ML20203E487
ML20203E487 | |
Person / Time | |
---|---|
Site: | Limerick ![]() |
Issue date: | 03/21/1986 |
From: | Grimsley D NRC OFFICE OF ADMINISTRATION (ADM) |
To: | Sugarman R SUGARMAN & ASSOCIATES |
References | |
FOIA-86-170 NUDOCS 8604240238 | |
Download: ML20203E487 (2) | |
Text
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+ UNITED STATES l 8 o NUCLEAR REGULATORY COMMISSION n y WASHWGTON, D. C. 20556
%,...../
Robert J. Sugarman, Esquire Sugarman & Hellegers 16th Floor, Center Plaza g g g,4 .
101 North Broad Street IN RESPONSE REFER l Philadelphia, PA 19107 TO F01A-86-170
Dear Mr. Sugarman:
This is in regard to your request, pursuant to the Freedom of Information Act, l to which the NRC assigned the above number, i This is a partial response to your request. We will notify you upon completion of search for and review of any additional records subject to your request.
X The staff has completed the search for and review of records subject to your request, and this is the final response to your request.
The NRC has no records subject to your request.
Records subject to your request are available for public inspection and copying at the NRC Public Document Room (PDR),
1717 H Street, NW, Washington, DC 20555, as noted on the enclosure (s). The PDR accession number is identified beside each record description.
X Records subject to your request are being made available for public inspection and copying at the NRC Public Document Room ,
(PDR), 1717 H Street, NW, Washington, DC 20555, in the PDR l file folder under the above number and your name. These records are listed on the enclosure (s).
We are enclosing a notice that provides information about ,
charges and procedures for obtaining records from the PDR.
Sincerely, WY Ay '
Donnie H. Grimsley, Director Division of Rules and Records Office of Administration Enclosure (s): As stated 8604240238 860321 PDR FOIA PDR SUGARMA86-170
- . _ . . . . . . _ ._ . . . . - . . . .... . .... . ._ s._,. .. . , .. ........m .. . _.
i Re: F01A-86-170 l J l
_AP_.nENDIX l
I ORIGINATOR RECIPIENT DESCRIPTION Philadelphia Electric NRC Semiannual Effluent Release Report Company No. 3 (July 1, 1985 - De~cember 31, 1985) - Limerick Generating Station, Unit No. 1, Docket No. 50-352.
(39 pages) .,
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~ ~ PHILADELPHIA ELECTRIC COMPANY 74 /e 2301 MARKET STREET %,
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P.O. BOX 3699 PH,lLADELPHIA. PA.19108 e las si e43-4ooo February 20, 1986 Docke t Nq. 50-3 52 Dr. Thomas E. Muricy, . Administrator U.S. Nuclear Regulatory commission Region I 631 Park Avenuo King of Prussia, PA 19406 SUBJECT : Semi-Annual Ef fluent Releases Report No. 3 July 1,198 5. through December 31, 1985 Limerick Generating Station Unit 1 s
Dear Dr. Murleys ,
Enclosed are i two copica of the S emi-Annual E f fluent Releases Rep 3r t N6. 3 for the pc riod July 1, 1985 through December 31, 1905 and one copy of the 1985 Tower No.1 Joint Frequency Distributions of Wind Direction & ' Speed. 'oy tmospheric
. Stability Class Report No.1 for Limerick Generating Ltation
- Unit 1.
This report la being submitted in compliance with 'the Technical Specificatrion 6.9.1.6 of Operating Liconne NPP-39 and Regulatory Guide 1.21' to fulfill the requirements of Regulatory Guide 10,.l.
Very truly yours, .
W. M .Alden Enginee r-In-Chargo.
Licensing Section Nuclear Services i Enclosures Attachme nts .
~
ces Document Control Desk, USNRC E. M. Kelly, Senior Site Inspector See Attached Service List (w/o Encionures) 2/ b Y7 1 f A lAf
(% Q) LV./ N y 1- U LO ON^
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cc: Troy B. Conner, Jr. , Esq. (w/o enclosure)
Ann P. Ilodgdon .Esq. (w/o enclosure).
Mr. Frank R. Romano (w/o enclosure).
Mr. Robert L. Anthony (w/o enclosure)
(w/o enclosurc)i ,
Ms. Phyllis Zitzer Charles W. Elliott, Esq. (w/o enclosure)
Barry M. Hartman, Esq. (w/o enclosure)
Mr. Thomas Gerusky (w/o enclosure)
Director, iPenna. Emergency (w/o enclosure).
Management Agency Angus Love, Esq. (w/o enclosure)
David Wersan, Esq. (w/o enclosure)
' Robert J. Sugarman, Esq. (w/o enclosure)
Kathryn S. Lewis, Esq. (w/o enclosure)
Spence W. Perry, Esq. (w/o enclosure)~
Jay M. Gutierrez, Esq. (w/o enclosure)'
Atomic Safety 6 Licensing Appeal Board (w/o enclosure)
Atomic Safet.y 4 Licensing Board Panel , (w/o enclosure)
Docket 6 Service S-sction (w/o. enclosure)-
E. M. Kelly (w/o enclosure)-
Timothy R. S. Cupbell (w/o enclosure) 8
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LIMERICK GENERATING STATION
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UNIT NO. 1 DOCKET No. 50-352 SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 3 JULY 1, 1985 THROUGH DECEMBER 31, 1985 Submitted to The United States Nuclear Regulatory Comission Pursuant to 1 I Eacility Operating License NPF-39 1
l Preparation Directed By:
o .. m te. m.a er l Limerick Generating Station f l '
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i PHILADELPHIA ELECTRIC CCMPANY LIMERICK GENERATING STATION l UNIT NO. 1 j
.a DOCKET NO. 50-352 ,
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SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 3 JULY 1, 1985 THROUGH DECEMBER 31, 1985 s
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i Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating License NPF-39 Preparation Directed By:
G. M. Leitch, Manager i Limerick Generating Station l
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TABLE Ol' CONTENTS 1
t I. Introouction II. Tables A. Summary of Radioactive Liquid and Gaseous Ef fluents
- 1. Liquid Efiluents
- 2. Gaseous Effluents ,
1 B. Solid Waste Disposition Report C. Meterological Measurements - Joint Frequency Tables D. Onsite and Of fsite Radiation Dose Assessment 111. Attachn.cnts i I, A. Suppleme ntal Inforn.ation Assumptions Used in Dose Assessments 1 B. Changes to the Of fsite Dose Calculation Manual (ODCM)
/ and Suppor t Docunentation P
I I
I
- u. ' *O - -_---_--___-___----__-___-______--____---______---___-_---_______-----L
, I. INTRODUCTION
[ This submittal complies with the format described in Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants", Revision 1, June, 1974, with
! data summarized en a quarterly basi ~s following the format of Appendix B thereof.
In accordance with LGS Technical Specification 6.9.1.8, this document summarizes the gaseous and liquid ef fluent releases for the period of July 1, 1985 through December 31, l 1985 and the resultant radiation doses from the liquid pathway to members of the public for the period of January
)
1, 1985 through December 31, 1985. There were no measurable releases of radioactive gaseous effluents during the report period and therefore no offsite doses to members of the public from this pathway nor to members of the public due to their activities on site. Where "O.00E+00" is used, it denotes the less than detectable level for the given isotope. These values are available upon request.
1
/ Disposition of solid waste during the report period is described within, to include: the total activity shipped by waste type and an estimate of the error in the reported totals the estimated composition of each type of waste by isotope; and the solid waste disposition, i.e. number of shipments, mode of transportation, destination, type of
, container, total container volume, and solidification agent.
p A summary report of the meteorological measurements taken during each calendar quarter within the 6-month reporting period is submitted as joint frequency distributions of wind direction and wind speed by atmospheric stability class.
The affected pages and justification for Revision 3 of the Offsite Dese calculation Manual (ODCM) is included.
]
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I II. TABLES A. SUMMAtlY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENTS 1
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4pitTs Ut USEpe penpf - TABLE II.A SATE: 3/37/36 11:39 Page 1 of 2 EFFLtENT'AND UASTE St$POSAL REPORT LIS819 UFLUENTS - SINWIATION W ALL RELEASES i
jr LNtITS : SUARTER SUARTER *EST. TOTAtt
}'
t a 3 8 4 : ERROR. si a
- . A**** CURIE LIMITS NOT O. FIS$1000 AND ACTIUATION PReDUCTS APPLICABLE. SEE
___ II. TABLE - D t 1. ':,TAL RELEASE (EXCL.: CI 4.2e5E-93 8.212E-et e.tseE+02 :
TRIT.. GASES. ALPNA): : : : :
t E. AUCRACE DILUTED sUCI/HL 4.3S X-47 e.149E-08 s CONC. DURING PERIOD t 8
- t 3. PERCENT F 2 8 0.eetE+0e 8 9.oe#E+es a mPPLICABLE LIMIT : : ******
- 3. TRIT!UN t 1. TOTAL RELEASE : CI 9 13GEeet t 4.92SE+0e e.133E+02 s 3. AUERAGE SILUTES UCI/NL 0.2SSE-64 0.64sE-07 8 CeNC. SURING PERIOD : :
- 3. PEDCENT W 8 % 8 0.000E+et e.000E+ee t a APs ICABLE LIMIT : :*****
C. DIS $9 LUES AMS ENTIIAIIIES SASE$ --
. ~ . . . _ . - . .
I 1. TOTAL RELEA$t i CI 8 4.995E-04 8 0 _. 182E-et t 0.200E+0E :
I 3. AUERAGE SILUTtt 'tutt/NL s 0.33sE-47 0 11X.09 :
B CONC. SURItet PERIOS : : a '
s 3. PERCENT W e t e.000E+00 9.eeeE+0e APPLICAtts tint? : a*****
a
- 9. ORess ALPHR RADIcecTIUtTY '
I 1. TOTAL REttASE t CI e 0.000E+00 4358C-eta 4.14TE+etI to UOLINE WASTE REttests sLITERS e 0.519E+07 4.958E+10s0100E+e85 s (PRIOR TO 91LUT10N) a : :
F. ..
I SILUT! ale UATER SUR11e8 PERIOS e sLITER$ s e 4.538t+47 s 0.14X+11 e e.teeE+et : .
e e
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. $1TE LINERICE TABLE II.A UNIT: U1 page 2 of 2 '
USER: n::RT DATE: 2/10/88 15:21 EFFLUENT AND UASTE DISPOSAL REPORT CASECUS EFFLUENTS - SUMMAT!0M 0F ALL RELEASES
$ e UNITS : OUARTER
( 00ARTER *EST. TOTAL:
- : 3 : 4 : ERROR. ta g A. FIS$10N AND ACTIUATION CASES
- , a 1. TOTAL RELEASE
- CI : 8.teeE+ee.: 8.6e6E ee : 0.0 hee +98:
- 2. AVERACE RELEASE UCI/SEC: 0.990E+98 : 0.000E+08 :
RATE FOR PERIOD : : :
- 3. PERCENT OF TECHNICAL R 9.000E+99 : 8.8eeE+86 :
SPECIFICATION LIMIT : : :
- 3. 10 DINES
- 1. TOTAL 10 DINE-131 : CI : 0.000E+90 9.seeE se : 8.ee9E+09 :
- 2. AVERACE RELEASE UCI/SEC: 8.900E+0e : 0.seeE*00 :
RATE FOR PERIOD : : :
- 3. PERCENT Or TECHNICAL: R : 9.000E+69 : 0.000E+00 :
a SPECIFICATION LIMIT : : : :
C. PARTICULATES
- 1. PARTICULATES WITH : CI 0.000E+ee : e.gpeE+gg : 0.pect+99 :
- HALF-LIVES 13 Days : : : :
- 2. AVERACE RELEASE UCI/SEC 9.000E+et : e.eeeE+ee :
- RATE FOR PERIOD : : :
- 3. PERCENT OF TECHNICAL: R 0.999E+00 e.eeeE+es :
3 SPECIFICATION L!n!T : : : :
- 4. GROSS ALPHA : CI 9.eGeE+00 3.teet+se : -
RADIDACTIVITY : : , 3 D. TRITIUM
- 1. TOTAL RELEASE : CI : 4.eeeE+ee e.ee#E+#8 9.000C+09 :
- a 2. AUERACE RELEnet :UCI/SEC: 0.ettt+09 e.eest,ge RATE FOR PERIOD : *
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- 3. PERCENT OF TECHNICAL:
- R : 0.000Este e.gggg,gg g .
SPECIFICATION LIMIT : : : . .
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PAGE S OF 9 SITE 8 L1MERICit - 1 UNITS U1 USERS f1 ART i DATE: t/10/88 15:49 EFFLUENT AND UASTE DISPOSAL REPORT TABLE A.2 CASE 005 EFFLUENTS FOR RELEASE POINTI E Unit 1 - South Stack CONTINUOUS MODE BATCH MODE ' \ a NUCLIDES UNITS : OUARTER 00ARTER CUARTER t OUARTER
- i t 3 4
- 3
- 4 ,
i t RELEASED t ! 3. PARTICULATES (CONTD) i ! : 3A140 : CI 0.000E+ee : 0.000E+04 0.000E+00 t 0.900E+6e ' 2
- CE141 8 CI : 6.990E+09 0.000E+0e : 0.000E409 8 9.000E+04 : >
....E+= ...aE+= , ...aE+= i ..a.E+= , ,
- i cE1u i er s t UNIDENT.
- CI 0.000E+09 0.999E+00 t 9.000E444 8 0.000E+44 :
l i : TOTAL FOR s t - I
- PERIOD t CI
- 9.990E+00 t 4.000E494 8 9.000E+M : 9.teeE+49 : i (A300E) : : :
^
. ENTER E C 3 TO ERASE SCREEN AND CONTINUE . i , i.
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l TABLE A.2 i PACE 9 0F 9
$1TEt LIMERICK UNITS U1 USERt NART DATES 2/10/88 15:30 ;
f EFFLUENT AND UASTC DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 4 Hot Maintenance Shop h CONTINUOUS MODE DATCH NODE MUCL! DES t UNITS 8 OUARTER
- GUARTER QUARTER
- 00*RTER ;
, t RELEASED I 3 8 4 3 8 4 .
- 3. PARTICULATES (CONTD) 3A140 CI
- 9.90eE+09 8 0.00eE+0e 4.000E+09
- 8.000E+6e *
- CE141 : CI I 0.000E+ee : 0.eeeE+ee e.eeeE+ee e.eeeE+ee t CE144 CI 0.999E+90 t 9.08eE*e0 8 0.90eE+09 8 4.90eE+60 t
- j. I UNIDENT.
- CI 8.000E+00 8 0.990E+0e e.900E+09 I 0.000E+00
> ~
t TOTAL FOR *
- 8 I I t
** PERIOD CI 0.000E+99 9.900E+99 0.000E+99 0.000E+09 8 8 (490VE) : :
- ENTER E C 3 70 ERASE SCREEN AND CONTINUE
- i -
i t 9 i 1 a I 1 1 } I l-1- 9 1
i l l r i
, I II. TABLES I
B. SOLID WASTE DISPOSITION REPORT Y \ l t 1
\
4
'l l
P l l l s 4 %*a . .k d1 9 A
. w w am w w seses u % . -
W. s.-- h ' I w TABLE II.B , Page 1 of '2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/85 TO 12/31/85 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) l 1. TYPE OF WASTE I UNIT I 6-month I Est. Total i I I l Period i Error, % i
-:_ __ _g _____g___ _g I a. Spent resins, filter sludges, I m3*.I 3.06E+2 I I I evaporator bottoms, etc. I Ci ! 2.06E+1 1 2.80E+1 I g_________ _ ____________________g______g_________g____________g 'l b. Dry compressible waste, I m3 I O.OOE+O I l I contaminated equipment, etc. I Ci i O.OOE+0 t O.OOE+0 I g ____ __ __ ____ __ __ _ _____ ___g ____ :______ __g___ _ _ g I c.* Irradiated components, I m3 I O.OOE+0 I I I control rods, etc. I Ci 1 0.OOE+0 I O.OOE+0 I g_____________________________________g______g_________g____________
I d. Other (describe) I m3 I I I i I ! Ci I i i l____ ______________________________I______I_________l____________I i
- Volume in cubic meters is~ total container volume. shipped.
'tbtal curie content and principal radionuclides were determined by -
gamna isotopic analysis of each batch of resin. Non-ganma snitting isotopes were Fuw.inined by using factors scaled to principal ganma enitters in accordance with "AIF/NESP Metixxiologies for Classification of Im-Ievel Radioactive Wastes Frun Nuclear Power Plants",,Noverober, - -
- . 1983.
e d
- - -- - - w w w " " - - '
W LE TI B
- 2. Ectimato of m2,3cr nuclido esmposition (by typa of wanto) - -
l TYPE A I TYPE B i TYPE C I TYPE D l- __3_ - _l_____ __ ___g_. ___ _______ l- ___________ ____ ,_ I isotope i Act.tvity l Per Cent i Activity l Per Cent i Activity i Per Cent i Activity i Per Cent 1 - 1 I (C1) I I (Ci) i I (Ci) I I (Ci) 1 I f l--------l--------l--------l---------l-------l---------l--------l---------l----------I H3 l-I 'l i I I I I I I I C14 l' ' I I I I I I I I I CR51 1 -6.08E+0 1 2.95E+1 1 I I I I I I I MN54 1 1.15E-1 1 5.59E-1 1 I I I I I I I FE55 1 1.32E+0 I 6.40E+0 I I I I I i I I C058 1 4.87E+0 1 2.36E+1 I I I I I i I
; I FE59 1 1.62E-1 1 7.88E 1 I I I I I I I j l NI59 8 2.89E-6 1 1. 40'_-5 l I I I I I I I CD60 1 5.57E-1 1 2.70E+0 I I I I I I I
, 8 NI63 1 1.17E-5 I 5.65E-5 I .I I I I I I l ZN65 1 7.42E+0 1 3.60E+1 I I I I I I I i 1 NB94 I I
- I . I I 'l I i !
i SR90 I I I I I I I I I NB95 1 1 7.96E-4 I 3.86E-3 I ~
. I I I I I I I 2R95 1 2.16E-2 I 1.05E-1 1 l I I I I I I TC99 1 -
I' I I I I I I I I RU103 I I I l' I I I I I I RU106 .I I I I I I I I I I I129 I i 1 . I I I I I I
. I 1131 1 4.78E-3 1 2.32E-2 I I I I I I i 1 CS134 I I I I -
1 1 . I I I I CS135 I I . I I I I , I I I
~
I CS136 I I I l i I I I I I CS137 I I I I I I I I I I 2A140 1 1.46E-2 1 7.08E-2 I I I I I I I I CE141 1 3.68E-4 1 1.78E-3 I I I I I I I
! CE144 I I - l' I I I I I I I PU239 I I I '
I I I I I I l I pu241 1 I i I I I I I I t i AM241 I I . I I I I I I I
. i ! AM243 I I I I I i 1 I I I CM242 I I I I I I I I I 4 I CM243 I I I I I I -
I I I 4 3- __-I l - __ l - -l ______3 3 - 3- ___ l _ ___ __I t 4.g g,.,3.. Solid Waste Disposition.,s...
, , , , c. - . , ,,. r. '-., ..o, . * * . .4 i ,
Total !
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Number of Shipments Mode of Transportation Destination Type of cont.ainer volume , Agent
7 d II. TABLES l C. METEOROLOGICAL MEASUREMENTS - JOINT FREQUENCY TABLES A h 4 4 1
'I <t i
I 1 1 k h f' 'b'" * . /- l --. , s. ,w : ._ a)
TABLE II.C l Page 1 of 1 l t . C. Meteorological Measurements - Joint Frequency Tables l l 3 The joint frequency distributions of wind direction and speed, by atmospheric stability class are enclosed as a separate report. The distributions include all three wind levels from Limerick Meteorological Tower No. 1. The distributions were developed dh the Radiation and j Meteorological Monitoring System - RM21A. Each of these
" wind roses" consist of eight pages of joint f requ'ency distributions. There is one distribution for each of the seven P-G stability classes, A through G, and a combined . "All Classes" page. The P-G stability classes are determined by the temperature differences measured over the 266-26 feet and the 171-26 feet height intervals. All meteorological data were finalized on the RM21A system.
Two NRC format meteorological data tapes covering the . periods January,1985 through June, 1985 and July, 1985 through December, 1985 are currently retained by the Limerick' Generating Station Meteorological consultant. e
)
1 I I L
. . sw + , . .e
- a t
II. TABLES D. ONSITE AND OFFSITE RADIATION DOSE ASSESSMENT 1
)
9 Ad
'e .
1 e I f I
^
l l b * :=-- , , . . . . . . . .
)
- TABLE II.D Page 1 of 1 M SITES LIMERICK ~
umITs U1 USER: MART O DATES 2/14/84 17327
$UMMART OF MAXIMUM INDIVIOUAL 00$ES TOTAL ACCUMULATION FOR PERIDOS:
O LICUIO: FROM 1/ 1/85 0:30 10 12/31/85 23800 GASEOUS: FEDM 1/ 1/85 0:00 TO 12/31/85 23 00 h EFFLUENT APPLI CA BL E ORGAk ESTIMATED 00SE AGE GROUP LOC ATIO N DIST DIR OF LIMIT (MREM) APPLICABLE-(MR) (M) (TOWARD) LIMIT iO LIQUID TOTAL 800Y 5.12E-03 CHILO RECEPTOR 1 1.TE-01 .3.0 g LIQUID LIVER 1.05E-02 AOULT RECEPTOR 1 1.4E-01 10.0 n ~~~~~~~~" " " " " " " " " " " " " " " " " " " " " " "'"'" " " NOBLE GAS AIR DOSE 0.00E+00 805. N 0.0E+00 .10.0 (GAMMA-MRAD) N08LE GAS AIR DOSE 0.00E+00 805. N 0.0E+00 20.0 y) (8 ET A- MR AD) NOSLE GAS T.80DY (GAMMA) [i 3 0.00E+00 ALL 0. 0.0E+00 5.0 NOBLE GAS SKIN (8 ETA) - 0.00E+00 ALL 0. 0.0E+00 15.0
)),
IODINE + T.800Y 0.00E+00 ACULT 884. N 0 0E+00 15.0 PARTICULATES
- d. -
SUMMARY
OF POPULATION COSES TOTAL ACCUMULATION FOR PERIDOS:
~y LICUID: FROM 12/31/84 23:00 TO 12/31/85 23:00 G AS ED.US : FROM 1/ 1/85 0:00 TO 12/31/85 23:00
____------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ . . ==_ EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION 00$E (PERSON-REM) _ _ _ - - _ _ = =
- LIQUID TOTAL 800Y 9.9 E-02 V LIQUID THYROIO 5.TE-02 GASEOUS TOTAL 800Y 0.0E+08 GASEQUS THTROIO 0.0E+08 v -
t V V
****There were no releases of radioactive gaseous effluents during the above V period and consequently no doses to members of the public due to their activities inside the site boundary. Also, there were no doses to "
members of the public due to their activitie; inside the site boundary re-sulting from radioactive liquid releases. O
!Q ~ : : e -. - .:: - = =e. . - - .?~ = ->
d 4 1 III. ATTACHMENTS A. SUPPLEMENTAL INFORMATION-ASSUMPTIONS USED IN DOSE ASSESSMENT e s f 5 I f a o
. . h4 W - 4 ' *#
III. ATTACHMENTS a A. SUPPLEMENTAL INFORMATION Facility: Limerick Generating Station - Unit 1 q License: NPF-27
- 1. Regulatory Limits (Technical Specification Limits)
A. Noble Gases: 15 500 mRems/Yr - total body " instantaneous" limits per j $ 3000 mRems/yr - skin Tech Spec 3.11.2.1 1 2 5 5 mRads - air gamma - quarterly air dose limits per g 10 mRads - air beta Tech Spe,c. 3.11.2.2 35 10 mRads - air gamma - yearly air dose limits per g 20 mRads - air beta Tech Spec. 3.11.2.2 B. Iodines, tritium, particulates with half life > 8 days:
- 1. $ 1500 mRems/yr - any organ " instantaneous" limits per (inhalation path) ~~ Tech spec. 3.11.2.1 2 5 7.5 mRems - any organ - quarterly dose limits per Tech. Spec. 3.11.2.3 3 5 15 mRems - any organ - yearly dose limits per Tech. Spec. 3.11.2.3 .
C. Liquid Effluents: l J
- 1. Concentration < 10CFR20 " instantaneous" limits per Appendix B, Table II, Col. 2 Tech. Spec. 3.11.1.1
- 2. $ 1.5 mRems - total body - quarterly dose limits per i < 5 mRems - any organ Tech. Spec. 3.11.1.2 3 5 3 mRems - total body - yearly dose limits per ~
1 $ 10 mRems - any organ Tech. Spec. 3.11.1.2
- 2. Maximum Permissible Concentrations i
MPCs are not used to calculate permissible release rates and concentrations for gaseous releases. a The MPCs specified in 10CFR20, Appendix B, Table II, Column 2 for identified nuclides are csed to calculate permissible release rates and concentrations for liquid releases per LGS Technical Specification 3.11.1.1. I I l
5 3., Avarsga Energy E determination based on liquid re. lease for the report period is 0.0189 Mev.
- 4. Measurements and Approximations of Total Radioactivity A. Fission and Activation Gases The method used is the Canberra Series 90 Counting System; GS - Gas Marinelli B. Iodine:
The method used is the Canberra Series 90 Counting System; CH - Charcoal Cartridge C. Particulate: The method used is the Canberra Series 90 Counting System; PT - Air Particulate Sample, 47 mm filter. D. Liquid Effluents: The method used is the Canberra Series 90. counting System
~
and the Radwaste Liquid Discharge Pre-Release Method with a 3.5 Marinelli.
- 5. Batch Releases A. Liquid 03 Q4 9 of Batch Releases: 78 95 Total Time for batch releases, minutes 5752 .6819 Maximum time period for a batch release, minutes 120 94 Average time period for batch release, min'ates 74 72 s
Minimum time period for a batch release, minutes 56 45 Average stream flow (blowfown) during periods of release of c effluents into a flowing stream, gpm 5646 5846 B. Gaseous None
- 6. Abnormal Releases A'. Liquid 1 None B. Gaseous None i
4 7 Description of Gaseous Release Points Release Point 1 = North Stack i Release Point 2 = Unit 1 - South Stack Release Point 4 = Hot Maintenance Shop
- 8. Description of Liquid Release Points Release Point' l - Liquid Radwaste Discharge to 'Schuylkill River
- 9. Liquid Dose Receptor Description 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 s
I b
~
III. ATTACHMENTS B. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL AND SUPPORT DOCUMENTATION 4 I 9 I G h
- e d
l q : .
%Inverb- e m - . d.W8mr b.
e . sw, d4 e .. ,
,,g4 s _ p s., .g.
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III. Changes to the Offsite Dose Calculation Manual and Support Documentation Revision 3 to the Offsite Dose Calculation Manual (ODCM) is submitted for the period in which the change became effective. The attached document cover sheet indicates review and approval of the change by Engineer-in--Charge, Nuclear and Environmental section of Mechanical Engineering Division and PORC approval by Limerick Station Superintendent. The following statements have been evaluated and determined to apply to the change: A. Justification.for the change is the replacement of Dairy Farm SCl of the Limerick Generating Station's Radiological Environmental Monitoring Program (REMP). Dairy Farm SCl has gone out of business. Dairy Farm 17C2 has replaced Farm SC1 as part of the REMP. B. This change will not reduce the accuracy or reliability of
. dose calculations or setpoint determinations. The affected table (Page 18 of the ODCM) and map (Page 20 of the ODCM) are included. *To a
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.9P-1001, Rev. 1 ~
Page 4 of 4 MAC/nlp ATTACT4ENT 8.1 OFF9ITE DOSE CALCULATION MANUAL 9evision 3 LIMERICK GENERATING STATION UNITS 1 AND 2 d
.d PHILADELPHIA ELECT.RIC COM?ANY t
Docket Nos. 50-352 & 50-353 I PORC Approval:
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CF _ ~ j Stati&6 Superintendent ' n Nuclear and Environmental ' Section Approval: _ j' E. I.f7 (' LcS Health Physics Representative /
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'i . 1 * * . ENVIRONMENTAL SAMPLING STATIONS , INTEAMEDIATE - .-DISTANCE . \!
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l 4. Wirm 6 20CRT1065 - - p - Milk (d) . 1) Control Station , 22F1 (d) Milk samplas are taken from .
/ 2) 17C2 several farms surrounding ICS.
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_ _25B1. ... . highest dose. potential. from wh!.* . .. as well as a centrol station.
* . The locations of the. farms are not listed herein due to a long-standing agreement with ,the farmers involved.' In returni '.i/ ~ . . . . ... . . __ . .. .. for. being . allowed .to sample,,mw!~.. '.a.. ., j analyse the milk,. PEm has agreed;, . . not to divulge the location of s y the farms. p,.}gfg.;t d' . .. . ,, s . :.: 1.</r: p. - " Fish -(e)' % -' > D Middis of
- vincent Pool. - : - 16cb , sss'- - 1.9 - (e) .1tso species of recretionallytim-y-Upstream to Pigeon Creek. porant fish, sunfish and brownm;,,.9 ' . .
, bullhead will be sampled if -
available. I
- 2) costream of ras, Keim Street 29C1 Mr ,3. 2 Bridge to Hanover Street Bridge (control) -
Pbod Products 1) 109 Information Center 1131 ,. ESE ' 0.5 (f) Food products are to'be samples (f) as part of the ISS Tec2nical
. Specification Program only if milk 1he.sampling is not p*erformed.
milk pathusy, Wr results
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humans than the vegetation path-way is monitored at a Icontien near the site, ard is a better
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sa gles. In addi , no crops
; groun in the vicinity of 105 . are irrigated with water in N- which 11guld plant wastes have been discharged.
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