ML20212L966

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Semiannual Effluent Release Rept 5,Jul-Dec 1986
ML20212L966
Person / Time
Site: Limerick Constellation icon.png
Issue date: 12/31/1986
From: Franz J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20212L954 List:
References
NUDOCS 8703110012
Download: ML20212L966 (37)
v • d • e


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LIMERICK

[ GENERATING J .

STATION "

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I PHILADELPHIA ELECTRIC COMPANY I LIMERICK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-352 I

I SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 5 JULY 1, 1986 THROUGH DECEMBER 31, 1986 I

I I

Submitted to The United States Nuclear Regulatory Commission i Pursuant to Facility Operating License NPF-39 I

Preparation Directed By:

J. F. Franz, Manager Limerick Generating Station I

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I I

I

TABLE OF CONTENTS

[ I. Introduction II. Tables A. Quantitative Summary of Radioactive Liquid and Gaseous Effluents

( B. Solid Waste Disposition Report C. Meteorological Measurements - Joint Frequency Tables D. Offsite Radiation Dose Assessment

[ =III. Attachments

( A. Radiation Doses to Members of the Public Due to Their &

Activities Inside Site Boundary B. Supplemental Information - Assumptions Used in Dose Assessments s

( -' C. "B" Residual Heat Removal Service Water Radiation Monitor Failure g

[

[-

I

I I. INTRODUCTION I This submittal complies with the format described in Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive I 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.

I In accordance with LGS Technical Specification 6.9.1.8, this document summarizes the gaseous and liquid effluent I releases for the period of July 1, 1986 through December 31, 1986. Where "0.00E+00" is used, it denotes the less than detectable level for the given isotope. Supplemental information, consistent with the format of Appendix B of I Regulatory Guide 1.21, is also included.

Disposition of solid waste during the report period I (July 1, 1986 to December 31, 1986) 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

10 ERASE SCREEN A,o CONT 1NUE : C 1

l

TABLE A.2 hf., SITE . : LIMERICK PAGE 5 0F 9 UNIT: U1 USER! MART

(  ; DATE: 02/21/87 10:24 -

-EFFLUENT AND. WASTE DISPOSAL REPORT c __________________________________

.6ASE00S EFFLUENTS FOR RELEASE POINT: 2 UNIT 1 - SOUTH STACK

{.____________________________________

CONTINU0US MODE BATCH MODE NUClIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :

RELEASED -
3  : 4  : 3  : 4  :
2. 10 DINES
CI  : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 0.000Ef00 !

(  : I131 I133  : CI  : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 0.000Ef00 : l

[ .

TOTAL FOR :  :  :  :  :  :
PERIOD  : CI 0.000E+00 : 0.000E+00 : 0.000E+00 0.000E+00 :
(ABOVE)  : 1.  :  :  :  : -

(. ___...________________________________________________________________

3. PARTICULATES

{ ___C14

CI  : 0.000Ef00 : 0.000Ef00 0.000Ef00 : 0.000Ef00 :

t CR51  : CI  : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 0.000Ef00 :

[ ______________________________________________________________________

t- MN54  : CI  : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 0.000Ef00 :

h~ FE59  : CI  : 0.000Ef00 0.000Ef00 1 0.000Ef00 0.000Ef00 t C058  : CI  : 0.854E-04 : 0.000Ef00 : 0.000Ef00 t'0.000Ef00 :

{ -1 C060  : CI  : 0.000Ef00 0.000Ef00 0.000Ef00 1 0.000Ef00 :

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

{ .

___ZN65

CI
CI  : 0.000Ef00 0.000Ef00 : 0.000Ef00 0.000Ef00 :

SR89

[!  : SR90  : ~ CI  : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 :

2R95  : CI 0.000Ef00 0.000Ef00 : 0.000Ef00 1 0.000Ef00

{ ___________________________________________________________________

___53124  : CI  : 0.000Ef00 0.000Ef00 0.000Ef00 0.000Ef00 :

r CS134  : CI  : 0.000Ef00 1 0.000Ef00 : 0.000Ef00 0.000Ef00.

[- ______________________________________________________________________

~ CS136  : CI  : 0.000Ef00 : 0.000Ef00 0.000Ef00 0.000Ef00 :

CS137  : CI  : 0.000Ef00 0.000Ef00 0.000Ef00 : 0.000Ef00 :

ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C

{

m TABLE A.2 PAGE 6 0F 9 SITE: LIMERICK ,

UNIT: U1 ^

USER: MART DATE! 02/21/87 10:24 EFFLUENT AND WASTE DISPOSAL REPORT I -GASEOUS EFFLUENTS FOR RELEASE POINT:

2 UNIT 1 - SOUTH STACK 4

BATCH MODE CONTINUOUS MODE NUCLIDES  : UNITS : QUARTER : QUARTER ! QUARTER : QUARTER : I

!  :  : 4  : 3 4  :

RELEASED 3
3. PARTICULATES (CONTD)

~~~~~ ~~ ~~~ ~~

i BA14b i bi ib$bbbb+bbIbIbbbkIbbIbbbbkibbIbbbbbIbbI CE141  : CI  : 0.000Ef00 0.000Ef00 0.000Ef00 0.000Ef00 :

CI  : 0.000Ef00 0.000Ef00 : 0.000Ef00 : 0.000Ef00 :

I - CE144 UNIDENT.  : CI  : 0.241E-02 0.000Ef00 0.000Ef00 G.000Ef00 '

TOTAL FOR PERIOD  : CI  : 0.249E-02 : 0.000Ef00 : 0.000Et?0 1 0.000Et00 :

! (ABOVE)  : .

ENTER [ C ] TO ERASE SCREEN AND CONTINUE : C i

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- TABLE A.2 r-i g::t J PAGE -7 0F 9

^

SITE:' LIMERICK

~

-UNIT: U1 USER: MART

{ DATE: 02/21/87 10:25

[.e.EFFLUENTANDWASTEDISPOSALREPORT V,

n m >

s. / e 6ASE0ds EFFLUENTS FOR RELEASE POINT: '4 HOT MAINTENANCE SHOP y ____......__._______...-_.-___.--__- 7

, -f e b

' 'Q BATCH MODE es

'h. k CONTINU0US MODE c._ yun. . .

f?pt!,NUCLIDES : UNITS : QUARTER QUAR:!ER  : QUARTER : QUARTER :

3  : ~ 4- 3  : 4 :

tif~ RELEASED :

[n1 1.'FISSION GASES ,

p,

_..___.____.._-.._____.___-__________.u..__..___________-____-_____-. C.

['- 1 ..AR41  : CI  : 0.000Ef00 : 0.00tT+00 : 0.000Ef00 0.000Ef00 :

____.__----___.._______________-_____di.___.-_-_-_-___--__.-__..-____

KR83M  : CI  : 0.000Ef00 0.000Ef00 : 0.000Ef00 0.000Ef00 :

't KR85M 7: CI : 0.000Ef00 1 ,0.000Ef00 : 0.000Ef00 : 0.000Ef00 1 KR85  : Ci  ! 0.000Ef00'i'O.000EiOO .0.000Ef00 ! 0.000Ef00 : ,

- KR87 l' CII  : 0.000Ef00 0.000EiOO : 0.000Ef00 0.000Ef00

-____._-_.w.__- C..u_--___________--a _____.-____.-__--________. ____.

[^4(31 KR88 ,: - ~'. 4 It 'Ci 0.000Ef00 1 0,000Ef00 1 0.000Ef00 0.000Ef00 e,

_...___._ ;_____ --__-----_-_____- .s _______---_________-___ --_--_.

! KR89  : CI  : 0.000Ef00 0.500Ef00 0.000Ef00 0.000Ef00 :

m
l KR90  : CI  : 0.000Ef00 0.000Ef00 : 0.000Ef00 : 0.000Ef00 :

z;;' _XE131M.

CI  : 0.000Ef00 s 0.0(0Ef00 1 0.000Ef00 1 0.000Ef00 2

m _- _..__..--________-__-___--....________---..___e .__--__________..__

); -XE133M  : CI  : 0.000Ef00 : 0.000Ef00 0.000Ef00 1 0.000Ef00 :

'~ XE133  : CI  : 0.000Ef00 0.000Ef00 1 0.000Ef00 0.000Ef00

XE135M  : CI  : 0.000Ef 00 3 0.00'4Ef 00c: 0.000Ef00 : 0.000Ef00 :

_-___ ;____-________________....___.--a.__....________-______-________

XE135  : CI  : 0.000Ef00 0.000Ef00 0.000Ef00 1 0.000Ef00 :

______.. .__-_____ _-__-_.-___--___-_e,_...____-________________--..__

XE137  : CI T 0.000Ef00 0.060Ef00 : 0.000Ef00 : 0.000Ef00 :

( .______.. _____--...____ .....--___-____...__ .. ______-____- __- ______

XE138  : CI  : 0.000Ef00 0.000Ef00 1 0.000Ef00 ! 0.000Ef00 :

_____..__...._--_-___.__..__....___-___.-_.w._____......--_____._..__.

[.

1, UNIDENT. CI  : 0.000Ef00 0.000Ef00 3 0.000Ef00 2 0.000Ef00 TOTAL FOR !  :

CI  : 0.000Ef00 0.000Ef00 1 0.000Ef00 3 0.000Ef00

{e  :

PERIOD (ABOYE)  :  :

I

['/ ENTER [C]TOERASESCREENANDCONTINJE:

C f - .

TABLE A.2 PAGE 8 0F 9 SITE: LINERICK j UNIT: U1 l USER: MART l l

DATE: 02/21/87 10:25 EFFLUENT AND WASTE DISPOSAL REPORT

6 GASEOUS EFFLUENTS FOR RELEASE POINT
4 HOT HAINTENANCE SHOP CONTINUOUS H0DE BATCH MODE
NUCLIDES : URiTS : QUARTER : QUARTER : QUARTER : QUARTER :

RELEASED :  : 3  : 4 3  : 4  :

E _: _._________._______._____________________.___..__ ___________________

2. IDDINES t I131  : CI  : 0.000Ef00 0.000Ef00 0.000Ef00 : 0.000Ef00 :

1133  : CI  : 0.000E+00 0.000Ef00 1 0.000E+00 ! 0.000Ef00 :

TOTAL FOR :  :  :  :  :  :

I: PERIOD (ABOVE)

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

C I 3. PARTICULATES

0.000Ef00 : 0.000Ef00 0.000Ef00 0.000Ef00 :

I _:__C14 CR51

CI
CI  : 0.000Ef00 0.000Ef00 1 0.000Ef00 : 0.000Ef00 :

! HN54  : CI  : 0.000E+00 : 0.000Ef00 : 0.000Ef00 0.000Ef00 !

FE59  : CI  : 0.000Ef00 1 0.000Ef00 : 0.000Ef00 0.000Ef00 :

I ___________________________________________________________________

___C058  : CI  : 0.000Ef00 : 0.000Et00 : 0.000E+00 : 3.f00Ef00 :

__. ____________________________________________________ --.s.________

0.000E+00 : 0.000E+00 : 0.000rtQt ; o.)00E+00 :

I _:___C060

CI IN65  : CI
0.000Ef00 0.000E+00 1 0.000Lt00 . i.000Ef00 :

I ___SR89  : CI  : 0.000Ef00 0.168E-06 : 0 000Ef00 : 0.300Ef00 :

CI  : 0.000E'00 : 0.000Ef00 1 0.000Ef00 1 0.000Ef00 :

> SR90

! ZR95  : CI  : 0.000Ef00 0.000Ef00 : 0.00^E+00 1 0.000Ef00

0.000Ef00 : 0.000Ef00 0.000Ef00 : 0.000Ef00 :

I _:__SB124 CS134

CI
CI.  : 0.000Ef00 0.000Ef00 : 0.000Ef00 1 0.030Ef00.:

CS136  : CI  : 0.000Ef00 1 0.000Ef00 0.000Ef00 1 0.000Ef00 :

CS137  : CI  : 0.000Ef00 1 0.000E+00 0.000Ef00 0.000Ef00 :

ENTER C C ] TO ERASE SCREEN AND CONTINUE : C

TABLE A.2 PAGE 9 0F 9 SITE: LIMERICK

' UNIT: U1 USER: MART DATE: 02/21/87 10:26 EFFLUENT AND WASTE DISPOSAL REPORT I GASEOUS EFFLUENTS FOR RELEASE POINT:

4 HOT HAINTENANCE SHOP CONTINUOUS H0DE BATCH MODE NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER  :

RELEASED : 3  : 4  : 3  : 4  :

I 3. PARTICULATES (CONTD)

BA140  : CI  : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 0.000Ef00 :

CE141  : CI  : 0.000Ef00 0.000Ef00 0.000Ef00 : 0.000Ef00 :

CI : 0.000Ef00 0.000Ef00 1 0.000E+00 1 0.000Et00 :

I _-_CE144 UNIDENT.  ! CI  : 0.000Ef00

_______~_ .__________

0.000Ef00 1 0.000Ef00 0.000Ef00 :

TOTAL FOR :  :  :  :  :  :

I: PERIOD

(ABOVE)
CI
0.000Ef00 1 0.168E-06 : 0.000Et00 ! 0.000Et00 :

ENTER C C ] TO ERASE SCREEN AND CONTINUE : C I

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II. TABLES B. SOLID WASTE DISPOSITION REPORT July 01, 1986 to December 31, 1986 I

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M M M M M M m m M M M -

M SOLIp WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/86 TO 12/31/86 (Not irradiated fuel)

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL -_-___ ___

1. TYPE OF WASTE
UNIT : 6-month : Est. Total !!

Error, /.

!  : Period :

! -;_____ - __ g g- - __-

3  :

Spent resins, filter sludges, i m3 2.92E+2 :

i a.

Ci  ! 6.02E+2 1 2.51E+1  :

evaporator bottoms, etc. _________;____________:

=_________________g___.

__. i m3  : O.OOE+O  :
b. Dry compressible waste, Ci 0.OOE+0 : 0.OOE+O i contaminated equipment, etc.

-_______l- --=;_________g___ --3 Irradiated components, i m3  : 0.OOE+0 :

c. 0.OOE+0  :

control rods, etc.  ! Ci  ! O.OOE+0 :

I - = - -  ;

m3  : 0.OOE+O i d. Other (describe) Ci 0.OOE+0 0.OOE+0  :

--- I ---*

  • ____________e m
p O 8 e

g M Volume, given in cubic meters, is total container volume shipped. N to w

Total curie content and principal radionuclides were determined by gamma isotopic analysis of each batch of resin. Non-gamma emitting isotopes were determined by using factors scaled to principal gamma emitters in accordance with "AIF/NESP Methodologies for Classification of Low-Level Radioactive Wastes From Nuclear Power Plants", November, 1983.

7 R n n f. l R R R R_ R R R R R R R R R F 15 F'

2. Estimate of major nuclide composition (by type of' waste)

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I TYPE A I TYPE D TYPE C I TYPE D I

_ -g -

3- _ _ . - - -

__ g _ _ - - - = g i Isotope ! Activity I Per Cent i Activity I Per Cent i Activity i Per Cent i Activity l Per Cent i I I (Ci)  ! I (Ci) 1 I (C1) I I (Ci)  ! I g g g g -g g -g g__________g__ --=g i H3 I 1.80E-2 1 2.9BE-3 I I I I I I i 1 C14 8 1.11E-4 8 1.85E-5 I I I I I I I I CR51 1 -5.06E+1 8 8.40E+0 I I I I i i I
i MN54 I 4.45E+O I 7.38E-1 1 I I I I I I

. I FE55 I 5.76E+1 1 9.56E+0 I I I I I I I l C058 1 9.37E+1 1 1.56E+1 1 I I I I I I I FE59 1 1.58E-1 1 2.63E-2 I I I I I I I

. I NI59 I I I I I i I I I I CO60 1 2.41E+1 1 4.01E+0 t i I I I I l

'I NI63  ! I I I I I I I I I ZN65 I 2.42E+2 1 4.01E+1 I I I I I I I I ND94 I I I I I i i  ! i

! SR90 I 9.28E-2 1 1.54E-2 I I I I I I I i i NB95 1 6.71E+1 1 1.11E+1 I I I I I I I (

l ZH95 1 6.20E+1 1 1.03E+1 I I I I I I I l l TC99 1 1.06E-6 1 1.75E-7 I I I I I I I l I RU103 I I I I I I I I i

! RU106 I I I I I I  !  ! I ,

I I129 1 2.65E-6 8 4.40E-7 I I I I I I I I I131 I 9.12E-2 8 1.51E-2 I I I I I I I I CS134 I I I I I I I I I I CS135 I I I I I I i i I I CS136 I I I I I I I I I I CS137 I I I I I I I I I I DA140 1 1.11E-1  ! 1.84E-2 I I I I I i 1 l8 CE141 1 3.66E-1 1 6.08E-2 I I I I. I I I I CE144 I 6.21E-1 1 1.03E-1 1 I I I I I I

I PU239 I 2.07E-3 1 3.44E-4 I i  !  ! I i  !

i PU241 1 9.16E-2 8 1.52E-2 I I I I I I I I AM241 I 5.13E-3 1 8.52E-4 I I i  !  !  ! I i i AM243 1 3.31E-4 5.50E-5 I I I I I I I I CM242 I I I I I I I I I

I CM243 I I I I I I I I I $

I I I I .I I I I I _t @

NM

3. Solid Waste Disposition @N, Number of Shipments Mode of Transportation Destination

- - - - = ______

, 15 Truct< DARNWEl_L l 4 Trucl< HANFORD

I I 1. TseLES C.

I METEOROLOGICAL MEASUREMENTS - JOINT FREQUENCY TABLES July 01, 1986 to December 31, 1986 I

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r C. Meteorological Measurements - Joint Frequency Tables l

' The joint frequency distributions of wind direction and speed, by atmospheric stability class are attached under F separate cover. The distributions include all three wind L levels from Limerick Meteorological Tower No. 1. The distributions were developed on the Radiation and Meteorological Monitoring System - RM-21A. Each of these

[ " wind roses" consists of eight pages of joint frequency distributions. There is one distribution for each of the seven Pasquill-Gifford stability classes, A through G, and a combined "All Classes" page. The Pasquill-Gifford

[ stability classes are determined by the temperature differences measured over the 266-26 feet and the 171-26 All meteorological data were r feet height intervals.

finalized on the RM-21A system. NRC format meteorological L

data tapes covering the periods January 1986 through June 1986 and July 1986 through December 1986 are currently L retainea on site.

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4 II. TABLES D. OFFSITE RADIATION DOSE ASSESSMENT

' January 01, 1986 to December 31, 1986 E

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TABLE D PAGE 1 OF 1 I SITE: LINERICK I UNIT: U1 USER: MART DATE: 02/21/87 12:12

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES -

TOTAL ACCUMULATION FOR PERIODS:

LIQUID: FROM 01/01/86 0:00 TO 12/31/86 23:00 I GASEQUS: FROM 01/01/86 0:00 TO 12/31/86 23:00 AIR: FROM 01/01/96 0:00 TO 12/31/86 23:00 LIMIT I EFFLUENT APPLICABLE ESTIMATED ORGAN DOSE (MREM)

AGE GROUP LOCATION DIST DIR (M) (TOWARD)

% OF APPLICABLE (MR)

LIMIT

_ LIQUID 1.42E-03 CHILD RECEPTOR 1 4.7E-02 3.0

_I TOTAL BODY LIQUID LIVER 2.91E-03 ADULT RECEPTOR 1 2 9E-02 10.0 NOBLE GAS AIR DOSE 1.14E-03 884. N 1.1E-02 10.0 I NOBLE GAS (GAMMA-MRAD)

AIR DOSE (BETA-HRAD) 6.02E-04 884. N 3.0E-03 20.0 NCBLE GAS T. BODY (GAMMA) 7.87E-04 ALL 805. N 1.6E-02 5.0 .

I NOBLE GAS SKIN (BETA) 1.46E-03 ALL 805. N 9.7E-03 15.0 0.....................................................................

IODINE + BONE 4.47E-02 TEEN 966. ESE 3.0E-01 15.0 PARTICULATES

SUMMARY

OF POPULATION DOSES l

i TOTAL ACCUMULATION FOR PERIODS:

I LIQUID: FROM 01/01/86 0:00 TO 12/31/86 23:00 GASEOUS: FROM 01/01/86 0:00 TO 12/31/86 23:00 lE

_FFLUENT E APPLICABLE ORGAN ESTIMATED POPULATION DOSE im (PERSON-REM) g ______________________________________________________________________

1.1E-01 LIQUID TOTAL BODY LIQUID THYROID 1.0E-01 I GASEOUS GASEOUS TOTAL BODY THYROID 1.3E-01 5.0E-04 ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C

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I III. ATTACHMENTS RADIATION DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR I A.

ACTIVITIES INSIDE SITE BOUNDARY January 01, 1986 to December 31, 1986 I .

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ATTACHMENT A PAGE 1 OF 1 A. Radiation Doses to Members of the Public Due to Their Activities Inside Site Boundary I Per Technical Specification 6.9.1.8, the Semi-Annual Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to Members of the Public due to their actvities I inside the Site Boundary during the report period.

Technical Specification states that Members of the Public shall include all persons who are not occupationally I associated with the plant. This category does not include employees of the utility, its contractors, or vendors.

Also excluded from this category are persons who enter the I site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

The maximum gaseous dose to Members defined above would be less than 1 x 10-gfRem. the Public This as value is based on the following assumptions:

1. Real time meteorology and gaseous effluent releases.
2. Total body dose due to an inhalation exposure.
3. Highest exposed sector (SW) of those sectors within I site boundary available for occupancy.

The maximum expected occupancy factor is a working year 4.

(or 25%) along the railroad tracks.

5. Distance to the railroad tracks, which pass through Site Boundary in the SW sector, is approximately 300 I meters.

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I I III. ATTACHMENTS B. SUPPLEMENTAL INFORMATION I

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,- -ev,,--n- - - - - - - ---_ . . w, , n n w _ ~e

III. ATTACHMENTS ATTACHMENT B PAGE 1 OF 3 D. SUPPLEMENTAL INFORMATION Fccility: Limerick Generating Station - Unit 1 License: NPF-39

1. Regulatory Limits (Technical Specification Limits)

A. Noble Gases:

I 1. $ 500 mRems/Yr - total body

$ 3000 mRems/yr - skin

" instantaneous" limits per Tech Spec 3.11.2.1

2. $ 5 mRads - air gamma - quarterly air dose limits per

$ 10 mRads - air beta Tech Spec. 3.11.2.2

3. < 10 mRads - air gamma - yearly air dose limits per 3 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. $ 7.5 mRems - any organ - quarterly dose limits per Tech. Spec. 3.11.2.3 ,

I 3. $ 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, TaEle II, Col. 2 Tech. Spec. 3.11.1.1 I 2. $ 1.5 mRems - total body 5 5 mRems - any organ

- quarterly dose limits per Tech. Spec. 3.11.1.2

3. $ 3 mRems - total body - yearly dose limits per

$ 10 mRems - any organ Tech. Spec. 3.11.1.2

2. Ma):imum Permissible Concentrations MPCs are not used to calculate permissible release rates and I concentrations for gaseous releases.

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

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ATTACHMENT B

. Av7tr q 7 En7rgy PAGE 2 OF 3 E determination based on gaseous effluent releases for the report pariod is 0.315 Mev.

. M' surements and Approximations of Total Radioactivity A. Fission and Activation Gases The method used is the Canberra Series 90 Counting System; GS l - Gas Marinelli B. Iodine:

l The method used is the Canberra Series 90 Counting System; CH

- Charcoal Cartridge I

C. Particulate:

The method used is the Canberra Series 90 Counting System; PT l - Air Particulate Sample, 47 mm filter.

D. Liquid Effluents:

l 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 t

l A. Liquid Q3 04

  1. of Batch Releases: 12 6 l 909 394 Total Time period for batch releases,
  • Maximum time period for a batch release,
  • 91 67 Average time period for batch release,
  • 63 66 l Minimum time period for a batch release,
  • 75.75 65 Average stream flow (Schuylkill River) during periods of release of effluents 360,835 933,504 l

into a flowing stream, gpm o = Minutes

ATTACHMENT B PAGE 3 OF 3

(

B. Gaseous Q3 Q4 5 0

-. # of Batch Releases:

Total Time period for batch releases,

  • 40297 0 Maximum time period for a batch release,
  • 10297 0 Average time period for batch release,
  • 60 0

[,

Minimum time period for a batch release,

  • 8060 0

[

  • = Minutes

(' 6. Abnormal Releases A. Liquid

[ None B. Gaseous

{

None

(- 7. Description of LGS Effluent Release Points c Release Point 1 = North Stack, Common

[ Release Point 2 = South Stack, Unit 1 <

Release Point 3 = South Stack, Unit 2

{

Release Point 4 = Hot Maintenance Shop

( Liquid Release Point = LGS Liquid Radwaste Discharge

8. Description of LGS Liquid Dose Receptors Receptor 1 = LGS Liquid Radwaste Discharge Point Receptor 2 = Citizens Home Water Company

{

Receptor 3 = Phoenixville Water Company

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

{ .

[

f - - - - -

4 a

III. ATTACHMENTS I C. "B" RESIDUAL HEAT REMOVAL (RER) SERVICE WATER RADIATION MONITOR FAILURE I

I I

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ATTACHMENT C PAGE 1 OF 1 C. "B" Residual Heat Removal Service Water Radiation Monitor Failure During normal operations, the "B" RHR Service Water Radiation Monitor was declared out-of-service due to indications of low sample flow. An investigation of the problem revealed the accumulation of corrosive materials on the walls of the piping. Several factors were attributed to the corrosion:

a. small diameter (l") pipe;  !
b. short pipe lengths; I c. numerous 90 degree elbows;
d. River water, which is highly aggressive to carbon steel, is used to supply service water.

The incorporation of new pipe material (from carbon steel to stainless steel) and reduced bendings in the pipe lines (to facilitate system flushing) are being evaluated as the long-term solutions to redeposition of corrosive products in the RER Service Water Radiation Monitor sample lines. In the interim, approximately 400 feet of RER Service Water sample I piping has been replaced with carbon steel. The thirty (30) day Action described in Technical Specification Table 4.3.7.11-1.lb Action 101 was exceeded because the corrective maintenance of replacing sample piping could not physically be performed in the time specified while observing all applicable station administrative controls. <

Concurrent with the aforementioned failure, the "B" RHR Service Water Radiation Monitor Low Sample Flow Switch was declared inoperable during the performance of a Surveillance Test. The magnetic Flow Switch Assembly, used to initiate the " Low Sample Flow" alarm, was inoperable. A new flow switch was ordered, but upon delivery was determined to be incorrect. At this time, the thirty (30) day Action for this failure had already been exceeded. Subsequently, a new switch was ordered and installed.

The Technical Specification requirement to take grab samples every eight hours was observed during the entire period of "B" RER Service Water Radiation Monitor inoperability per PORC Position #16. At this time, the "B" RHR Service Water Radiation Monitor has not been returned to service.

Independently, either of these two failures would have I resulted in the thirty (30) day Action being exceeded.

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