADICACTIVITY- ....e .... ....................-....................................... 't-1. TOTAL RELEASE I CI 1 0 000E400 1 0 000Ef00 1 0.000E400 t 'E. VOLUME WASTE RELEASED'! LITERS i 0.185E407 1 0.662Ef07 : 0 000Ef00! t L1 (PRIOR TO: DILUTION) ! ! i- ! ..a................................................~..................
0.000E400 : _1 lF. VOLUME DILUTION WATER ! LITERS 1 0.571E408 ! 1 0.482E408 !
- ! l 1 -USED DURING PERIOD ,
I FAGE 1 Or 5 . SETEt LInERICK-UNf T! U1.- USERt MART DATEt 08/19/92 07106 EFFLUENT AND WASTE DISPOSAL REPORT & ~ L10VID EFFLUENTS FOR RELEASE FOINT! 1 LIOUID RAD WASTE DISCHARGE TO SCHUiLKILL RIVfR 4 CONTINUOUS tl0DE FATCH MODE QUARTER !
! .NUCLIDES ! UNITS ! OUARTER 1 QUARTER t 00ARTER i
! 1 1 2 ! ! ! 2 8 RELEASED !
1
.! H3 1 C1 ! 0 000Ef00 1 0.000Ef00 1 0 143E401 ! 0 606E401 1 ! C14 1 CI 1 0.000Ef00 1 0 000E400 1 0.000Ef00 ! 0.000E400 t t NA24
- CI I 0.000Ef00 8 0.000E400 f 0.000Ef00 f 0.000Ef00 t
! P32 8 CI ! 0 000Ef00 1 0.000E400 1 0 000E400 1 0.000Ef00 t
! CR91 1 CI ! 0.000E400 1 0.000Ef00 1 0.240E-03 1 0.407E-02 I1 MN34 i CI ! 0.000E400 t 0 000E4SO 1 0 000Ef00 1 0.380E-02 !
! MN56 1 CI 1 0.000Ef00 1 0 000Ef00 1 0.000E400 1 0.000Ef00 t t FESS ! CI t 0.000Ef00 ! 0.000Ef00 1 0 509E-03 1 0 433E-02 8 I FE59 i CI ! 0.000Ef00 1 0.000E400 ! 0.000Ef00 t 0.317E-04 I 1 C058 i CI 1 0.000Ef00 3 0 000Ef00 1 0.000Ef00 1 0.100E-02 8
! C060 1 CI i 0 000Ef00 1 0.000EiOO ! 0.572E-04 8 0.509E-02 !
I NI63 ! CI I 0.000Ef00 1 0.000Ef00 t 0.000Ef00 1 0.000Ef00 !
! N!65 1 CI- 1 0 000E400 1 0.000Ef00 1 0.000Ef00 1 0.000EiOO !
...............................m....................................... '
1 CU64 ! CI 1 0.000Ef00 1 0 000Ef00 3 0.000E400 1 0.000Ef00 t t- ZN65 i CI ! 0.000E400 t 0 000Ef00 1 0.566E-04 1 0.432E-02 1
! ZN69 .i CI ! 0.000Ef00 1 0.000Ef00 1 0 000Ef00 3 0.000Ef00 t
!- BR83 i CI ! 0.000E400 1 0 000EiOO i 0.000Ef00 1 0 000E400 i
! BR04 i CI- 1 0.000Ef00 1 0.000Ef00 t 0.000Ef00 ! 0.000Ef00 t i BRB5 ! CI ! 0.000Ef00 ! 0 000Ef00 ! 0.000Ef00 1 0 000Ef00 t C
ENTER [ C 3.TO ERASE SCREEN AND CUNTINUE !
FAGE 2 Or 5 SITE! LINERICh UNIT! 03 ,* USEkt HART DATEt 08/19/92 07113
' EFFLUENT ANL' WhS1C DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT! 1 LIQUID RAD WASTE DISCHARGE TO SCHUYLEILL RIVER CUNTINUOUS 60DE BATCH NODE J
00ARTER I OVARTER ! OVARTER 1 .
't NUCLIDES ! UNITS t OUARTER !
! 2 ! ! ! 2 1
! RELEASED 1 1 1 LICUZD EFFLUENTS (CONTD) ..
! RP86 ! CI ! 0 000Ef00 1 0.000E400 1 0.000E400 1 0.000E400 t t RBBB t CI ! 0.000E400 1 0.000Ef00 1 0 000Ef00 1 0.000Ef00 1 t RPB9 I CI 1 0.000E400 1 0.000Ef00 1 0.000Ef00 1 0.000E400 t SR89' ! CI t 0.000Ef 00 1 0.000E4 0' 1 0.509E-04 1 0 144E-03 1 1 -
I SR90 t CI t 0.000Ef00 1 0.000Ef00 1 0 000Ef00 1 0 000Ef00 t 1 SR91 ! CI i 0 000E400 1 0 000E400 1 0.000Ef00 1 0.000Ef00 t
! SR93 1 CI ! 0 000Ef00 1 0.000Ef00 1 0.000EiOO I 0 000E400 t ! Y90 1 CI I 0 000E400 1 0 000E400 1 0 000Ef00 1 0.000Ef00 !
l Y91H ! C1 1 0.000E400 1 0 000E400 1 0.000Ef00 1 0.000Ef00 t
! Y91 1 CI I 0 000Ef00 1 0.000Ef00 1 0.000E400 1 0.000Ef00 t
! CI I 0.000E400 1 0 000E400 1 0.000Ef00 1 0.000Ef00 t
! Y93 t Y93 ! CI 1 0 000Ef00 1 0 000Ef00 1 0.000EiOO ! 0 000Ef00 t
! 3R95 1 CI t 0 000E400 1 0 000EiOO t 0.000Ef00 1 0.000Ef00 t
! 2R97 I CI 1 0.000Ef00 1 0 000Ef00 1 0.000Ef00 ! 0 000E400 t z! NB93 ! CI' t 0 000Ef00 1 0.000Ef00 1 0.000E400 1 0.0000100 1
! M099 LI -1 0 000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 I 1
TC99M- 1 CI 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 t
? 't TC101 ! CI t 0 000Ef00 1 0.000Ef00 1 0.000E400 1 0.000Ef00 1 C
ENTER [ C 3 TO ERASE SCREEN AND CONTINUE i i
+
FAGE 3 0F 5 . i SITE! LIHERICK UNIT! U1,. USER! NART DATE! 08/19/92 07123 EFFLUENT AND WASTE DISPOSAL REPORT 1 L30ll3D ErrLUENTS FOR RELEASE POINT! 1 LIQUID RAD WASTE DISCNARGE TO SCHUYLN!LL RIVER
/ CONTINUOUS H0DE PATCH H0DE I NUCLIDES i UNITS t OUARTER 1 00ARTER 1 QUARTER ! 00ARTE0 t .
! ! 2 1 1 1 2 I
! RELEASED ! 1
- LIQUID EfrLUENTS (CONTD) t RU103 1 CI i 0 000E400 1 0 000Ef00 1 0.000Ef00 1 0.000Ef00
?! RU105 i C1 1 0.000Ef00 1 0 000Ef00 1 0 000Ef00 1 0.000Ef00 t 1 RU106 ! CI t 0 000E400 1 0.000Ef00 1 0 000Ef00 1 0.000E400 t 1 A0110M i CI I 0.000Ef00 1 0.000E400 t 0.000Ef00 1 0.000Et00 1 t TE125N t CI ! 0.000Ef00 t 0 000E400 1 0 000Ef00 1 0.000Ef00 t j 1 TE127H I CI ! 0 000Ef00 ! 0.000E400 t 0 000Ef00 1 0.000Ef00 t 't TE127 t CI 1 0.000E400 t 0.000E400 ! 0.000Ef00 1 0.000Ef00 t I TE129M t CI i 0.000Ef00 l'O.000Ef00 ! 0.000Ef00 1 0.000E400 t , ! TE129 t CI i 0 000E400 8 0.000Ef00 t 0.000Ef00 1 0.000EiOO t f 1 TE131H t C1 1 0.000Ef00 t 0 000Ef00 1 0.000Ef00 1 0.000Ef00 i ! TE131 1 CI t 0.000Ef00 t 0.000E400 t 0.000E400 1 0 000E400 t I TE132- -1 CI I 0.000Ef00 1 0.000E400 1 0.000Ef00 1 0.000Ef00 t -1 3130 t 'CI 0.000E400 ! 0.000Ef00.! 0.000Ef00 1 0 000E400 t -! 1131 !. CI ! 0.000Ef00 1 0.000Ef00 1 0.000E400 1 0.000Ef00 t , ...................................................................... )
1 1132 - t CI 1 0.000Ef00 1 0.000Ef00 1 0.000Cf00 t 0.000Ef00 t ..
.............................c........................................ -! 1133 ! C1 t 0 000EiOO t 0.000Ef00't 0.000Ef00 1 0.000EiOO t l 1834 ! CI' $ 0.000Ef00 1 0.000E400 ! 0.000Ef00 1 0.000Ef00 t ! 3135 t CI t 0.000Ef00 ! 0 000Ef00 1 0.000E400 ! 0.000E400 t ,
ENTEF'E C 3 TO ERASE SCREEN AND CONTINUE $ C
I' PAGE 4 Or 5 l SITE! LIMERICK ,. jUNITI U1 f
- USER MART DATE! OR/19/92 07114
( ] -, 1
~
Mt EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUEN15 FOR RELEASE POINT! 1 LIQUID RAD WASTE DISCHARGE TO SCHUYLKILL RIVER CONTINUOUS N0DE BATCH MODE 00ARTER ! OUARTER 1 QUARTER ! 00ARTER 1
! .NUCLIDES ! UNITS 1 ! 2 1 2 ! !
RELEASED 1 1 1 1 LIQUID EFFLUENTS (CONTD) t CS134 1 CI t 0.000E100 1 0.000Ef00 1 0 000Ef00 1 0.644E-04 1 1 CS136 ! CI ! 0.000E400 1 0.000E400 1 0 000E400 1 0.000Ef00 t t C9137 ! CI 1 0 000Ef00 1 0.000Ef00 1 0.000Ef00 1 0 173E.03 I I CS138 ! CI t 0.000Ef00 1 0 000Ef00 1 0 000Ef00 1 0.000Ef00 1 BA139 i CI t 0 000E400 1 0.000Ef00 1 0.000E400 1 0.000Ef00 t 1 BA140 i CI t 0 000Ef00 1 0.000Ef00 ! 0.000E400 1 0.000EiOO ! I BA141 1 CI ! 0 000E400 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 t t DA142 i CI 1 0.000Ef00 8 0.000Ef00 ! 0.000Ef00 1 0.000Ef00 t , t LA140 1 C1 1 0.000E400 1 0.000E400 1 0.000Ef00 1 0.000E400 t I LA142 1 CI 1 0.000Ef00 1 0.000E+00 1 0.000Ef00 1 0.000Ef00 t
! CE141 1 CI i 0.000Ef00 t 0.000Ef00 1 0.000Ef00 1 0 000Ef00 t
! CE143 1 CI ! 0.000Ef00 8 0 000Ef00 t 0.000Ef00 ! 0.000Ef00 t I CE144 ! C1 1 0 000E400 1 0.000Ef00 1 0.000Ef00 t 0.000E400 t PR143 i CI ; 0.000Ef00 1 0.000Ef00 1 0 000EfE0 1 0.000Ef00 t 1
! PR144 1 CI t 0 000EiOO ! 0.000Ef00 1 0.000E400 1 0 000Ef00 t I HD147 i CI 1 0.000Ef00 t .000EiOO 0.000Ef00 1 0.000Ef00 t I AS76 ! CI ! 0.000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000E400 t I W187 t CI 1 0 000E100 1 0 000Ef00 1 0.000Ef00 1 0.000Ef00 t C
ENTER E C 3 TO ERASE SCREEN AND CONTINUE !
- - - - - -__ _____ _ ___ _ '"" " ' - - ' * ~ ,_,
t' 1 L i I e.I
' PAGE 5 0F 5 ,
%iL: LIHERICK
%i, NIT: U1
- USER: MART DATE! 08/19/72 07!34 :
EFFLUENT AND WASTE DISPOSAL REPORT , i LIQUID EFFLUENTS FOR RELEASE POINT: 1 LIQUID RAD WASTE DISCllARGE TO SCHUYLKILL RIVER
.- BATCH H0DE .
CONTINUOUS MODE r
...................................................................... QUARTER 00ARTER NUCLIDEF UNITS : QUARTER : QUARTER
- 1 : 2 :
- 1 1 2
! RELEASED i
LIQUID EFFLUENTS (CONTD) .. ... ......
- CI 0 000Ef00 1 0.000Ef00 1 0.000F 0.000Ef00 NDNE 1
TOTAL FOR ! : ' 1- PERIOD : CI : 0.000C400 0.000Ef00 : 0.143E401 : 0.608Ef01 : i ! ! (ABOVE) : : : i 8 l XE-133 : CI 0.000Ef00 1 0.000Ef00 : 0.967E-03 : 0 804E-03 :
! XE-135 : CI : 0 000EiOO 0.000Ef00 : 0.485E-03 : 0.361E-03 :
I i. i l i l l l
. _ _ . _..._..___. _. .. - . . _ _ _ . _ _ _ . . _ -_ __ .._.__.. .._ . . . _ . .. . -_m_- .... .. . _ _ -... . _ . . _ .
f J J I
- II. TABLES .
i i C. SOLID WASTE DISPOSITION REPORT , .- -t January 1, 1992 to June 30, 1992 t
?
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___ _ - - _ _ - _ _ . _ - - _ _ _ . - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - ^ ' - ^ - ^ ' ' ^ ^ ' ^ ' ^ ^ ' '
4 i . r e w t.,i !. 5. 0. $. $. N. U. $. E. N. $. $. $. $.
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O O m in - w . . O
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, :=
.. 1888885858088.8888888888888888
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1 III. ATTACHMENTS N. EUPPLEMENTAL INFORMATION Pacility: Limerick Generating Station - Units 1 and 2 Licenses NPF-39 (Unit 1) and NPP-85 (Unit 2)
- 1. Regulatory Limits (Technica) Specification Limits)
A. Noble Gases:
- 1. < 500 mRems/Yr - total body -
" instantaneous" limits E 3000 mRems/yr - skin per Tech Spec 3.11.2.1
~
and OnCM Contro2 3.3.2 2 5 10 mRads - ai r ganmta - quarterly air dose limits per Tech Spec. 3.11.2.2 - 5 20 mRads - air beta and ODCM Control 3.3.3 3 5 20 mRads - air gamma - year)y air dose limits
-< 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 days:
- 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 < 10CFR20 " instantaneous" limits per Appendix B, Ta5le II, Col. 2 Tech. Spec. 3.11.1.1 and ODCM Control 3.2.2 3 mRems - total body - quarterly dote limits per 25 Tech. Spec. 3.11.1.2 5 10 mRems - any organ and ODCM Control 3.2.3 3 5 6 mRems - total body - yearly dose limits per 5 20 mRems - any organ Tech. Spec. 3.11.1.2 ar.d ODCM Cont rol 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 releasen.
The MPCs specified in 10CFR20, Appendix B, Table II, Column 2 for identified nuclides are ured to calculate permissible release rates and concentrations for liquid releases.
'3 . Average Energ,y basedongaseouseffluent releases for the report period, average l beta energy is 0.170 MeV and average gamma energy is 0.115 MeV.
- 4. 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. lodine: The method used is the Canberra Series 90 Counting System; Cll - Charcoal Cartridge. C. Particulate: The method used is the Canberra Series 90 Counting System; PT - Air Particulate Sample, 47 mm filter. D. Liquid Effluents: The method used is the Canberra Series 90 Counting System and the Raduaste Liquid Discharge Pre-Release Method with a 3.5 liter Marinelli.
- 5. Batch Releases Q1 02 A. Liguid 33 104
# of Batch Releases:
Total time period for batch releases,
- 2283 7270
- 145 87 Maximum time period for a batch release, Average time period for batch release,
- 69.18 69.90 Minimum time period for a batch release,
- 52 58 Average stream flow (Schuylkill River) 7.94C5 8.83E5 during periods of release of effluents into a flowing stream, gpm
* = Minutes
B. Gaseous 01 02 - 29 4 4 of Batch Releases: Total Time period for batch releases,
- 155550 13020 Maximum time period f or a bate: 4 release,
- 44640 7620 Average. time period for batch release,
- 536'4 3255 Minimum time period for a batch release,
- 10 1260
* = Minutes
- 6. Abnormal Releases A. Liquid -
None D. 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 u 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 1
ill. ATTACllMENTS I D. PROCESS CONTROL PROGRAM (PCPj, REVISION 1 RW-803, Solid Radwaste System Process Control Program (PCP) was revised during this reporting period. A copy of RW-600 is included in this report. The following cuthinarizes those changes which were incorporated into RW-BOC, Revision 1:
- 1. Section 2.0 was revised to incor porate section 13.1 of the UPSAR.
- 2. Section 6.1.3 was added to clarify the processing of Condensate Deep Bed Demineralizer sludge.
- 3. Section 6.1.4.6 was revised to include steps 6.2.2.2 through 6.1.2.7. _
- 4. Attachment 8.2 section 9(B) was revised to include Condensate Deep Bed Deminerali::er sludge into the definitions.
I RW-800, Rev. 1 , l P^9e f 20
. 3924015740 NJH/DPM/KJC/rgs l
PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION she/92 p HW-800' SOLID RADWASTE SYSTEM PROCESS CONTROL PROCRAM (PCP)_ 1.0 PURPOSE This program provides guidance and boundary conditions for preparation of specific procedures for processing, sampling, analysis, packaging and shipment of solid radwaLte in accordance with State and Federal Regulatory requicements. 3.1 This program is applicable to the Limerick 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 compliar.ce with 10CFR61 by:
- a. Defining the various waste streams.
Establishing a set of process parameters that affect b.
' solidification and developing operational controls for those parameters.
- c. Implementing a Waste Classification System in accordance with 10CPR61 and applicable Regulatory Guidance,
- d. Providing an appropriate Quality control Program as required by 10CFR20.311. S
- e. Implementing procedures for processing, I
containerization and transport of waste to ensure specific DOT, NRC, and burial site requirements are satisfied. i 2.0 RESPONSIBILITY NOTE: The station operating organization is outlined in section l 13.1 of the UFSAR. 2.1 PORC is responsible for reviewing all revisions to the PCP. 2.2 The Plant Manager is responsible for approving all revisions to the PCP. 2.3 The Nuclear Quality Assurance Department performs audits to ensure compliance with the Quality Assurance plan. l
RW-800, kev. 1
- l Page 2 of 20 NJ11/DPM/KJ C/ r gs l (
2.4 All PECo and PECo contract personnel are responsible for implementation of p;ocedures and good practices so as to provide quality Assurance and maintain exposures ALARA. 2.5 The Engineer-Radwaste is responsible for: 2.5.1 Compliance with this Process Control Program. 6 2.5.2 Record keeping and document control of shipping and processing data. 2.5.3 Assuring that radwaste personnel are appropriately trained and qualified. 2.5.4 Coordinating reviews and revisions to thi, document and corresponding implementing procedures. 2.5.5 Reviews and revisions to this PCP and its implementing procedures. 2.6 The Superintendent-Operations is responsible for: 2.6 2 Providing trained personnel to operate appropriate radwaste process equipment. 2.6.2 Defining those Operations positions which require training. 2.7 The Superintendent-Training is responsible for: 2.7.1 Development and implementation of performance-based training for designated personnel utilizing the Training Systems Development (TSD) model in . accordance with Training Division procedures. 3.0 PREREQUISITES 3.1 Prior to revising or deleting a PCP implementing procedure, the preparer shall review the procedure against the PCP to ensure that there is no compromise or conflict. 3.2 Prior to a modification to an inplant liquid radwaste processing system the individual responsible for the MOD shall review to ensure that it is not in conflict with or compromises the PCP. When conflict or compromise is identified it shall be resolved. 3.3 Processing of solid radioactive waste . hall be performed by qualified and trained personnel. Trait ng records for operators of mobile vendor processing units shall be maintained by the Engineer Radwaste while the vendor is active on-site. These records shall be sent to the Nuclear Records Management System after the vendor has completed work on-site.
--_---_ -_ -'"-^- --- -__ __ .
l RW-800, Rev. 3 l l Page 3 of 20 NJil/DPM/KJ C/ r g s l 3.4 Vendor services may be used for radioactive waste ' processing providtd the cervices are governed by an NRC approved Topical Report. Processing of radioactive waste l by on-site vendors shall be performed in accordance with applicable Topical Report, procedures and NRC guidance. 3S The Topical Reports of vendor supplied radwaste processing systems shall un+ rgo 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 beManagement performed in accordance with review shall include applicable RW procedures. a review of plant-to-vendor equipment interface. 3.6 On-site processing radioactive waste shall be performed in . accordance with approved ctation 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 he reviewed by PORC and approved by the Plant Manager (Ref. 7.19). 5 4.2 Sections of the PCP (RW-800) referring to Generic Letter 99-01 (Raf. 7.lR) shall not be deleted without the approva) of the Engineer-Padwaste. 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 f or the operation of the pr ocess ' 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 Rele se Report for the period in which ' the change was made. This shall be done an accordance with ODCM Section 13.6. 4.5 Changes to resin dewatering implementingthe procedures or free standing & systems shall require verification that's water content of the packaned product within the limits established by regulatory ainits via ST-0-RRR-733-0. 4.6 When processing does not meat disposcl site and shipping and transportation requiremtats, shipment shall be suspended and the Process Control Program (RW-600), the implement)ng procedures and/ot the solid waste system shall be corrected as necessary to prevent recurrence (Ref. 7.18). i
\
. _ . . . ..__.._ _ _._ _ _ _ . . _ . . . _ ~
. RW-800, Rev. 1
*l-.- Fage 4 of 20
~<- * .
NJil/DPM/KJC/rgs I. . i 1 4,7 When processing is not perfotmed in accordance (RW-with th , each- cor.tainer_ shall be reprocessed to conform to PCP i 800) requirements and appropriate administrative action l shall be take'n to prevent recurrence. , , I
$.0 APPkRATUS f N/A ,
s 6.0 PROCEDURE a Vendor services riay be used to process any radioactive waste stream provided the services are performed with an . acceptable Process Control Program. ] 6.1 Process Description wil -waste streams Processing of solidare defined inwaste radioactive Attachment shall-be 8.2. 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 FILTER /DEMINERALIZER SLUDGE 6.1.2.1 Each-condensate filter /demineralizer 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 As the sludge settles, in a Condensate Phase Separator. clarified liquid is decanted. . 6.1.2.3 For centrifuge-dewatering of the settled sludge, the phase separator _ is isolated when approxi.mately 240 cubic feet of- l* K sludge has-secamulated.- 6.1.2.4 For vendor dewatering of f the settled sludge, the pnase separator is isolated , when approximately 400 cubic feet of
-sludge-has accumulated. .
I 6.1.2.5 The settled sludge is- ready for
-dewatering while further backwashes are routed to alternate phase separators.
. - , , _ m.-, - , - - . .,---_..__-__._,,_.m ,..- _ ._ . . _ _ _.-. _ .... _ -._. _.-..~ - _ ..-,..
s KW-800, Rev. 1 3, hfS l Page 5 of 20 , 8 NJil/DPM/KJC/rgs H 6.3.2.6 The phase separator contents are . recirculated for a minimum of 30 minut?s to mix contents of the vessel, resulting in a homogenous resin slurry. (For ' centrifuge dewatering, tho mixture should not exceed 5% dry weight concentration.
,' Por' Vendor dewatering a higher
* ' concentration can be achieved.
6.1.2.7 The solido slurry is then fed to a centrifuge or to the External Processing Station for dowaterirg as appropriate. 1 6.1.3 CONDENSATE DEEP BED DEMIHERALIZER SLUDGE _ k 6.1.3.1 Each coradensate deep bed demineralizer backwash consists of approximately 2800 gallons of slurry with approximately 16,130 lbs. (dry wt.) sport resins and crud. 6.1.3.2 Each backwash contain', 320 cubic feet of resin and is collected in an empty Spent 1 Resin Receiver Tank. 6.1.3.3 During normal operations the Spent Resin Receiver Tank contents will be sent to the Ploor and Equipment Drain deep bed demineralizers for reuse. 6.1.3.4 Resins that are determined unacceptable for reuse or excess will be processed from the 1A Spent Resin Receiver Tank
-using vendor-dewatering.-
6.1.3.5 The 1A Spent Resin Receiver Tank Contents are recirculated for a minimum of 25 minutes to mix contents of the vessel, resulting in a homogeneous resin slurry.- 6.1.3.6 The solids slurry is then fed to the External Processing Station for dewatering. 6.1.4 WASTE SLUDGE 6.1;4.1 Each backwash'from a radwaste or fuel pool filter demineralizer consists of approximately 1,500 gallons ofLslurry, with approximately 60 lbs. (dry wt.) spent resins and crud. L,. ...... .. - .
4 RW-800, Rev. 3 l Page 6 of 20 NJH/DPM/KJC/rgs l,, 6,1.4.2 Each backwash from a radwaste deminera31zer consists of approximately 1,500 gallons of slurry, with an average of 2,125 lbs. (dry wt.) spent resins (may contain charcoal overlay). 6.1.4.3 Successive backwashes from radwaste
. filter demineralizers, radwaste deminerulizers, and fuel pool filter /demineralizers are collected in the Waste Sludge Tank until approximately
- 12,000 gallons of liquid and resin sludge are accumulated.
6.1.4.4 The Waste Sludge Tank contents are $ recirculated fcr a minimum of 45 minutes to mix contents of the tank, resulting in a homogeneous resin slurry ranging from 0.5 to 6% (dry wt.) total solids. During normal operation the Waste Sludge Tank contains only the radwaste and fuel pool filter demineralizer backwashes which result in a 0.5% (dry wt.) total colids 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. C 6.1.4.5 The solids slurry is fed to a centrifuge for dewatering or to the External Processing Station for dewatering as _ appropriate, e.l.4.6 Waste Sludge Tank contents may also be sent to a condensate phase separator for processing in accordance with steps 6.1.2.2 through 6.1.2.7. 6.1.5 REACTOR WATER CLEANUP P1LTER/DEMINERALIZER SLUDGE 6.1.5.1 Each RWCU filter /demineralizer backwash consists of approximately 1,100 gallons of slurry with approximately 4P lb. (dry wt.) spent resins and crud. 6.1.5.2 Successive backwashes are collected and allowed to settle in a phase separator. As the sludge settles the clarified liquid is decanted, i
\
RW-800, Rev. 1 , l Page 7 of-20 ' NJil/DPM/KJC/rgs j,, 6.1.5.3 For centrifuge dewatering of the settled sludge, the phase separator is isolated of when approximately 140 cubic feet sludge has accumulated. . 6.1.5.4 For vendor dewatering of the settled sludge, the phase separator is isolat of
's. hen approximately 160 cubic feet
.' sludge has accumulated.
I 6.1.5.5 The settled sludge is ready for - dewatering while further backwashes are routed to alternate phase separators. 6.1.5.6- The phase separator contents are . recirculated for a minimum of 30 minutes to mix contents of the vessel, resulting in a homogenous resin slurry. (For Jcentrifuge dewatering, the mixture should not exceed 5% dry weight concentration. Por Vendor dewatering, a higher concentration can be achieved). 6.1.5.7 The solids slurry is ther. fed to a centrifuge or the External Processing
/~ Station for dewatering as appropriate.
Note Resjn sludges from different waste streams and different units.may be mixed to_ optimize packaging ~and " _ characterization, houever these quantities shall be . . documented. 6.1.6: DRY ACTIVE WASTE (DAW) 6.1.6.1 DAW is processed by an off-site vendor " b ' prior to disposal. 6.1.7 OILY WASTE 6.1.7.1 Oily waste generated during 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-accesc enclosed area for temporary storage.
- 6. ~ .7.2 . Oily waste can be solidified in appropriate containers by vendor supplied equipment in accordance with approved vendor process control procedures.
9
RW-800, Rev. 1
, l Page 8 of 20 NJH/DPM/KJC/rgs j,
6.1.7.3 Olly waste may be processed through decontamination to levels which may be free released as non-contaminated The material or non-contaminated waste. contaminat9d byproducts of this decontamination process may be processed as DAW. p 6.1.7.4 Olly waste may be shipped off-site for processing by appropriate vendors on the PCCo evaluated vendors list. 6.1.8 IRRADIATED kEACTOR COMPONENTS 6.1.8.1 Irradiated reactor components are sampled, cut as necessary, loaded into liners in accordarice with applicable station procedures. 6.1.9 MISCCLLANCOUS PILTERS 6.1.9.1 CRD Pilters are loaded into appropriate containers and shipped for burial in accordance with applicable station procedures. 6.2 DEWATERING PROCCSS CONTROL 6.2.1 Centrifuge Rosin S)udge Dewatering 6.2.1.1 The 0.5-61 solids slurries discussed in a Section 6.1 are fed to a centrifuge at controlled flow rate for dewatering. 6.2.1.2 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. 6.2.1.3 The centrifuged resin is packaged in appropriately selected liners Processor High Integrity containers (HIC). System level probes extending into tne liners or HICs ensure that void spaces within the container are minimized to the extent practical. 6.2.2 Vendor Resin Sludge Dewatering
RW-800, Rev. 1 . l Page 9 of 20 , NJH/DPM/KJC/rgs i l, I 6.2.2.1 The slurries discussed in Section 6.1 are ' fed to vendor dewatering systems at approximately 30 to 50 gp1 "la the 'n External' Processing Station. located 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 i humidity are monitored to ensure optimum ; operation and compliance with the free standing water criteria for burial. 6.2.2.3 Vendor dewatered resin is packaged in appropriately selected liners or High Integrity Containers (HIC). Process system level probes and/or video cameras ,' mounted within the fill head ensure the liner or HIC is filled without undue void spaces to the maximum extent practical. c 6.2.3 Approved Resin Sludge Dewatering Vendors ; 6.2.3.1- For Vendor dewatering described in 3 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-~submitt?d to:the NRC. 6.2.3.2 For Vendor dewatering described in Section 6.1 and-6.2 theJLN 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, previously submitted to the NRC. 6.2.3.3 For_._ Vendor dewatering; described in Sections 6.lrand.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, p.eviously submitted to the NRC.
. RW-800, Rev. 1 j Page 10 of 20 NJH/DPM/KJC/rgs j.
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-05-011P-A, previously submitted to the NRC. 6.3 10CRP61 IMPLEMENTATION 6.3.1 Waste Classification - A computerized RADRAN, waste is classification and shipping program, 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. 6.3.1.1 -Por DCWATURED RESIN, waste classification shall be based upon dose-to-curie calculation and the use of scaling , factors for hard to measure isotopes. After each container fill, appropriate dose rates are obtained and entered into Radman. 6.3.1.2 For DRY ACTIVE WASTE (DAW), waste classification shall be based upon isotopic analysis and the use of scaling ' factors for waste sludge or representative smears along with dose-to- ' curie conversion. ~ 6.3.1.3 For OILY WASTE, 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. 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 oasis. 6.3.1.5 For MISC. Pilters, waste classification shall be based upon dose to curie calculation and the use of scaling factors for hatd to measure isotopes.
l kW-800, Rev. 1* l Page 11 of 20
!;JH/DPM/KJC/rgs -
l , 6.3.1.6 A detailed analysis is petformed annually to identify isotopi abundances and scaling factors t ir ~h use of ST-0-RRR-731-0, ST-0-RRR-732 ., and ST-0-RRR-734-O. 6.3.1.7 Radionuclide concentrations and
. classification of future waste shipments are expected to be similar to those of previous shipments Values forare each specific available frc,m waste stream.
shipment manifest forms. 6.4 WASTE STABILITY 6.4.1 M!nimum Stability Requirement 6.4.1.1 Waste at Limerick Generating Station is packaged in metal containers (drums, boxec, liners) or High Integrity Containers. In no case shall radioactive waste be packaged in cardboard or fiberboard boxes for burial. 6.4.1.2 Dewatered resin is sampled annually as a minimum to verify the free standing water content of the packaged product is within the limits established by applicable In regulatory limits via ST-0-RRR-733 0. addition to the annual verification, the free stand'nq water is determined whenever proceas changes occur that may significantly alter system dewatering performance. Performance of ST-0-RRR-733-0 serves as a demonstration of system operability and for ensuring the waste form is similar to that indicated in prequalification testing. 6.4.1.3 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:
- 1. The container is equipped with a vent to prevent accumulation of such gas.
RW-800, Rev. 1 l Page 12 of 20 l NJH/DPM/KJC/rgs lJ
- 2. A determination by calculation, test, or measurement is performed to ensure that hydrogen generatien is limited to a molar quantity that would be no more than 5% by volume of the secondary container gasthat voidis at STP over a period of time twice the expected shipment time.
- 3. The cask cavity will be inerted. ,
utility 6.4.1.4 Experience has demonstrated that waste streams do not contain or generate toxic gas, vapors, or fumes and do not contain hazardous, biological, pathogenic, or infectious materials. Radioactive wastes shall have no 6.4.1.5 dwtectable free standing liquids. No detectable free standing liquid shall be defined as not more than l'. of the volume of the waste when the waste is in a disposable container designed to ensure stability or not morefor than waste 0.5% of the processed volume of the waste in any other container. This is ensured using appropriate station procedures. 6.4.2 Waste Stability 6.4.2.1 Dewatered resin requiring stabilization is packaged in High Integrity Containers (HIC) the that have stability requirements been certified of to meet 10CPR61.56(b). The HICs are handled and stored in a manner such that their ability to provide The stabilization chemical and is not physical compromised. 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. to 6.4.2.2 All reasonable efforts are made 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.
~---- - _ _ _ _ __ _ _ ____ _ __------'-------___m . _ _ _ ,
RW-800, Rev. 1
'l Page 13 of 20 .
NJH/DPM/KJC/rgs l *, 6.4.4 Shipment Manifests 6.4.4.1 Each waste shipment shall te accompanied by a shipping manifest giving a phys'.al description of the waste, the volume,the the radionuclide identity and quantity,
, total radioactivity, the principal c chemical form, and waste class.
Quality Assurance Program 6.4.5 6.4.5.1 The quality assurance program consists of required use of plant procedures which implement the Process Control Program and requirements of the Corporate Quality Audits by personnel Assurance Program. independent of the Octivities are by appropriate performed and reviewed management personnel. 6.4.5.2 In addition, the Process Control Program (RW-800) and implementing procedures are audited once per 24 mont ;s by the Nuclear
~
Review Board in accordal;e with Plant l Technical Specification 6.5.2. 6.4.5.3 Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures. 6.5 _ REVISING THE PCP (RW-800) 6.5.1 Revisions to the PCP (RW-300) shall be reviewed by PORC and approved by'the Plant Manager. 6.5.2 Revisions to the PCP (RW-800) to incorporate vendor supplied process' systems shall be performed in the 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 PCP (RW-800) the shallTopical submitted be revised to reference Report. 6.5.2.3 For vendors who have not submitted a Topical Report to the NPC for review, the PCP (RW-800) shall be revised to include the vendors Topical Report as an attachment. 1 _ - - i
RW-800, Rev. 1
'[ Page 14 of 20 NJH/DPM/KJC/rgs-Ti' 6.5.4 All revisions to.the PCP (RW-800) shall be reported to the NRC in the Semi-Annual Effluent Release Report _in accordance with the off site dose calculation manual via ST-0-RRR-990-0. .
16 . 6' SURVEILLANCE REQUIREMENTS FOR SOLIDIFICATION
.s
-6.'6.1 At let t one-representative test specimen from at least every isnth batch of waste shall be
' solidified. See Ref 7.18. ..
6.6.2 If any test specimen fails to verify solidification, the solidification of the batch
- under test shall be suspended until additional test specimens can be obtained. alternative solidification parameters can be determined and a subsequent-test verifies solidification. See Ref.
7.18. 6.6.3 If the initial test specimen from a batch of waste fails'to verify solidification, representative test specimens from consecuti , batches shall be tested until at least.three consecutive test specimens demonstrate solidification. The Process Control Program (RW-800) shall be modified as requiredSee to assure solidification'of subsequent batches. Ref. 7.18. 6.7 DOCUMENTATION 6 . 7 .1_ Records of allfdata, tests, analysis results, and records of training, inspection, and audits are maintained'in accordance-with. plant QA 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 res"1ts of training, inspection, and-audits are-retained'in accordance with the-LGS Quality Assurance Plan'and. applicable station Administrative procedures. , 7.0 SOURCLi AND REFERENCES 7.1 49 CPR 1 rts 170 through 178. 7.2 10 CFR'P cts 20,-50, 61 and-71.
RW-800,-Rev. 1 - l Page 15 of . l NJH/DPM/KJC/rgs
..l. '
7.3 Standard Re' view Plan'11.4, Rev. 2, 2.including Branch i Technical Position ETSBil-3, Rev. 7.4 Low level Waste Licensing Branch Technical Position on ~ Radioactive Waste Classification.
. 7.5 Low Level Waste Licensing Branch Technical Position on ~
Waste Form. 7.6 South Carolina Department of Health and Environmental 097. Control Radioactive Material License No. E.rnwell Waste Management Facility Site Disposal Criteria. 7.7 7.8- State of- Washington Radioactive Materials License No. WN-1019-2. 7.9 Nuclear Pacific Inc. Topical Report for Dewatering System TP-02-P-A, Rev. l'. 7.10 General Critera for High Integrity Containers (SCDHEC). T. l l PCP Implementing Procedures. 7.11.l' Limerick Radwaste Procedurec (RW) 7.11.2 wimerick Station. Test Procedures (ST) 7.11.'3 Limerick-System Procedures (S) Note: PCP Implementing Procedures are those listed above which apply directly to processing, packaging, sampling, analyzing, and shipping radwaste. 7.12 Nuclear QA Plan 7.13 Chem Nuclear Systems Inc Topical Report RDS-1000 Radioactive Waste Dewatering System RDS-25506-01-NP-A. 7.14 Stock Equipment Co. Topical Report Oulck Dry Process For O. Dewatering Bead Resin and Filter Sludge, SRS-003-P, Rev. 7.15 Westinghouse-Hittman Nuclear, Inc. Topical ReportSTD-R 011-A, Mobile Incontainer Dewatering and Solidification System. 7.16 Generic Letter 89-01 (Implementation of Programatic Controls for Radiological Effluent Technical Specifications [ in the Administrative Controls Section of the Technical L Specifications-and the-Relocation of Procedural oDetails the of RETS to the Offsite Dose Calculation Manual or Process Control Program), 1/31/89. 7.17 Limerick Generating Station Unit _1 and 2 Technical Specifications, 6.5.1.6, 6.8.1, 6.13. i i I
l 1RW-800,'Rev.'1-- l' Page:16 of 20 1 ' NJH/DPM/KJC/rgs ,
-l- 'l ST-0-RRR-732-0, ST-
'7 .1 P L Station Test-Procedures ST-0-RRR-731-0, 0-RRR-733-0, ST-0-RRR-734-0.
L l. 7.19-:ODCM O'.- I 8.0 ATTACHMENTS Sol-idLBadwaste Management System Proceus Flow Diagram RW-8.1 800 Attachment 8.1. 8,2 Definitions (RW-800, Attachment 8.2). Li
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RW-800, Rev. d.. . Page --_18 o f 2 CF NJH/DPM/KJC/rgs 4 ATTACHMENT 8.2 (Page_1 of-3) DEFINITIONS l
-1 . _ -
OPERABLE -.A-System, train, component or device shall be operable.or have operability when it is capable of performing its specified function (s), and when all necessary attendantfinstrumentation, controls, electrical
' power,-cooling or seal water, lubrication 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 cc7tain 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 acceptchie L 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 rorm acceptance criteria.
- 6. LOW-LEVEL RADIOACTIVELWASTE (LLW) - special Those low-level nuclear,1or radioactive wastes containing source,
-by-product material _ that are acceptable for disposal in a
--land _disposalnfacility. -For the purposes of this definition, low-level radioactive waste has the that sameis meaning as'in the Low-Level Waste Policy Act, radioactive waste not classified as high-level radioactive waste, transuranic _ waste, spent nuclear-fuel, or by-product materialias defined in section lle.(2)-of the Atomic Energy Act (uranium or thorium tailings and waste).
RW-800,-Rev. 1 -
-l2 Page 19 of 20- ,
NJH/DPM/KJC/rgs. ATTACHMENT 8.2 .. (Page 2 of 3)
.7. WASTE' CONTAINER - A-vessel of any shape, size, and 1
- composition used_to.contain the final processed waste. i 8.- WASTE FORM - Waste in a waste container acceptable for l c disposal at a licensed disposal facility. ,
j
- 9. WASTE TYPES (A) NON-CONTAMINATED WASTE - Waste containing no detectable contamination.
l -- (B) RADIOACTIVE WASTE STREAMS 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 overlay material, and small 1 concentrations of various solids, activated and non-activated corrosion products.
. CONDENSATE DEEP-BED DEMINERALIZER SLUDGE - The contaminated waste product generated by the
! backwash of the condensate deep-bed demineralizers consisting of contaminated ion exchange bead resins at-varying' degrees of exhaustion and small concentrations of various solids and corrosion products.
- WASTE SLUDGE - The contaminated waste product 1 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 cf various solids and corrosion products.
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 l ion exchange resins at varying degrees of _ exhaustion, fibrous filter media,-and small I concentrations of various solids and corrosion
' products.
.. RW-800, Rev. 1
'jJ Page 20 of 20; NJH/DPM/KJC/r_gs ATTACHMENT 8.2 (Page 3 of 3)
- DRY ACTIVE WASTE - Dry wastes consists of air filters, miscellaneous paper, rags,:etc., from tools
/
contaminated areas; contaminated clothing, and equipment parts that cannot be effectively i
* -decontaminated; and solid laboratory wastes. ,
of' OILY WASTE-WET RADIOACTIVE WASTES - Oils consist non-reclaimable _ contaminated oils and grease-of various grades both synthetic or otherwise in_ free form or containing various amounts of solid material. IRRADIATED REACTOR COMPONENTS - Materials which
-have been i~rradiated through neutron flux from the reactor. This includes but is not limited the start-up sources, LPRMS, SRMS, IRMS, channel clips- _
-and. tips.
t
- 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 IMPLEMENTIN
G. PROCEDURE
S -_Those Limerick specific RW, ST, and S_ procedures which apply directly to processing, packaging, sampling,_ analyzing, and shippiig radwaste..
- 11. SOLIDIFICATION - Waste processed into.the form of aoffree the standing monolith, having.no more'than 0.5 percent waste volume as free-liquids.
L L l~ l
4 III. ATTACHMENTS-(Cont'd) C. Radiation Monitors Out-of-Service On'4/19/92 at 1015, the Unit 1 Service Water Radiation Monitor was declared inoperable due to low flow conditions and highControl counts per minute.(2E10 cpm). With this existing situation, ODCM 3.2.1' Action Statement'"b" was entered. This action states in part:
' With,less thanlthe minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, taKe the ACTION shown in Table 13.2-1. This Action, from Table I3.2-1 states in part to take grab samples at least once per 8 hours and that. the samples are to be analyzed for radioactivity by gamma isotopic analysis.
A defective pre-amp was replaced which was determined to be the cause
-of'the high counts per minute. A temporary change to S26.1.M allowed the Service Water Radiation Monitor to be placed in service until a '
modification (TCl 921103) could be completed. On 7/17/92 at 1700, the Unit 1 Service Water Radiation Monitor was declared operable. -
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