Text

Semiannual Effluent Release Rept 3,Jul-Dec 1985
	ML20140C143
Person / Time
Site:	Limerick
Issue date:	12/31/1985
From:	Leitch G; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20140C135	List: ML20140C129; ML20140C143; ML20140C159;
References
	NUDOCS 8603250190
	Download: ML20140C143 (41)
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"

A N 5

PHILADELPHIA. ELECTRIC COMPANY PHILADELPHI A LIMERICK GENERATING STATION 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 Cotamission Pursuant to Eacility Operating License NPF-39 Preparation Directed By:

G. M. Leitch Manager Limerick Generating Station 8603250190 860228 PDR ADOCK 05000352 R

PDR r.

~

l-(

. -l___--_______________

1 LIMERICK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-352 l

SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 3 j

JULY 1, 1985 THROUGH DECEMBER 31, 1985 Submitted to

{

The United States Nuclear Regulatory Commission Pursuant to Eacility Operating License NPF-39 1

Preparation Directed By:

G.- M. Leitch, Manager Limerick Generating Station

PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION 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 Commission l

Pursuant to Facility Operating License NPF-39 Preparation Directed By:

G. M. Leitch, Managar Limerick Generating Station l

l l

i I

TLbLE Ol' CO;.TEt;TS I.

Introcuction II.

Tables l

A.

Summary of Radicactive Liquid and Gascous Ef fluents l

1.

Liquid Ef11 tents l

2.

Gaseous Effluents B.

Solid Waste Disposition Report C.

Meterological Measurements - Joint Frequency Tables D.

Onsite and Of fsite Radiation Dose Assessment 111. Attac hn e nt s A.

Supplemental Inforn.ation Assumptions Used in Dose Assessments B.

Changes to the Of fsite Dose Calculation Manual (ODCM )

and Suppor t Docucentation 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 on a quarterly basis following the format of Appendix B thereof.

In accordance with LGS Technical Specification 6.9.1.8, this document summarizes the gaseous and liquid effluent releases for the period of July 1, 1985 through December 31, 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.

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 isotopc; and the solid waste disposition, i.e. number of shipment s, mode of transportation, destination, type of container, total container volume, and solidification agent.

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 l

atmospheric stability class.

The affected pages and justification for Revision 3 of the Offsite Dose Calculation Manual (ODCM) is included.

II.

TABLES A.

SUMMARY

OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENTS

\\-

N

x:

4Nf17 Ug TABLE II.A USEPs Mmpf Page 1 of 2 DATE: 2/17/96 11:19D EFFLUENT AND UA5TE DISPOSAL REPORT LISUID EFFLUENTS - SUNRATION OF ALL RELEASES s UNITS t 90AftTER : 40AftTER

EST.

TOTAlt t

3 4

ERROR. R

- - - - CURIE LIMITS NOT APPLICABLE. SEE A. FISSION AND ACTIUATION PRODUCTS II. TABLE - D

1. TOTAL RELEASE (EXCL.*

CI s 0.295E-93 9.212E-41 : 9.190E+02 :

TRIT., CASES. ALPHA)a e

a t 2. AUERACE DILUTED sUCI/NL 8 9.383E-97 8 9.149E-98 CONC. DURINC PERIOD s s

t 3. PERCENT OF 2

9.999E+99 0.999E+99 :

APPLICABLE LIMIT

=***

3. TRITIUM

1. TOTAL PELEASE

CI 9.136E*00 t 9.926E+99 9.133E+02

2. AVERAGE DILUTED SUCI/ML 9.2SSE-94 9.64BE-97 :

I CONC. DURING PERIOD t t

a s 3. PERCENT OF 8

R 0.999E+99 0.999E+99 3

APPLICABLE LIMIT a*****

C. DISSOLVED AND ENTRAINED CASE 5 t 1. TOTAL RELEASE I CI

0.995E-94 t 9.162E-92 s 0.200E+02 t 8. AUERAGE DILUTED IUCt/NL 3 9.!BSE-97 7 0.113L-09 :

a CONC. DURING PERIOD a

3. PERCENT OF R

e 0.999E+99 9.000E+ 99 8

APPLICABLE LIMIT I

e a

~.

D. OROSS ALPHA RADI0 ACTIVITY I 1. TOTAL RELEASE e CI 9.000E+99 4.650E-98 9.147E+91 8 E. UOLUME WASTE RELEASED tLITERS e 0.519E+97 8 9.959E*19 9.190E+985 s

(PRIOR TO DILUTION) e e

s a

F. UOLUME DILUTION MATER BLITERS I 9.53SE+97 : 9.143E+11 9.199E+93 :

USE3 DURING PERIOD 8

8 e

s M

M - MiI bu

TAELE EE*A 911(s LIREDICE UNITI U1 Page 2 of 2 USER MART DATE: 2/10/96 15:27 EFFLUENT AND WASTE DISPOSAL REPORT CASE 005 EFFLUENTS - SUMMATION OF - ALL RELEASES t UNITS : 00ARTER : 00ARTER sEST. 70TAtt a

3 8

4

ERROR. R A. FISSION AND ACT!UATION CASES I 1. TOTAL RELEASE CI 9.ee9E+99 8 9.900E+99 8 9.99eE+99 :

t 2. AUERACL RELEASE

-tuCI/SEC 9.999E+99 8 9.90eE+99 :

. RATE FOR PERIOD

3. PERCENT OF TECHNICAtt R

0.999E+99 9.9eeE+99 :

SPECIFICATION LIMIT s t

t t

3. 10 DINES t 1. TOTAL 20 DINE-131

CI 9.999E+99 8 9.000E+99 8 9.999E*99 8 8 2. AVERACE RELEASE

UCI/SEC 9.999E+9e 9.90eE+99 8

RATE FOR PERIOD

3. PERCENT OF TECHNICAL:

R

9.90eE+99 : 9.999E+99 :

SPECIFICATION LInIT

C. ' ARTICULATES I 1. PARTICULATES WITM t CI 9.999E+99 8 9.999E+99 9.000E+99 HALF-LIUES 19 DAYS 8 2. AVERACE RELEASE SUCI/ SECT 9.999E+99 0.999E+49

RATE FOR PERIOD 1 3. PER0ENT OF TECHNICAL:

R t 9.999E+99 9.000E+99 8 SPECIFICATION LIMIT :

a e

4. CROSS ALPHA s C!

t 0.999E+99 0.09eE+99 :

s RADIDACTIVITY t

D. TRITIUM

1. TOTAL RELEASE CI

0.994E+99 8 9.999E+99 e 9.DeeE+99 :

2. AUER4cE RELEASE UCI/ SECS 0.999E+99 8 9.999E+99 8

RATE FOR PERIOD t

t*

t a

s 3. PERCENT OF TECHNICALt R

t 9.999E+99 0.999E+99 :

SPECIFICATION LIMIT :

II.

TABLES A.l.

LIQUID EFFLUENTS 1

l

llill

+

1 A

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8 8

s _

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a s

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+

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+

4 E

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r T

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0 1

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9

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J V.USERI. MART TABLE A.1 r

I: t/17/36 Sts29 b AND unSTE DISPOSAL REPORT b,%.;%y,.i-

'yLIGUID EFFLUENTS FOR MLEASE POINT: 1 Liauid Fad Waste Discharge to Schuylkill River

Wt '. '

CONTINUOUS H0K DATCH MODE ~

p '.y, 6'; -

e UNITS : GUAltTER GUAltTER : OUARTER 00AltTER

,- [" i MUCL19Es

....I;. RELEASED 3

a 4

3 4

l J '

q

;Jituto ErrtuEnts (Confot

.p

CI

0.000E+49 0.999E+99 0.000E+00 s 0.000E+00 8; CS134

- '*t r.' s CS136

CI 0.000E+49 : 9.000E+99 9.000E+00 s 0.000E+09 0.

E.

s..

E.

s... E.s.

...;;E.

s

~

. C$ii7 ei

.t CS138

CI s 9.000E+96 4.000E+00 8 0.940E+00 s 0.000E+00 I 94130

CI

4.000E+ee : 0.990E+00 s 0.990E+98 0.000E+00 s E

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II.

TABLES B.

SOLID WASTE DISPOSITION REPORT l

5 1

i l

1

(

l l

I 1

Page 1 of 2 l

f SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/85 TO 12/31/05 A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1 I

I Period i Error, %

I

-l g_____g______ _ 3 g

I a.. Spent resins, filter sludges, I m3* I 3.OSE+2 I I

I evaporator bottoms, etc.

I Ci I 2.06E+1 1 2.80E+1 1

___ ___ g g..

___g I

b.

Dry compressible waste, I

m3 i O.OOE+O I I

I contaminated equipment, etc.

I Ci I 0,00E+O I O.OOE+O I

_g

_ g g____

g.

I c.

Irradiated components, I

m3 I O.OOE+O I I

I control rods, etc.

I Ci i O.OOE+O !

O.OOE+O I

_g

_g g.

_ __ _ _ g,

g d.

Other (describe)

I m3 I

I I

Ci i

I i

I _.

I

___I__

- 1 I

Volume in cubic meters is total container volume shipped.

l I

'Ibtal curie content and principal radionuclides were determined by gama isotopic analysis of each batch of resin. Non-ganma emitting isci.cpes were determined by using factors scaled to principal ganma enitters in accordance with "AIF/NESP Nethodologies for Classification of Iw-Ievel Radioactive Wastes From Nuclear Power Plants",,Novenber, 1983.

e l

Hm

2.

Estimate of majo" nuclide composition (by type of wanto) l TYPE A I

TYPE B i

TYPE C I

TYPE D l

I

l-I-

--I I ' Isotope i Activity l Per Cent i Activity i Per Cent i Activity 1 Per Cent i Activity l Per Cent i I

I (Ci)

I I

(Ci) i I

(Ci)

I I

_g

_____g_

g_

____g g_____

g_________I-

__g i

H3 I

I I

I C14 l'

I I

I CR51 I

6.08E+0 1 2.95E+1 I I

I I

MN54 1

1.15E-1 I 5.59E-1 I I

I I

FES5 I

1.32E+O I 6.40E+O I I

I I

C058 8

4.87E+0 1 2.36E+1 1 I

I I

FE59 1

1.62E-1 1 7.88E-1 I I

I I

NI59 8

2.89E-6 1 1.40E-5 I I

I I

CO60 t

5.57E-1 1 2.70E+0 I I

I I

NI63 1

1.17E-5 I 5.65E-5 I I

I I

i 1

ZN65 I

7.42E+0 1 3.60E+1 I I

I I

NB94 I

I I

I SR90 t

i I

I I

I NB95 I

7.96E-4 I 3.86E-3 I I

I I

ZR95 1

2.16E-2 1 1.05E-1 1 I

I I

TC99 I

l' 8

I I

I RU103 I

I 1

I I

I RU106 I

I I

I I129 I

I I

~

l I

I131 1

4.78E-3 1 2.32E-2 I I

I I

I CS134 I

I I

I CS135 I

I I

CS136 I

I I

I CS137 I

I I

I BA140 1

1.46E-2 1 7.OBE-2 I I

I I

CE141 1

3.68E-4 i 1.78E-3 I I

I I

CE144 I

I l-1 I

I I

I PU239 I

I I

I i

1 I

I PU241 I

I I

l I

AM241 I

I I

I AM243 I

I I

I CM242 I

I I

I CM243 I

I I

I l

I

__t I

l I

I

_t i

3.

Solid Waste Disposition Total Centainer Solidification Number of Shipments Mode of Transportation Destination Type of Cont.ainer Volume Agent Type A 306m3 12 T..-a, nonnues

II.

TABLES l

C.

METEOROLOGICAL MEASUREMENTS - JOINT FREQUENCY TABLES i

i f

~

TMlLE II.C ^ '

~

Page 1 of 1 C.

Meteorological Measurements - Joint Frequency Tables The joint frequency distributionslof 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 dn the Radiation and Meteorological Monitoring System - RM21A.

Each of these

" wind roses" consist of eight pages of joint frequ'ency

-distributions.

There is one distribution for each of the I

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.

]

I e

f i

1 II.

TABLES D.

ONSITE AND OFFSITE RADIATION DOSE ASSESSMENT

+

)

TABLE II.D Page 1 of 1 SITE: LIMERICK usiIT U1 USER: MART DATg 2/14/84 1T32T

SUMMARY

OF MAXIMUM INDIVIOUAL DOSES TOT AL ACCURUL ATION FOR PERIDOS:

g LICUIO:

PROM 1/ 1/85 0:00 TO 12/31/85 23:00 GA5EOUS: PROM 1/'1/85 0:00 TD 12/31/85 23:00 g

APPLI C A BL E ESTIMATED AGE LOCATION

t OF LIMIT EFFLUENT ORGAk 00SE GRDUP DIST DIR APPLICA8LE-(MR)

(P. REM)

(M) (TOWARD)

LIMIT h

LIQUID TOTAL 800Y 5.12 E- 03 C HILO RECEPTOR 1 1.7E-01 30 LIQUID LIVER 1.05E-02 ADULT RECEPTOR 1 1.0E 10.0 NOBLE GAS AIR DOSE 0.00E+00 805.

N 0.0E+00 10.0 (GAMMA-PRAD)

N08LE GAS AIR 00$E 0.00E400 805.

N 0.0E+00 20.0 (8 ETA-HRAD) 3 NOBLE GAS T.80DY (GAMMA) 0.00E+00 ALL 0.

0.0E+00 5.0 3

NOBLE GAS SKIN (8 ETA) 0.00E+00 ALL 0.

0.0E+00 15.0 p

ICDINE+

T.80DY 0.00E+00 ADULT 884.

N 0 0E+00 15.0 PARTICULATES 3

l:

SUMMART OF POPULATION COSES TOTAL ACCUMULATION FOR PERIDOS:

I LICUID:

FROM 12/31/84 23:00 TO 12/31/85 23:00 j

GASEQUS: FEOM 1/ 1/85 0:00 TO 12/31/85 23:00 EFFLUENT APPLICABLE ESTIMATED h

ORGAk POPUL ATION 005E

( P E R S O N-R E M)

LIQUID TOTAL 800Y 9.9E-02 LIQUID THYRDID 5.7 E- 0 2 8

GASEOUS TOTAL 800Y 0.0E+00 GASEQUS THYRDIC 0.CE+00

)

J

- - - There were no releases of radioactive gaseous ef fluents during the above period and consequently no doses to members of the public due to their I

h activities inside the site boundary. Also, there were no doses to members of the public due to their activities inside the site boundary re-sulting from radioactive liquid releases.

d d

III.

ATTACHMENTS A.

SUPPLEMENTAL INFORMATION-ASSUMPTIONS USED IN DOSE ASSESSMENT f

III.

ATTACHMENTS A.

SUPPLEMENTAL INFORMATION Facility: Limerick Generating Station - Unit 1 License:

NPF-27 1.

Regulatory Limits (Technical Specification Limits)

A.

Moble Gases:

1 5 500 mRems/Yr - total body

" instantaneous" limits per

< 3000 mRems/yr - skin Tech Spec 3.11.2.1 2

5 5 mRads - air gamma - quarterly air dose limits per

< 10 mRads - air beta Tech Spec. 3.11.2.2 3

5 10 mRads - air gamma - yearly air dose limits per

< 20 mRads - air beta Tech Spec. 3.11.2.2 B.

Iodines, tritium, particulates with half life > 8 days:

15 1500 mRems/yr - any organ

" instantaneous" limits per (inhalation path)

Tech Spec. 3.11.2.1 2 5 7.5 mRems - any organ - quarterly dose limits per Tech. Spec. 3.11.2.3 3

5 15 mRems - any organ - yearly dose limits per Tech. Spec. 3.11.2.3 C.

Liquid Effluents:

1. Concentration < 10CFR20

" instantaneous" limits per Appendix B, Table II, Col. 2 Tech. Spec. 3.11.1.1 2 5 1.5 mRems - total body - quarterly dose limits per

< 5 mRems - any organ Tech. Spec. 3.11.1.2

3. S 3 mRems - total body - yearly dose limits per 5 10 mRems - any organ Tech. Spec. 3.11.1.2 2.

Maximum Permissible Concentrations MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.

The MPCs specified in 10CFR20, Appendix B, Table II, Column 2 for identified nuclides are used to calculate permissible release rates and concentrations for liquid releases per LGS Technical Specification 3.11.1.1.

i l

3.

Avarcge Ennrgy l

l E determination based on liquid release for the report period is O.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 04 4 of Batch Releases:

78 95 l

Total Time for batch releases, minutes 5752 6819 Maximum time period for a batch release, minutes 120 94 Average time period for batch release, minutes 74 72 Minir um time period for a batch release, minutes 56 45 l

Average stream flow (blowdown) i during periods of release of effluents into a flowing stream, gpm 5646 5846

'B.

Gaseous None l

l 6.

Abnormal Releases A.

Liquid None B.

Gaseous None i

l 7.

Description of Gaseous Release Points Release Point 1 = North Stack i

i Release Point 2 = Unit 1 - South Stack Release Point 4 = Hot Maintenance Shop 8.

Description of Liquid Release Points Release Point 1 - 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 4

Receptor 4 = Philadelphia Suburban Water Company Receptor 5 = City of Philadelphia Crew Course I

i

III.

ATTACHMENTS B.

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL AND SUPPORT DOCUMENTATION

+

e h

III.

Chrngas to the Offaito Dona Calculction Menunl and Support Documsntation Revision 3 to the Offsite Dose Calculation Manual (ODCM) is submitted for the period in which the change became ef fective.

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 SCl 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.

I i

I I

HP-1001, R2v. 1 Pcge 4 of 4 MAC/nlp ATTACTIENT 8.1 OFrSITE DOSE CALCULATION MANUAL Revision b LIMERICK GENERATING STATION UNITS 1 AND 2 PHILADELPHIA ELECTRIC COMPANY Docket Nos. 50-352 & 50-353 i

PORC Approval:

St'atiM Superintendent i

Nuclear and Environmental

^

Section Approval:

LGS Health Physics Represe tat e

s Nuclear and Environmental Representative:

r

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. I,la4ERICg stWERATWs0 STATICW DATE

/ 2 2'7-8 5 g.

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1Al'8l.

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ENylRONMENTAL SAMPLIND STATIONS

t INTIAMEDIATI D,isTANC5.

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FICtTAE M.A.2 20 i

1 l

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.... - - - - ~

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i

- ^ - - - - - - - - - - - - - - - -

U D.

d

4. Ingestion 6 IDCNT106 6

)

/

. 1) controh. station Milk (d) 22FL (d) Milk sniplas are taken from 2) 17c2 several farms surrounding Im.

3) 1981

'these farms include those with the 4) 25a1......

highest Anam potential from which.

as well as a control station.

l

'the locations of the farms are not listed herein due to a long-standing agreement with.the farmers involved.- In return,f_k

.....f0f. being m)1med to sample,.,and.1,,,

l analyse the milk, P500 has agreed.

. not to divulge the location of.

f-i the farms.

c :.h ' ' ?

W,. y. -

u

,, 1.9 - (e) 'nso -Tw" of recretionally im-3

- Fish -(e) " v -- 1) te(M1e of hPool

-16C}-

, SSE -

Upstream to Pigeon Creek.

pocant fish, sunfish and becun bullhead will be sampled if available.

4 l

2) upstrema of Ics, Keim Street 29C1 18#f 3.2 i

Bridge to Hanover Street i,

Bridge (control) j Pood Products

1) IGS Information Center 11S1.

ESE

' O.5 (f) Peod rh are to be samples

~

l (f) as part of the IGS 'ftschnical i

Specification Program only'if milk sampling is not performed.

l

'the. milk pathuey, dich results

- )

In a higher maximum doom tn

)

tasmans than the vegetation path-way is monitored at a 1contion near the site, anS is a better Indicator than vegetation j

samples. In addition, no crops 4

i groun in the vicinity of ICS are irrigated with water in i

which liquid plant westes have ENGR. M been discharged.

4 H.P.

[T]Qfs,

)

DATE

.J MM i

.

ML20140C143

Text

SUMMARY

SUMMARY

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