ML20114C045

Semi-Annual Effluent Release Rept 16 for 920101 Through 920630

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 3 10CFR5 0. 3 6 (a ) 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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h 4 '-4 a ) j l c 4 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION -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 Un ted' States Nuclear Regulatory Commission i -Pursuant to Facility Operating License NPF-30-(Unit 1) and NPF-85_(Unit-2) G. L.' Roacp, Services Superintendent r-'r-r. ,c. ,c, e ,-w-,-, -iw-y %,.-,,m,,y-g7.

1 r l 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 B. Process Control Program (PCP) 1 C. Radiation Monitors Out-of-Service l ~ n

v b -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 l_ waste. type and an estimate of-the error in the reported 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. There were no changes to the Offsite Dose Calculation L 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 7 .L,m. m ,,,w -4D rw--e.- -m =w e-

[;r v i j ~. 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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g-7 7

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 !.NUCLIDES

UNITS i QUARTER QUARTER QUARTER QUARTER s

- 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

...___................__......~..___._....___..._______........... KR85

CI

-0.000Ef00 : 0.000Ef00 i 0.191Ef01 0.341Ef00 ;

KR87-CI

0.000Ef00 1 0.000Ef00 : 0.000Ef00 0.000Ef00

.KR88-CI

0.000Ef00': 0.000Ef00 0 143Ef00 ; 0.000Ef00

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 :

TOTAL-FOR : I o PERIOD CI

0.000Ef00 1 0.000Et00 1 0.135Ef03 : 0.341Ef00 :

(ABOVE) l

ENTER E-C ] TO ERASE SCREEN AND CONTINUE :

C 1 .r

m. .~ 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 CONTINUQUS NODE BATCH NODE J 1.NUCLZDES

UNITS :

QUARTER : QUARTER ! QUARTER

QUARTEF: :

RELEASED 1 2 1 2 ~ 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 Ca4

- CI

0.000E+00 1 0.000E+00 : 0.000E+00 0.000Ef00

CRS1

' CI

0 000Ef00 0.000Ef00 0.000E+00 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 : l-.C050 CI

0.090E+00~: 0.000Ef00 : 0.000Ef00-0.000E+00 :

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 :

8 SR90 CI'

0.000E+00 1 0.000E+00 0.000E+00 : 0.000E+00 ZR95-

.CI

0.000E+00.0.000E+00 : 0.000Ef00 0.000E+00 :

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 ! CS136 CI-0.000E+00 : 0 000E+00 0.000E+00 0.000E+00 : 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 RELEASED 1 2 1 2

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, !.NUCLIDES : UNITS : QUARTER QUARTER QUARTER OVARTER

RELEASED 1

2 1 2

1. FIS3!ON OAFES

---................--........----.-...-..----...--...........-- -~ AR41

CI

0 000E+00 : 0.000E+00 1 0.275E-04 0.000E+00 :

KRS3M CI

0.000Ef00 1 0,000Ef00 1 0.000Ef09 : 0.000E+00 1 KRBan CI

0.000E+00 1 0.000E+00 : 0.000Ef00 0.000E+00 !

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 :

- XE138

CI

0.000E+00 : 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! 01;. 7 -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 NUCLIDES-UNITS : QUARTER QUARTER QUARTER QUARTER RELEASED : 1 2 1 2

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 !

IR95 - CI .: 0.000Ef00 : A.000Ef00 0.000Ef00 ; 0.000Ef00 : L ..__e..... ~;- 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 i.NUCLIDES

UNITS :

QUARTER QUARTER QUARTER QUARTER 1 2 1 2 '... 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 !.NUCLIDES

UNITS : QUARTER QUARTER QUARTER :

GUARTER RELEASED 1 1 2 1 2

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 !.NUCLIDES -UNITS : QUARTER OUARTER QUARTER QUARTER i RELEASED 1 2 1 2

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 :

1 CD60 CI

0 000Ef00 : 0.890E-05 : 0.000Ef00 0.000E400 :

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

- ! RELEASED 1 2 1 1 2 i

3. PARTICULATES (CONTD)

BA140 - CI i 0 000T* I 0.000Ef00 i 0.000Ef00 1 0.000Ef00 :

1 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 EFFLUENT AND WASTE DISPOSAL REPORT t ' GASEOUS EFFi.UENTS FOR. RELEASE POINT! 4 HOT MAINTENANCE SHDP i I d BATCH NODE / CONTINUOUS MODE 3.NUCLIDES-UNITS 1 QUARTER : OUARTER GUARTER : QUARTER 'i' RELEASED : 1 2 1 1 2 i

1. F3SSION OASES j

' AR41 CI i 0.000Ef00 : 0.000Ef00 i 0.000Ef00 t 0 000Ef00 :

1. - 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 :

' _t - XE138 -1 CI. t-0.000Ef00 1 0.000Ef00 i 0 000Ef00 t 0.000Ef00 t ~ TOTAL FOR 1 I 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 !.NUCLIDES 1 UNITS.! OUARTER QUARTER OUARTER : QUARTER. ; t RELEASED i i 1 2 1 2 i

2. IDDINES l

1131 CI 1 0.000E+00 1 0.000Ef00 1 0.000E+00 : 0.000E+00 : L..........................._........................................_ l 1 1133 1 CI

0.000E+00 1 0.000E+00 t 0.000Ef00 : 0.000Ef00 t TOTAL FOR !

i ! 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 ENTER E C J-TO ERASE SCREEN AND CONTINUE : C -r-- c.,.,

PAGE'12 0F 12 Sf7E 'AIMERICK' UN!Ti U11- -USER! MART ~ DATEt: 08/19/92 07106 l i EFFLUENT AND WASTE DISPOSAL REPORT-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 1 RELEASED 1 1 1 2 i 1 2

3. PARTICULATES (CONTD)

L! BA140 11 CI-t 0.000Ef00 1 0 000Ef00 1 0.000E+00 1 0.000E400 : p...................................................................... LI CE141 i CI . : 0.000E400 0.000E400 1 0.000Ef00 1 0.000Ef00 i -1 CE344

CI i 0 000EiOO 0.000Ef00 1 0.000Ef00 0.000Ef00 t 1_; TOTAL FOR l-i i

PER30D ! CI

0.000Ef00 2 0 000Ef00 : 0 000Ef00 ! 0.000Ef00 1

(ABOVE) I 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 f

ErfLUENT.AND WASTE DISPOSAL REPORT 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 APPLICABLE 1 1 i i ................ LIMIT 1 -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 1 APPLICA!tLE LIMIT 1 i 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 : APPLICABLE LIMIT I 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 : 1 -USED DURING PERIOD l

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 !.NUCLIDES ! UNITS ! OUARTER 1 QUARTER t 00ARTER i QUARTER 1 RELEASED 1 1 2 2 8 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 ENTER [ C 3.TO ERASE SCREEN AND CUNTINUE ! C

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 't NUCLIDES ! UNITS t OUARTER 00ARTER I OVARTER ! OVARTER 1 ! RELEASED 1 1 1 2 2 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 1 SR89' ! CI t 0.000Ef 00 1 0.000E4 0' 1 0.509E-04 1 0 144E-03 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 Y93 CI I 0.000E400 1 0 000E400 1 0.000Ef00 1 0.000Ef00 t 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 1 LI -1 0 000Ef00 1 0.000Ef00 1 0.000Ef00 1 0.000Ef00 I ? 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 ENTER [ C 3 TO ERASE SCREEN AND CONTINUE i C 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 RELEASED 1 2 1 1 1 2 I - 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 ~ EFFLUENT AND WASTE DISPOSAL REPORT Mt LIQUID EFFLUEN15 FOR RELEASE POINT! 1 LIQUID RAD WASTE DISCHARGE TO SCHUYLKILL RIVER CONTINUOUS N0DE BATCH MODE !.NUCLIDES ! UNITS 1 00ARTER OUARTER 1 QUARTER 00ARTER 1 1 RELEASED 1 1 1 1 2 2 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 1 PR143 i CI

0.000Ef00 1 0.000Ef00 1 0 000EfE0 1 0.000Ef00 t 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 ENTER E C 3 TO ERASE SCREEN AND CONTINUE ! C ~

t' 1 L i I PAGE 5 0F 5 e.I %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 CONTINUOUS MODE BATCH H0DE r NUCLIDEF UNITS : QUARTER QUARTER QUARTER 00ARTER RELEASED 1 1 2 1 2 i LIQUID EFFLUENTS (CONTD) 1 NDNE - CI 0 000Ef00 1 0.000Ef00 1 0.000F 0.000Ef00 TOTAL FOR ! 1-PERIOD CI

0.000C400 0.000Ef00 : 0.143E401 : 0.608Ef01 :

8 (ABOVE) i i 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 ? f 5 t . Y [ e + 4 r en +if-e W

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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: " instantaneous" limits 1. < 500 mRems/Yr - total body 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 5 20 mRads - air beta per Tech Spec. 3.11.2.2 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 25 3 mRems - total body - quarterly dote limits per 5 10 mRems - any organ Tech. Spec. 3.11.1.2 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. Measurements and Approximations of Total Radioactivity 4. 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

1. of Batch Releases:

2283 7270 Total time period for batch releases, 145 87 Maximum time period for a batch release, 69.18 69.90 Average time period for batch release, 52 58 Minimum time period for a batch release, Average stream flow (Schuylkill River) 7.94C5 8.83E5 during periods of release of effluents into a flowing stream, gpm = Minutes

01 02 - B. Gaseous 29 4 4 of Batch Releases: 155550 13020 Total Time period for batch releases, 4 release,

• 44640 7620 Maximum time period f or a bate:

536'4 3255 Average. time period for batch release,

• 10 1260 Minimum time period for a batch release,
• = 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..2 section 9(B) was revised to include Condensate Deep Bed Deminerali::er sludge into the definitions.

RW-800, Rev. 1 l 3924015740 P^9e f 20 NJH/DPM/KJC/rgs l PHILADELPHIA ELECTRIC COMPANY she/92 p LIMERICK GENERATING STATION SOLID RADWASTE SYSTEM PROCESS CONTROL PROCRAM (PCP)_ HW-800' 1.0 PURPOSE This program provides guidance and boundary conditions for preparation of specific procedures for processing, packaging and shipment of solid sampling, analysis, radwaLte in accordance with State and Federal Regulatory requicements. This program is applicable to the Limerick Generating 3.1 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. affect Establishing a set of process parameters that b. solidification and developing operational controls for those parameters. Implementing a Waste Classification System in c. accordance with 10CPR61 and applicable Regulatory

Guidance, d.

Providing an appropriate Quality control Program as required by 10CFR20.311. S Implementing procedures for processing, e. containerization and transport of waste to ensure I specific DOT, NRC, and burial site requirements are satisfied. i 2.0 RESPONSIBILITY The station operating organization is outlined in section NOTE: l 13.1 of the UFSAR. PORC is responsible for reviewing all revisions to the PCP. 2.1 The Plant Manager is responsible for approving all 2.2 revisions to the PCP. The Nuclear Quality Assurance Department performs audits to 2.3 ensure compliance with the Quality Assurance plan. l

RW-800, kev. 1 l Page 2 of 20 NJ11/DPM/KJ C/ r gs l ( PECo and PECo contract personnel are responsible for All 2.4 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. -_ -'"-^-

RW-800, Rev. 3 l l Page 3 of 20 l 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 has been submitted to the NRC for the Topical Report review shall be performed in accordance with review. The applicable RW procedures. Management review shall include review of plant-to-vendor equipment interface. a 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. The Process Control Program (RW-800) shall be implemented 4.3 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. Changes to the PCP (RW-800) shall be submitted to the ( 4.4 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. Changes to resin dewatering implementing procedures or the free standing 4.5 systems shall require verification that water content of the packaned product 's 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 Fage 4 of 20

• l-NJil/DPM/KJC/rgs

~<- I. i 1 When processing is not perfotmed in accordance with th 4,7 (RW-each-cor.tainer_ shall be reprocessed to conform to PCP i requirements and appropriate administrative action 800) recurrence. shall be take'n to prevent I APPkRATUS f $.0 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 are defined in Attachment 8.2. Processing of solid radioactive waste shall-be performed by properly trained and qualified operating personnel. NON-CONTAMINATED WASTE - Processed as ordinary 6.1.1 (non-radioactive) waste and is disposed of in. accordance with. applicable station procedures. CONDENSATE FILTER /DEMINERALIZER SLUDGE 6.1.2 Each-condensate filter /demineralizer 6.1.2.1 _ backwash consists of approximately 9,000 gallons of slurry with approximately 350 lbs. (dry wt.) spent resins and crud. Successive-backwashes are collected and 6.1.2.2 allowed to settle in a Condensate Phase Separator. As the sludge settles, clarified liquid is decanted. For centrifuge-dewatering of the settled 6.1.2.3 sludge, the phase separator _ is isolated when approxi.mately 240 cubic feet of-l K sludge has-secamulated.- For vendor dewatering of f the settled 6.1.2.4 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 hfS l Page 5 of 20 3, NJil/DPM/KJC/rgs 8 6.3.2.6 The phase separator contents are H 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,.

RW-800, Rev. 3 4 l Page 6 of 20 NJH/DPM/KJC/rgs l,, Each backwash from a radwaste 6,1.4.2 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 The solids slurry is fed to a centrifuge 6.1.4.5 for dewatering or to the External Processing Station for dewatering as appropriate, e.l.4.6 Waste Sludge Tank contents may also be to a condensate phase separator for sent processing in accordance with steps 6.1.2.2 through 6.1.2.7. REACTOR WATER CLEANUP P1LTER/DEMINERALIZER SLUDGE 6.1.5 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. Successive backwashes are collected and 6.1.5.2 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,, For centrifuge dewatering of the settled 6.1.5.3 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. Resjn sludges from different waste streams and different Note 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, Olly waste may be processed through 6.1.7.3 decontamination to levels which may be free released as non-contaminated material or non-contaminated waste. The contaminat9d byproducts of this decontamination process may be processed as DAW. p Olly waste may be shipped off-site for 6.1.7.4 processing by appropriate vendors on the PCCo evaluated vendors list. 6.1.8 IRRADIATED kEACTOR COMPONENTS 6.1.8.1 Irradiated reactor components are loaded into sampled, cut as necessary, liners in accordarice with applicable station procedures. 6.1.9 MISCCLLANCOUS PILTERS CRD Pilters are loaded into appropriate 6.1.9.1 containers and shipped for burial in accordance with applicable station procedures. 6.2 DEWATERING PROCCSS CONTROL 6.2.1 Centrifuge Rosin S)udge Dewatering The 0.5-61 solids slurries discussed in 6.2.1.1 Section 6.1 are fed to a centrifuge at a 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 or High Process 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 External' Processing Station. located 'n 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. 6.2.3 Approved Resin Sludge Dewatering Vendors c 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 Waste Classification - A computerized waste 6.3.1 RADRAN, is classification and shipping program, used to determine waste classification from the Manual isotopic analysis and scaling factors. methods may be used if the computer system is not available or not applicable. -Por DCWATURED RESIN, waste classification 6.3.1.1 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. ~ For OILY WASTE, waste classification 6.3.1.3 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 A detailed analysis is petformed annually 6.3.1.6 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 for each specific Values are available frc,m waste stream. shipment manifest forms. 6.4 WASTE STABILITY 6.4.1 M!nimum Stability Requirement Limerick Generating Station is 6.4.1.1 Waste at 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. the addition to the annual verification, 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 A determination by calculation, 2. test, or measurement is performed to is ensure that hydrogen generatien limited to a molar quantity that would be no more than 5% by volume of the secondary container gas void that is STP over a period of time at time. twice the expected shipment The cask cavity will be inerted., 3. utility Experience has demonstrated that 6.4.1.4 waste streams do not contain or generate or fumes and do not toxic gas, vapors, contain hazardous, biological, pathogenic, or infectious materials. Radioactive wastes shall have no 6.4.1.5 No dwtectable free standing liquids. 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 more than 0.5% of the for waste processed volume of the waste This is ensured in any other container. using appropriate station procedures. 6.4.2 Waste Stability Dewatered resin requiring stabilization 6.4.2.1 is packaged in High Integrity Containers (HIC) that have been certified to meet the stability requirements of The HICs are handled and 10CPR61.56(b). their stored in a manner such that ability to provide stabilization is not compromised. The chemical and physical properties of the resin in no way compromises the integrity of the Upon arrival at the burial container. Class B and C wastes are placed in

site, concrete overpacks for increased stability.

All reasonable efforts are made to 6.4.2.2 eliminate unnecessary void spaces within the waste packages. 6.4.3 Labelling Each package of waste shall be clearly 6.4.3.1 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 Each waste shipment shall te accompanied 6.4.4.1 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. 6.4.5 Quality Assurance Program The quality assurance program consists of 6.4.5.1 required use of plant procedures which the Process Control Program and implement requirements of the Corporate Quality Audits by personnel Assurance Program. independent of the Octivities are performed and reviewed by appropriate 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. Administrative controls for preventing 6.4.5.3 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. (RW-800) to incorporate vendor Revisions to the PCP 6.5.2 supplied process' systems shall be performed in the following manner: Prior to use of a vendor supplied system, 6.5.2.1 the Limerick Process Control Program (RW-800) shall be revised to address _the vendor's service requirements. For vendors who have submitted a Topical 6.5.2.2_ the PCP Report to the NRC for review, (RW-800) shall be revised to reference the submitted Topical Report. For vendors who have not submitted a 6.5.2.3 the Topical Report to the NPC for review, 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 required to assure solidification'of subsequent batches. See Ref. 7.18. 6.7 DOCUMENTATION Records of allfdata, tests, analysis results, and 6. 7.1_ 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. NJH/DPM/KJC/rgs l... ' 7.3 Standard Re' view Plan'11.4, Rev. 2, including Branch i 2. Technical Position ETSBil-3, Rev. Low level Waste Licensing Branch Technical Position on ~ 7.4 Radioactive Waste Classification. Low Level Waste Licensing Branch Technical Position on 7.5 ~ Waste Form. 7.6 South Carolina Department of Health and Environmental 097. Control Radioactive Material License No. Facility Site Disposal Criteria. 7.7 E.rnwell Waste Management State of-Washington Radioactive Materials License No. WN-7.8-1019-2. 7.9 Nuclear Pacific Inc. Topical Report for Dewatering System TP-02-P-A, Rev. l'. General Critera for High Integrity Containers (SCDHEC). 7.10 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) PCP Implementing Procedures are those listed above which Note: apply directly to processing, packaging, sampling, analyzing, and shipping radwaste. 7.12 Nuclear QA Plan Chem Nuclear Systems Inc Topical Report RDS-1000 7.13 Radioactive Waste Dewatering System RDS-25506-01-NP-A. Stock Equipment Co. Topical Report Oulck Dry Process For SRS-003-P, Rev. O. 7.14 Dewatering Bead Resin and Filter Sludge, Inc. Topical ReportSTD-R Westinghouse-Hittman Nuclear, Mobile Incontainer Dewatering and Solidification 7.15 011-A, System. (Implementation of Programatic Generic Letter 89-01 Controls for Radiological Effluent Technical Specifications 7.16 [ in the Administrative Controls Section of the Technical Specifications-and the-Relocation of Procedural Details of L o the RETS to the Offsite Dose Calculation Manual or Process Control Program), 1/31/89. Limerick Generating Station Unit _1 and 2 Technical 7.17 Specifications, 6.5.1.6, 6.8.1, 6.13. i i I

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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 train, component or device shall be -1. _ - OPERABLE -.A-System, operable.or have operability when it is capable of and when all performing its specified function (s), necessary attendantfinstrumentation, controls, electrical lubrication or other ' power,-cooling or seal water, auxilliary equipment that are required for the system, train, component, or device to-perform its subsystem, function (s) are also capable of performing their related support function (s). ' SLUDGE - Contaminated liquid which'may cc7tain water, oil, 2. and suspended solids, including ion exchange media and other filters. PROCESSING - Changing, modifying, and/or packaging.the 3. commercial nuclear power plant generated wet radioactive waste into a form that is acceptchie L a disposal facility. QUALITY ASSURANCE / QUALITY CONTROL -'As used in this 4.- document, " quality assurance" comprises all those planned and systematic actions necessary to provide adequate will. confidence that a structure,. system, or component Quality assurance perform satisfactorily in service. 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. SAMPLING PLAN - A sampling program' implemented to ensure 5. representative samples from the feed waste and-the -that 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) - Those low-level radioactive wastes containing source, special nuclear,1or -by-product material _ that are acceptable for disposal in a --land _disposalnfacility. -For the purposes of this definition, low-level radioactive waste has the same that is meaning as'in the Low-Level Waste Policy Act, classified as high-level radioactive radioactive waste not waste, transuranic _ waste, spent nuclear-fuel, or by-product materialias defined in section lle.(2)-of the Atomic Energy (uranium or thorium tailings and waste). Act

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 composition used_to.contain the final processed waste. WASTE FORM - Waste in a waste container acceptable for 8.- c disposal at a licensed disposal facility. j 9. WASTE TYPES NON-CONTAMINATED WASTE - Waste containing no detectable (A) 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 I exhaustion, fibrous filter media,-and small 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. CRD FILTERS - Control Rod Drive System filter' media t which has been contaminated by activated particles in-the reactor water which are deposited on_the filters.through control rod drive water flow. IMPLEMENTIN

G. PROCEDURE

S -_Those Limerick specific RW, 10. PCP and S_ procedures which apply directly to processing, ST, packaging, sampling,_ analyzing, and shippiig radwaste.. SOLIDIFICATION - Waste processed into.the form of a free of the 11. 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 high counts per minute.(2E10 cpm). With this existing situation, ODCM Control 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. ---_}}