ML18089A206
| ML18089A206 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1983 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18089A205 | List: |
| References | |
| PROC-830331, NUDOCS 8306300194 | |
| Download: ML18089A206 (74) | |
Text
A*,:
~
OFFSI'EE DOSE PS~G CALCULATION MANUAL The Energy People ','
I.
'1 1 ,---- -- ---- --- ---------~--- - - - --- - -- -------1 r SALEM NUCLEAR GENE~ TI1G 111
~ STATION
~~~~~~~~~~~~~~~
UNITS NO. 1 & 2 ri
- NOTICE -
r THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE 8EEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND' MUST BE RETURNED TO THE RECORDS FACILITY OPERATING LICENSE NOS.
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DEADLINE RETURN DATE
- 6/;ilf /!--7 1-*
'\
f-;> 0 61 DDl'f ()
RECORDS FACILITY BRANCH
.M.:\RCH 1983 r ~----------------~------------
1,- - --- - - -- - - - - - - - ---- - -------- -- --------------------- ---*-* - -- - --- - - -- ----~ ---- - - - - - -- -- - --
' I*
.. SGS/M PAGE 1 OF _ __
The Energy People REVISION NO. 0 NUCLEAR I OP DEPARTMENT DATE* 11/l /82 OF.'FSITE DOSE I TITLE:
CALC[JLATION MANOAL SECTION I
OFF.'SITE OOSE I CALC(Jf:.ATH1N MANUAL (ODCM)
I ON ITS 1 AND 2 OPERATING LICENSE NO. DPR-70 AND I OPERATING LICENSE NO. DPR-75 I SALEM NUCLEAR GENERATING STATION PUBLIC SERVICF.} ELECTRIC AND GAS COMPANY I
I I
I I
I JM PBO 55 10/l I
.-;~---
. f TIT{..'l!f ODCM - SNGS REVISIONt . 0 P.1.6 E OF SECTION:.* TABLE OF CONTENTS . DATE: 11/1/82 APP'D BY:
Chapter *Page
1.0 INTRODUCTION
1.1*
2.0 IMPLEMENTATION 2.1 3.0 RADIATION INSTRUME~TS 3.1
...~.'.
3.1 Gaseous Effluent Monitor Setpoints (General) 3.2 Liquid *Effluent Monitor Setpoints (General) 3.3 Instrument Setpoints 4.0 LIQUID EFFLUENT~ 4.1 4.1 Limits or Restrictions 4.2 General Guidance on Dose Calculations 4.3 Liquid Effluent Concentration 4.~ Liquid Effluent Dose 4.5 Liquid Radwaste Treatment I .5. 0 GASEOUS EFFLUENTS (NOBLE GASES) 5.1 5.1 Limits* or Restrictions I 5.2 General Guidance on Dose Calculations 5.3 Gaseous Effluent Dose to Air I 5.4 Gaseous Effluent Dose Rate to*Man I 6. 0 5.5 -Gaseous Effluent.
. Curie
. Release IODINE* 1 :ft, TRITIUM AND PART.ICULATES Estimates 6 .1
~*7 ~ -: *.~ .-. -~6
- r G0.5eoU~ ~ftuenr(~o-yr ~ob:te G-as )- Des-e ~ 0 Mane-:= * ~ ~ ~. ~ ~-~ ~ ~ ~~
6.2 Gaseous Effluent Dose Rate to Man I 6 .3 -~Gaseous Radwaste Treatment I.
'I 7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7.1 Monitoring Program 7.1 I 7.2 Estimate of Direct Radiation Dose I M P80 .55 10/2 I
l TITLE: ODCM-SNGS. REVISION~ 0 PAGE OF
. SECTllON: *
1.0 INTRODUCTION
DATE: 10/1/8 2 APP'o er:
- The offsite Dose Calculation Manual (ODCM) is required by.the Radiological Effluent Technical Specificati6n.
The ODCM was prepared incorporatin.g the guidance supplied. by the USNRc- Effluent Treatment Branch in their letter to all power reactors dated January 18, 1979.
It provides additional facts and administratives con-trols to be used at the Salem Nuclear Generating Station to.incorporate the principals of 10CFR50 Appendix I.. This document should be used in conjunc-tion with 0th.er station procedures and documents which are reference herein.
In order to provide reasonable assurance that d.oses remain within 10CFR50 Appendix I guidelines, a conversative assumption is to increase the dose calculated by 25%. Analysis performed to demonstrate compliance with 10CFR50 Appendix I indicates that ~his assumption should be conservative. The semi-annual Effluent Release Report will report the actual doses.
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M P79 56/15 4 1.. 1
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TITl.S: ODCM - SNGS REVISION: a PAGE OF SECTION: 2*1 IMPLEMENTATION CATE: 10/ l/ 82 APP'D BY:
This ODCM shall.be maintained in accordance with Radiological Technical Specification 6.14. It shall be reviewed at least once a year by the Station Operation Review Commi.ttee or their designee. Temporary changes are- permitted as long as. Section 6 .8 .3 of the Technical Specifications are.complied with. Distribution of amendments will be by controlled copies_.
~*.,
r M :Pao ss 10/3 2.1
1 La E ..Oept "*
TIT~: *oocM-SNGs !'EV ISIO'NI 0 PAGE OF SECTION: 3. 0 RADIATlON INSTRUMENTS OA TE: 10/1/82 0 APP 0 BY:
RADIATION.INSTRUMENTS OVERVIEW In the Salem Nuclear Generating Station several radiation monitors are provided on gaseous and liquid effluent path-ways to.provide radiological surveillance in accordance with General Design criterial 60 and 64. These channel9 are
- described in detail in the Salem Nuclear Generating Station Final Safety Analysis Report.
Channels which .provide effluent monitoring for gaseous
(
releases are listed below and pictorially represented in figure 3-1.
Gaseous Effluent Channels l ) Channel l-Rl4 Waste Gas Effluent Monitor This channel is located inside the waste gas duct work discharge line. It is a thick wall G.M. tube which is fairly insensitive to Xe-133 radiation. On high activ-ity It will closes valve 1WG41.
- 2) Channel l-Rl6, 2-Rl6 Noble Gas Vent Monitor These channels are located inside the vent duct work.
They are extremely sensitive sensors. Unit 1, l-Rl6 Channel is a. thin wall G.M. tube. Unit 2, 2-Rl6 channel is a. beta scintillator. They have no control function, and serve as a back-up to channels l-R4lt and 2-R41C which utilize pumps.
- 3) Channel l-R41C, 2-R41C Noble Gas Vent Monitor Channel l-R41C is located in the mechanical penetration area for Unit 1 and in the Auxilliary Building near the ventillatlon duct in Unit 2. They will isolate contain-ment and clo*se valve WG41.
J.
- 4) Channel l-Rl2A Containment/Vent Noble Gas Monitor This channel is part of the original plant design of the
-RMS System in which channel l-Rl2A could be switched to sample f-rom- the plant- vent or containment.
- 5) Channel l-R45A, B, C, D Hi~~ Range Vent Monitor (Later)
These channels contain a high range noble gas monitor channel R45B and a medium range channel R45C for com-pliance with NUREG 0578. A background channel R45A is also used. Channel l-R45D and 2-R45D monitor a fixed iodine/particulate Cartridge.
- 6) Channel l,2-R44A, B, C, D, E High Range Steamline Monitors These channels located on.top of the penetration area provide for high level noble gas detection from the atmospheric relief lines. These channels are currently not operational.
M P82 133/05 1-li 3~ 1
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. LaE.Oepf TITLE:
- ODCM-SNGS _!IEVISIOHI 0 PAGE OF SECTION: 3 ~ 0 RADIATI_ON INSTRUMENTS DATE: 10/1/82 0 APP 0 BY:
Monitoring of liquid release is performed by Channel R-18 and R37. The liquid channels utilized are listed below and describe pictorially in figure 3-2.
Liquid Effluent Channels
- 1) Channel l-Rl8, 2-Rl8 Liquid Waste Monitor This channel monitors liquid discharges from the liquid waste system. High activity in the discharge line will cause valve 1WL51 or 2WL51 to close.
- 2) R37 Chemical Waste Basin Monitor (Later)
THis channel monitors liquid discharges from the chem-ical waste basin. Normally no activity will.be discerned.
1~-- ~ -~ ~ -~-~ ~ c~ =- == -~ ~ ~ ~ ~- =
I- ----- - - --- -- - --- --- -- ----
-- - -- ~ -~ - --
r M P82 133/05 2-li 3.'ia
I ..r_-__r YARD R4£A-D SAFETY HAIN STEAM INSIDE VALVES LINE MONITOR TURBINE CONDENSER CONTAINMENT (LATER)
R .. .......
t!S197 HAIN STEAM ...........
STOP VALVE
~
~
Figure 2-1 Liquid Releases To The Environment 1
lJI 82.
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\
.'r~
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l
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t Victoreen Instruments Low Range Noble Gas Eberline Instruments High Range Noble Gas R41A R41B R41C Particulate Iod~ne .Noble Gas 1
R45B R45C R 16 PSEG Sampler.
I Inline ;I:odine & Part.
Low Range Routine PSEG Noble Gas Signal Eberlin Sampler 1
sampler. To Iodine & 1close Partic.
I High Range ¢ Routine I
.J Charcoal Gas Decay Tank Fuel . l-Rl4 WG41 (Unit 1 only) 3lag I VENT Figure 2-2 Gaseous Releases To The Environment 3.lc
LaE Dept\
I
, T\TLE:.._* ODCM - SNGS REVISIOHl 0 P'AGE OF SECTIOH3. 0. RADIATION UfSTRUMENTS 1
OATQl/l/82 APP D SY:
RADIOACTIVE GASEOUS EFFLUENTS MONITORING INSTRUMENTATION ODCM INSTRUCTION I-3.2 SNGS-TS 3.3.3.10 Specification:'
The setpoint is derived such that the channel will alarm before the release limits of Technical Specification 3.11.2.1 are exceeded. The release limits are as follows:
Whole Dose mrem/yr Body Skin Basis Instantaneous 500 3000- 10CFR20*
Limits Discussion:
The setpoint is based on a calculation usirig certain assump-tions r~garding*isotopes, release rates and dispersion.
The calbulations are pro~ided for each channel required by Table 3.3-13 of the SNGS-TS.
Method: .
In ~eneral the setpoint is derived as follows:
Action
. 1 The dose limits above are converted into a derived gaseous release rate in units of
.uCi/sec. A conservatively high vent flow rate of 125,000 cfm is used.
2 .*-:: The release rate in units of uCi/sec is
.- converted into.a radiological concentration in ~nits o~ uCi~cc.
3 Th~ sensitivity of each channel has been determined such that it is known how many counts per minute will be produced per j
uCi/cc of activity.
r 4 Using steps 2 and 3 a setpoint is produced which corresponds to the cbncentration
~ derived in step 2.
f I
M P82 126/02. 2-mw 3.2
La E Dept~.
, TITL!::~' ODC~ - SNGS R£VIS10Ht Q PAGE OF SECTION=). 0 RADIATION INSTRUMENTS . DA.TE.:11/1/8 2 APP'D l!IY:
RADIOACTIVE LIQUID EFFLUENTS MONITORING INSTRUMENTATION ODCM INSTRUCTION I-3.l SNGS-TS 3.3.3.9 Specification:
The setpoint is derived such that the channel will alarm before the release limits of Technical Specification 3.11.1.1 are exqeeded. The setpoint limits for channel l-Rl8, 2-Rl8, and R37 are described below:
C~ncentration uCi/cc Discharge Point Basis Instantaneous <MPC 10CFR20 Limits Discussion:
The setpoint is based on a calculation using certain assump-tions regarding isotopes, release rates and dilution. The calculations are provided for each channel required by Table 3.3-12 of the SNGS-TS.
Method:
In general the setpoint is derived as follows~
Action
. 1 *The activity concentration at the discharge point after dilution by the circulating water system is determined.
2 The activity concentration at the location bein~ moni+/-6red is determined.
3 The sensitivity of each channel has been determined such that it is known how many counts per minute will be produced per uCi/cc of activity.
4 Using steps 2 and 3 a setpoint is produced which corr~sponds to the ~oncentration derived in step 2.
M P82 126/02 1-mw 3.3
TITLE1*, 'ODCM
- SNGS "£VISIOHI 0 PUE 1 OF 3 SECTION: 10/1/82 A.PP'D llY:
. 3 *0 RADIATION INSTRUMENTS . OJ.TE:
3.2 Derivations of Setpoints Channel l-Rl4 Waste Gas Effluent Monitor Alarm: 15,000 cpm Basis:
~., .. The .alarm will activate when the concentration reaches ~7% of the Tech. Specs. instantaneous release rate limits for noble gases.
Calculations:
- 1. Instantaneous release*rate limits for noble gases:
A) ~* (Qtv
- Kv> ~ 500 mrem/yr.
Q where Qtv = the total noble gas. release rate from the plant vent in uCi/sec and Kv = the average total body dose factor due to gamma emission (mrem/yr per uCi/m3). X/Q is the atmospheric dispersion factor.
We assumed that Xe-133 is the dominant gamma emftting.
isotope present as indicated using the results of the PWR GALE code. The channel was calibrated using Xe-133. For simplicity, it can be shown that for whole body doseS. from gas decay tank releases using Table 11.1-6 of the FSAR, it can be- assumed that all releases consists of Xe-133 qnly.
The Ki term used is th.at of Xe-133.
mrem/yr
= 2.94E02 uCi/m3 500 QTv-~ (2.94E02*2.2E-6) uCi/sec QTV ~ 0. 77 Ci/sec*
- and .
.~here Qtv = the total noble gas release rate from the plant vent in uCi/sec.
M PBO 55 10/11 3.4
TITLE:,>
ODCM -.SNGS ltEVISIOHt 0 PA'GE 2 OF 3 1
SECTION: 10 /1./82 A.PP D llY:
- 1.0 RADIATION INSTRUMENTS DATE:
3.2 Derivations of Setpoints (Cont'd)
. l-Rl4 Waste Gas Effluent Monitor Lv = the average skin dose factor due to beta emissions (mrem/yr per uCi/m3), and Mv = the average air dose factor to gamma emissions
{mrad/yr per uCi/m3).
Assuming Kr-85 is dominant for skin dose then Lv = l.34E03 mrem/ir and assuming Xe-133 is dominant uCi/m * .
mrad/~r for air dose, then Mv = 3.53E02 uCi/m therefore:
. Qtv < 3000
[(l.34E03) + 1.1 x 3.53E02] (2.2E-06)
Qtv < 0.79 Ci/sec The whole body dose rate is the most restrictive.
- 2. Maximum waste gas release flow rate = 150 ft3/min 3 *. Conversion factor= 2.832 x 104 cc/ft3.
- 4. Weighted sensitivity of l-Rl4 for Kr-85 and xe-133 = 5.4 x 103 cpm
-=-....,_....,-
uCi/cc
- 5. Fraction of total releases expected to come from gas decay tanks = ..0.37 (Obtained from update *FSAR Tables 11.3-1 .and 11.3-2) *.
-- -,.- ~ . .
- --- - --- ~- - -- --- --- - - - ~ - -- - - --- -- --- - -- ---
M P80 55 10/12 3.5
LaE Peot
- ro-T,-T-L-E:=-----~O~D~C~M::;----~S~N~G~S:----------------__::____.....:_____--:o~--_:_------__,.3:---------...-j------
- REVISIOH~ P.lGE OF SEC Tl'ON: 3 .O RADIATION INSTRUMENTS ~ATE: 10/1/82 0
.lPP 0 B'f:.
r-------------""'."""-------__;,-'-------------------~--_:,_~--------~_j 3.2 Derivations of Setpoints (Cqnt'd) l-Rl4 Waste Gas Effluent Monitor 6 *. Meter error factor = 0.75 assumes worst case for meter rasponse error of +/- 25% (Radiation Monitoring System Technical Manual).
- 7. Conversion factor= 106 uCi/Ci.
- 8. Conversion factor = 60 sec/min.
- 9. X/Q = 2.2E-6 sec/m3 which is the historical highest calculated annual average relative *concentration.
Setpoint:
(0.37) (0.77 Ci/sec) (106 uCi/Ci) (60 sec/min) (5.4xl03 cpm/uCi/cc) (0.75) =
150 ft3/min x (2.832 x 104 cc/ft3) 16,297 cpm Therefore, choose the nearest major graduation bn the meter faca~ 15,000 ppm.
== -= =--==---::--==_.=:;--
M P80 55 10/13 3.6
LSE '°'ept TITLE: *ODCM~SNGS REVISIOHI 0 PA8E 1 OF 3
' 3.0 RADIATION INSTRUMENTS SEC Tl OH: DATE: 10/1/82 APP'D BY:
3.2 Derivations of Setpoints (Cont'd) 1Rl6 Plant Vent Effluent Alarm: 10,000 cpm
.Basis: The alarm will activate well before the concentra-tion reaches the Tech. Specs. instanta~eous_release rate limits for noble gases.
- Calculations:
- 1. Instantaneous release rate limits for noble gases:
A) X * (0Tv Ky) ~ 500 mrem/yr.
Q where 0Tv = the total noble gas rele~se rate from the plant vent in Ci/sec and Kv: .= the average total body dose factor due tG gamma emission (mrern/yr_ per uCi/m.3). _-
Assuming that Xe-133 predominates and using the respective Ky from the ODCM tnen: -.
Ky = 2.94E02 mrern/yr uCi/m3 Otv < 500 - .
(2.94E02) ( 2. 2E--Q)
Otv < 0.77 Ci/sec -.
and B) 0Tv *(L + 1.1- My) *X ~ 3000 rnrern/yr 9 Q :
where Otv = the _tota~ nob~~ gas release*~at~
~-= = -~--~ = =-~f~rom~ j:he=p_la11o._t.-~~n=1~- l..Il__u_c_J_/§~C~- = ~ ~ ~-~- ~-=- __ ~- ___ _
- ~
- - ---- -=---- ---- - -
- - - --- -~
M P79 62 04 5 3.7
L8 E De pf r1ru: ,., oDc'M - SNGS REVISION: 0 PA9( 2 OF 3
SECTION: 3 .,0 RADIATION INSTRUMENTS DA.TE:
10/1/82 .APP'D SY:
3.2 Derivations of Setpoints (Cont'd) l-Rl6 Plant Ve0t Effluent Lv = the average skin dose factor d~e to beta emissions (mrem/yr perv Ci/m3).
and Mv = the average air dose factor to gamma emissions
{mrad/yr per uCi/sec).
Assuming Xe-133 predominates:
rnrem/~r Lv = 3.06E02 uCi/m and rnrad/~r Mv = 3.53E02 uCi/rn )
Otv < 3000
[ 3
- 0 6 E0 2 + 1 . 1 x 3
- 5.3 E 0 2 ] ( 2
- 2 E- 6 )
Otv < 1.96 Ci/sec The wh'ole body dose rate is the more restrictive liill'i t.
- 2. Plant vent flow rate = 1.25 x 105 £t3/min.
- 3. Conversion factor= 2.832 x 104 cc/ft3 cpm 4a. Sensitivity to Xe-133 = 3.6 x 107 uCi/cc (Determined from initial radiological calibration by using procedure lPD 4.3.008).
4b. Sensitivity to a mixture of radionuclides typically present in the plant vent = 4.9 x 109 cprn/uCi/CC as determined by the Chemistry Department, September 1992.
- 5. Met-er--error factor = 0-. 7 5 assumes worst case_ f o_r meter response error of +/- 25% (Radiation Monitoring System Technical Manual) *
. 6.
'7.
Conversion factor 106 uCi/Ci .
Conversion factor= 60 sec/min.
- 8. X/Q = 2.2E-6 sec/m3 which is the historical highest calcu-lated annual relative concentration.
I M P80 55 10/16 3.. 8
L8E 0ept 0
TITLE:
.,
- ODCM-SNGS REVISIONt PAGE 3 OF 3
SECTION: 3.0 RADIATION INSTRUMENTS DATE: 10/1/82 APP'D BY:
3.2 Derivations of Setpoints (~ont'd) 1Rl6 Plant Vent Efflu~nt Limitation based on Instaneous Release limits' Ci uCi sec cpm (0.77 sec) (106 Ci) (60 iiiin) (3.6xl07 uCi/cc) (0.75) = 352,372 cpm (l.25xlo5 ft3/rnin) (2.832xl04 cc/ft3)
To provide early: indication of higher than normal plant vent activity 1he alarm setpoint is set to alarm at 10,000 cpm.
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M P79 62 04 6 3.9
La E .r.ie t
- TITLE:
- ODCM O. Pl.G~ 3
_R EVISIOH< OF sEcr\oH: 3 *0 RADIATION INSTRUMENTS DATE:
10/1/82 0 APP 0 B'l':.
3.2 Derivations _of Setpoints (Cont'd)
CHANNEL 2Rl6 Plant Vent (Gross)
INSTRUMENT NO. RA-8346-2 LOCATION Plant Vent Elevation 19~
DETECTOR Photomultiplier Tube, Beta Scintillator INTERL.OCKS CONTROLLED None
- LOOP NO. 4 INSTRUMENT RECOMMENDED SETTINGS
- coNF = 0.90EO DDBND = 1. 41E3 CTTIM = 3.00El' FAIL = O.OOEO HIGH VOLTAGE .ADJUSTMENT Set H.V. (test pt.) to 9.7 volts or adjust H.V. to obtain either of the following values:
a) 3.2E5 cpm from Co60 source number 237D b) l.1E5 cpm from Sr90 source number 237P c) l. lES cpm from Sr90 source number 2370 ALARM *4.57E05 CPM WARNING 1. 03E04 CPM ALARM SETPOINT BASIS: The alarm will activate when the concentration reaches the instantaneous ~elease rate limits for noble gases The detector utilized is a beta scintillator and is, therefore, more sensitive for beta rays then it is .for gamma rays. However, the predominate gaseous isotope is Xe-133 which is a beta and gamma emitter. The dose expression is solved and the most restrictive curie limit discharge* limit is selected as the radiation setpoint.
ASSUMPTIONS ANrr CALCULATIONS
- l. The ODCM limits the instaneous release rate for noble
.gases:
A. The whole body dose must be less than 0.5 rem as follows:
Kv* X/Q
- Qv < 500 rnrem/yr SNGS-2 M P79 63 02/4 3.10
L8E Dept
~.TITLE:
.. . ODCM REVISIOHt O* PUE .2 OF 3 SEC Tl OH:
- 3. 0 "RADIATION INSTRUMENTS DATE: 10/1/82 APP'D BY:.
ASSUMPTIONS AND CALCULATIONS: (Cont'd) 2Rl6 where Qv = the total noble gas release rate from the plant vent in Ci/sec and Kv = the average total body do~e factor due to gamma emission (mrem/yr per Ci/sec).
mrem/~r KV= 2.94 E 02 uci/m then:
Ov < 0.77 ci/sec and B. The skin dose must be less than 3 rem as follows:
Qv [L +1, 1 M] X/Q < 3000 mrem/yr
~v = the averaye skin dose factor due to beta emissions (mrad/yr) per uCi/m3 and Mv = the average air dose factor to gamma emissions (mrad/yr per uCi/m3 For X~-~33 the dose factors are as follows:
mrem/yr
= 3. 06EO 2 uCl/sec/m3 and mrad/~r
= 3~53E02 uCi/m Qv < 3000
[3.06E02 + (1.1) (3.53E02)] * [2.2E-6) therefore:
Qv < 1.96 Ci/sec 0.77 Ci/sec is a more restrictive limit than the 1.96 Ci/sec.
- 2. Maximum plant vent flow rate = 1.25 x 105 ft3/min
~ ~--~rP-SE'&G= tneerna=1~ memorandum 0 =0~f-6-'18--7~6 )=- ~ ~- ~ -~--~ =
' -~ -- -- *- --- -- - ___:*"- -~-- -- 4:_:_ _:'_: - 3c..---- ---
- 3. Conversion factor= 2.8 x 10 cc/ft -
. cpm
- 4. Sensitivity to 133xe = 3.50x107 uCi/cc (Determined from initial radiological calibation by using y~ctoreen procedure AT-65 on 12/12/78 with 3.39 x 10 uCi/cc of Xe-133.)
SNGS-2 M P79 63 02/5* 3 .B.
La E Oeot l*IT\.E: *'
- ODCM REVISIOHi 0 PUE 3 OF 3 SECTIOH:
. ' 3.0 RADIATION INSTRUMENTS OA.TE: 10/1/82 APP'O SY: .
ASSUMPTIONS AND CALCULATIONS: (~ont'd) 2Rl6 6
- 5. Conversion f~ctor = 10 uCi/Ci.
- 6. Conversion factor = 60 sec/min
- 7. X/Q = 2.2E-6.sec/m3 which is the historical highest
~.*.. calculated annual average relative' concentration.
- 8. In sampler background = 22 cpm (Victoreen Procedure
. AT-6 5).
Setpoin t: Alar*m Ci uCi sec 7
(0.77 sec)(lO 6 ci j (60 min)(3.50~10 ) u~i/cc = 456,779 cpm 5
( 1 . 2 5x1 0 f t /mi n ) ( 2 . 8 3 2x1 0 cc If t ) **
Therefore, dial in a setpoint of 4.57E05 cpm WARNING SETPOINT BASIS: The alarm will activate when the concentration reaches a fraction of the Technical Specifications quarterly
- release rate limits for noble gases. The alarm/trip setpoint wili be set to prevent the air dose from gaseou~
effluents from exceeding 5 mrad due to gamma emitters and 10 mrad~from beta emitters during any calendar quarter from each reactor at*the site.
(l/3.15E7)
- M
- x
- Q < Smrad (equivalent to lOmrad)
Q . quarter yr
( 1/3 .l SE7)
- N
- x
- Q < lOmrad (equivalent to 40mrad)
Q yr By solving for Q and d_ividing by the number of seconds in a calendar quarter, it may be proven that the average release rate of Xe-133 must be less than l.73E-2 Ci/sec for each reactor at the site.
Setpoint: Warning
-2 6 - . - 7 cpm (l.7xl0 Ci/sec) (10 uCi/Ci (60 sec/min) 3.50xl0 4 uc17C5 = 10,084 cpm (1. 25xl0 5 ft 3/min) (2. 832xl0 cc/ft )
The~efore diai in a setpoint of l.03E04 cpm I
SNGS-2 M P79 63 0~/6 3 .12
L5E Dept
.TITLE: **'
ODCM - SNGS 1 . 1 OF 3 REVISIOPH PAGE SECTION: DA.T~ APP'D Ill':
in 11 /Q?
CHANNEL 1R41C Plant Vent ~ampling Iodine INSTRUMENT NO. RA .
LOCATION Elevation 100 DETECTOR . Photomultiplier Tube, Beta Scintillators INTERLOCKS CONTROLLED Close 1WG41 valve LOOP NO.
INSTRUMENT RECOMMENDED SETTINGS CONF = 0.90EO DDBND* = 2.55E2 CTTIM = 3.00El FAIL* = O.OOEO HIGH VOLTAGE ADJUSTMENT Set H.V. (test pt.) to 6.9 volts (actual value) is _102~or. adju~t H.V. to obtain either of the fol~owing values:
a) 3. 2E5 cpm from Co60 source numbe.r 23.7D b) l.1E5 cpm from Sr90 source number 237P c) l.1E5 cpm from Sr90 source number 237D ALARM 4.31E5 CPM WARNING 9*.80E3 CPM ALARM SETPOINT BASIS: The alarm will activate when the concentration re~ches th~ instantarteous release rate limits for noble gases The detector utilized is a beta .scintillator and is, therefore, more sensitive for beta rays than it is for gamma rays.
However, the predominate gaseous isotope is Xe 133 which is a beta and gamma emmiter. The dose expression is solved.and the most restrictive curie limit dishcarge limit is selected as the radiation setpoint.
- ASSUMPTIONS AND CALCULATIONS
- 1. The ODCM limits the instantaneous release rate for noble gases: \
A. The Whole body dose must be less- than -o. 5 rem as follows:
Kv* X/Q
- Ov ~ 500 mrem/yr
,.. where Ov = the total noble gas release rat~ from the plant vent in Ci/sec and Kv = the average total body dose factor. due to gamma emission (mrem/yr per Ci/sec).
Kv = 2.94 Eo2 I
- Adjust as required. MP79 53 8/1 3.13
L8 E Dept TITLE: ,.* ODCM - SNGSonitoring System R E'VISION: 1 1"4GE' 2 OF j
~
SECTION: 1 T"> 7\ T'IT 7\'T'T(il\1 Tl\lC:'T'RfTMl<'l\l'T'C: 04.TE: 10 I 1I 82 APP' 0 !IY:
ASSUMPTIONS AND CALCULATIONS {CONT"D) 1R41C
_then:
Ov <.0.77 Ci/sec and B. The Skin dose must be less than 3 rem as follows:
....... Ov* [L +1.1 M] X/Q < 3000 nrem/yr Lv = the average skin dose factor due to beta emissions (mrad/yr) per uCi/m3 and = the average air dose.factor to gamma emissions (mrad/yr) per uCi/m3
- For Xe-133 the dose factors are as follows:
Lv = 3.06E02 mrem/yr uCi/sec/m3 and Mv = 3.53E02 mrad/yr uCi/m3 Qv < *3000
[3.06E02 + (l.1)(3.53E02)]*[2.2E-6]
therefore: ,.*
Qv < 1.96 Ci/sec 0.77 Ci/sec is more restrictive limit than the l.9fr Ci/sec.
- 2. Maximum plant vent flow rate = 1.25 x 105 ft3/min (PSE&G internal memorandum of 6/18/76)
- 3. Conversion factor = 2~8 x 104 cc/ft3
- 4. Sensitivity to 133xe- = 3.33Xl07 cpm uCi/cc Determined from initial radiological caliQration by using Victoreen procedure AT-65* on 12/12/78 with 3.39 x lo-2 liCilcc o-f Xe--133.
- 5. Conversion factor = 106 uCi/Ci.
_q. Conversion factor = 60 sec/min 7~ X/Q = 2.2E-6 sec/m3 which is the historical highest calculated annual average relatiave concentration.
- 8. In sampler background= 22 cpm (Estimate using Victoreen procedure AT-65).
I MP79 53 8/2
-3 .14
/
L8 E Dept TITLE:,** bDCM - SNGS REVISIOHf 1 PASE OF 3 1 SECTIOH: 0 DA.TE: APP 0 B'f:
ASSUMPTIONS AND CALCULATIONS (Cont'd) 1R41C SetpDint: Alarm Ci uCi sec (0.77 sec) (106C1) (60 min) (3.33xlo7 cpm) = 430,678 cpm (l.25xl05 ft3/min)(J.832xl04 cc/ftl) uCi/cc Therefore dial in a setpoint 4.31E5 cpm WARNING SETPOINr BASIS: The alarm will activate when the concentration reaches a fraction of the Technical Specifications quarterly release rate limits for noble gases. The alarm/trip setpoint will be set to prevent the air doss from gaseous effluents from exceeding 5 mrad *due* to gamma emmitters and 10 mrad from beta ~mmitters during any calendar quarter from each reactor at the site.
(l/3.15:E7)
- M
- x
- Q < 5mrad (equivalent to 1 Um rad)
Q quarter yr.
- (l/3.15E7) * ~
- x
- Q < lOmrad(equivalent to 40rnrad)
Q yr.
where, M~ N, x and Q are defined in the ODCM Q
By solving for Q and.dividing the number of seconds in a calendar quarter, it may be proven that the average release rate of Xenon-133 must be less than l.73E-i Ci/sec for each reactor at the site.
Setpoint: Warning cpm (l.73xlo-2ci/sec) 106 uCi/Ci) (60 sec/min) j,33xlo7 uCi/cc - 9,676 cpm
. (l.25xl05 ft 3/min) (2.832xlo4 cc/ft3)
Therefore dial in a setpoint of 9.80 E3 cpm
\
MP79 53 8/3 I 3.15
LaE Qeo!
L TITLE: ODCM _REVISIOH:
0 P.I. GE 1 OF 3
SEC T1~0 H:
3.0 RADIATION INSTRUMENTS 10/1/82 0 0.1. TE: A PP 0 B'f:.
3.2 Derivations of Setpoints (Cont'd)
CHANNEL 2R41C Plant Vent (Noble Gas)
INSTRUMENT NO. RA-1.0155-2 LOCATION Eiec. Penetration Area glevation 100, columns Cl9A C20A DETECTOR Photomultiplier Tube, Beta Scintillator
. Il':J.TERLOCKS CONTROLLED Close 2WG41 Valve LOOP NO. 2 INSTRUMENT RECOMMENDED SETTINGS CONF = 0. 90Eo* DDBND = 2.71E2 CTTIM = 3.00El FAIL = O.OOEO HIGH VOLTAGE ADJUSTMENT Set H.V. (test pt.) to 7.9 volts actual. value is 1180 volts or _adjust H.V. to obtain either of the following values:
a) 3.2E5 cpm from Co60 source number 237D b) 1.lES cpm from Sr9El source number 237P c) l.1E5 cpm from Sr90 source number 2370 ALARM 4.89E05 CPM WARNING l.10E04 CPM ALARM SETPOINT BASIS: The a~arm will activate when the concentration reaches the instantaneous release rate limits for noble gases The detector utilized is a beta scintillator and is, therefore, more sensitive for beta rays then it is for gamma rays. .However, the predominate gaseous isotope is Xe-133 ~hich ia a beta and gamma emitter. The dose expression is solved and the most restrictive curie limit discharge limit is selected as the radiation setpoint.
ASSUMPTIONS AND CALCULATIONS
- 1. The ODCM limits the instaneous release rate for noble gases:
A. The Whole body dose must be less than 0.5 rem. as follows:
Kv* X/Q
- Ov < 500 mrem/yr r
SNGS-2 M P79 63 02/1 3.16 j
L8E Dept TITLE: ODCM REVISIONi 0. PAGE 2 OF 3 SECTION: ' 3. 0 RADIATION INSTRUMENTS DATE: 1O/li82 APP'o ev:
ASSUMPTIONS AND CALCULATIONS: (Cont'd) 2R41C where Qv = the total noble gas release rate from the plant vent in Ci/sec and Kv = the average total body dose factor due to gamma emission (mrem/yr- per Ci/sec).
mrem/yr uCi/m3 then:
Ov < 0.77 Ci/sec and B. The Skin dose must be less than 3 rem as follows:
Qv * [L +1.1 M] X/Q < 3000 mrem/yr LY = the average skin dose factor due to beta emissions mrad/yr) per uCi/m3 and Mv = the average air dose factor to gamma emissions (mrad/yr per uCi/m3)
For Xe--133 the dose factors are as fallows:
mrem/yr L
v = 3 .O 6E02 uC1/m3
. and mrad/~r Mv = 3. 5 3EO 2 uCi/m Qv < 3000
[ 3
- 0 6 EO 2 + ( 1
- 1) ( 3
- 5 3 EO 2) ] * [2
- 2 E-6 ]
therefore:
Qv < 1.96 Ci/sec 0.77 Ci/sec is more restrictive limit than the 1.96 Ci/sec.
- =---::- - = -= ~ ------==- -=--=-
=- ---- -= - ~ -_ 2 .--~ ~~xi~~~ -~p1a~-t_ve~--t~ fl-o~.=- r_~t,~~ ::~-1_:2 s~~x~~~ 9~~- It ymr_ n __ :~ -:- --~~---~~ ~ - ~- - _
(PSE&G internal memorandum of 6-18-76) - - ~ -~ ---
4 3
- 3. Conversion factor = 2.8 x 10 cc/ft cpm
- 4. Sensitivity to 133 xe = 3.75xl0 7 uCi/cc (Determined from initial radiological calibration SNGS-2 M P79 63 02/2 3 .1 7
LSE Dept
~TITLE:,! ODCM REVISIOHI 0 3 PAGE OF SECTION: *3. 0 RAD.IATION INSTRUMENTS 04.TE: 10/1/82 APP'o al':
ASSUMPTIONS AND CALCULATIONS: (Cont*' d) 2R4 l c by using Victoreen procedure AT-65 on 12/12(78 with 3~39 x 10- 2 uCi/cc of xe-133.)
6
- 5. Conversion factor = 10 uCi/Ci.
~* Conversion factor = 60 sec/min
- 7. X/Q = 2.2E-6 sec/m 3 which is the historical highest calculated annual average relative concentration.
- 8. In sampler background = 20 *cpm (Victoreen procedure AT-6 5).
Setpoin t:
- Alarm Ci uCi sec . cpm (0.77sec). (10~ er;-) 7
.(60 min) (3.7~xl.O ) ifi/cc = 489,407 cpm (l.25xl0 ft /min) (2.832xl0x cc/ft )
Therefore, dial in a septoint of 4.89E05 cpm WARNING SETPOINT BASIS: The alar.m will activate when the concentration reaches a fractrion of the Technical Specifications quarterly*
release rate limits for noble gases. The alarm/trip setpoint will be set to prevent the air dose from gaseous effluents form exceeding 5 rnrad due to gamma emitters and 10 rnrad from beta emitters during any calendar quarter from each reactor ~t the site. *
(l/3.15E7)
- M
- X
- Q < 5mrad (equivalent to lOrnrad)
Q quarter yr (l/3.15E7)-
- N
- X
- Q < lOmrad (equivalent to 40rnrad)
Q yr By solving for Q and dividing by the *numb~r of seconds in a calenda~ quarter it may be proven tha~ the average release rate of Xe-133 must be less than l.73E-2 Ci/sec for each reactor at the site.
Setpoint: Warning 2 6 7 cpm (l.73x.io- ci/sec) 10 uCi/Ci) fi60 s3c/min) 3.75xl0 4UCI/cc = 10,996 cprn 3
(1. 25xl0 ft ./min) ( 2. 832xl0 *cc/ft )
Therefore, dial in a setpoint of l.10E04 cpm j
SNGS-2 M P79 63 04/3 3 .18
u:1t. uepr TITl.E: ,*1 ODCM - SNGS u . .L.
REVl510Ht OF L
3.0 RADIATION INSTRUMENTS 10/1/Bfut SEC Tl OH: O.t..TE: .t.PP'O BT:
3.2 -Derivations of se*tpoints (Cont'd) 1Rl2~ Containment/Plant Vent Gas Effluent (Plant Vent Mode*)
Alarm: 20 ,000 cpm ,.*
Ba.sis: The alarm will. activate when the concenration reaches the Tech. Specs. instantaneous release rate limits for noble gases (Salem Technical Specifications Section 3.11.2.1). FSAR Table 11.1-7 is used to determine the fractional npble gas releases.
Calculations:
- 1. Instantaneous release rate limits for noble gages:*
A) X *<Otv
- K;) ~ 500 mrem/yr*
Q where Otv = the total noble gas release rate. from the plant vent in uCi/sec and Kv ~ the average total body dose £acto1 due to gamma emission (mrern/yr per uCi/m3).
\
Assuming the \fractional releases Xe-133 predominates:
I mrem/~r Kv = 2.94E02 uCi/m 500 Otv < (2~94E02)(2.2E-06) and Otv < 0.77 Ci/sec B)X
- Otv * (Lv + 1.1 Mv) < 3000 mrern/yr Q*
where Otv =the* total noble gas release rate fro~ the plan vent in uCi/sec.
\.
L= the *average skin dose factor due to beta emission
( mrem/yr per uC-i/m3 ) .-
I 3.19
.M
- PBO 55 10/14
L8 E Dept TITl..E: :* 'ODCM-SNGS REVISION! 0 PUE 2 OF 3
- SECTION: 3.0 RADIATION INSTRUMENTS DA.TE:* 10/1/82 A.PP'D 81:
3.2 Derivations of Setpoints (Cont'd) 1Rl2A Containment/Plant Vent Gas Effluent (Plant Vent Mode)
..*.. and Mv = the average air dose fa'ctor due to gamma emissions (mrad/yr per uCi/m3).
mrem/1r L = 3.06E02 uCi/m .
and mrad/yr M = 3.53E02 uCi/sec therefore:
3000 (3.06E02 + 1.1
- 3.53E02) (2.2E-6) 0.79 _Ci/sec whole body*is the more restrictive limit.
- 2. Maximum plant. vent flow rate = 1.2 x 105 ft3/min (PSE~G internal memorandum of 6-lB-76).
- 3. Conversion fa~tor = 2.832 x 104 cc/ft3 cpm
- 4. Sensitivity to Xe-133 = 2.1 x 106 uCi/cc (Determined from initial radiological calibration.
u~ing procedure lPD 4.3.004}. *
- 5. Meter error factor= 0.75 assumes worst case* for meter response error of + 25% (Radiation Monitoring System Technical Manu_al). *
- 6. Conversion Factor= ~06 uCi/Ci. \
- ~ ---* --
I M P79 62 04 4 3.20
LeE~Oept TITl.E: I ODCM - SNGS REVISION: 0 PAGE 3 OF 3 SECTION: 3. 0 RADIATION INSTRUMENTS DATE: 10/1/82 APP'o BY:
3.2 Derivations of Setpoints (Cont'd)
- 7. Conversion factor= 60 sec/min.
- 8. X/Q = 2.2E-06 sec/m3 which is the historical highest calculated annual relative concentration Setpoint:
(0.77Ci ) (106 uCi)60 sec (~.l x 106 cpm )(0.75) sec Ci min uCi/cc = 20,555 cpm (1.25 x 105 ft3/min) (2.832 x 104 cc/ft3)
Therefore, choose the nearest major graduation on the meter face of 20,000 cpm
==~===~===~=~=====~
M P80 55 10/15 3.21
TITLE:*. . . . ODCM-SNGS *:. . . *.o* . REVIS.ION;** ""b ... P~Gel OF* 2.
SECTION: .
- 3. 0 RADIATION. .. INSTRUMENTS.
. DATE: *. *10/1/82 - APP'O BY:
3: 2, De:ti va tions. of Setpoints (Cont'd).
l-R18 Liquid Wast~*oispo~al Monitor Alarm: 800,000 CPM is permissible if and only if MPCw is*
greater than 2 .5 .x 1-0-5 uCi/cc.
Basis: This channel l-Rl8 device monitors a liquid_ waste discharges before these discharges are diluted by the ~irculating water and released to the environment. Sect ion 3 .11.1 .1 of the Tech~ Specs~ requires that the MPC not be exceeded. The alarm will activiate when the concentration through the monitor reaches a value whe~e the resultant concenttation in the dilution water will exceed the MPCw for an historical mixture of isot9p~s.
Calculation:
- 1. MPCw =weighted MPC where 2.5 x lo-5 uCi/cc is the worst case historical data in Porter Gertz Consultants Technical Report
- 150 (PGC T~ #150).
- 2. CPM Sensitivity of monitor is 2.9 x 107 uCi/cc as calculated and documented in the original calibration of the R18 detec~or based on 1PD4.3.001.
3~ A flow rate through the. li_quid radwaste discharge line of 80: GPM is assumed ..
- 4. Meter error factor= 0.75 assumes worst case for meter response of
+2~% (Radiation monitoring system techniccil manual).
- 5. Flow rate of 185,000 GPM assuming operation of one circulating water pump @ full flow. If a procedure is written to assure both circulating water pumps are operating a value of 370,000
- GPM may be* used.
- 6. Throttling factor of 2 *shouid be used if the flow rate through the sampler is less than 40 GPM~
Calculate the setpoint as follows:
Setpoint:
-- MPCw (.Rl8 sensitiv.ity) (#circul~tors) (circulatbr flow rate) (meter error (Pump flow rate) (throttle error (if any)) .
M P79 "62 04 7 3.22
TITLE: . ODCM-SNGS**.
-;--R-evisloN;*-, o *--. PAGE2 OF* 2 . ~ .. *.. . - .
SECTION: 3. 0 RADIATION. INSTRUME;NTS. DATE: 10/1/82 .. APP'O BY:
Method of Arriving at Variable set"po.int
- 1-R-18 Liquid Waste ~isposal Manito~ (Cont'd)
Example uCi CPM (2.5 x lo-5 cc * (2.9E7 uCi/cc * (1) * (185,00 gal) * .75
-..... ~~~~~~~~~--,-~--,-~80-=------:1,----,,----,(~2~)~~~~~~~~~.,.--~-
min = l.01E6 CPM
~
min Select the closest value other than full scale or 800,000 cpm How to determine the MPC;
- MPCw is calculated as follows
. . . . . . . . etc.
MPCA Therefore, choose the nearest graduation on the meter face less than the full scale.
M P79 62 04 8 3.23
Lat: .oept Tl T LE:
I
' ODCM * - SNGS REVISION: Q PAGE lOF 2 SECTION: 3.0 RADIATION INSTRUMENTS DA TE: *10/16/82 0 APP 0 BY:
J.2 Derivations of Setpoints - Cont'd CHANNEL R37 Chemical Waste Basin INSTRUMENT NO. RA-LOCATION Yard - near basin DETECTOR Photomultiplier Tube, Gamma Scintillator INTERLOCKS CONTROLLED - None Loop No.
INSTRUMENT RECOMMENDED SETTINGS CONF = 0.90EO DNBND* = l.92E2 CTTIM = 3.00El FAIL = O.OOEO HIGH VOLTAGE AD,JUSTMENT Set H.V. (test pt) to 6.2 volts or adjust H.V. to cibtain any of the following values:
a) l.9E5 cpm from Ba 133 source number 237J b). 1. 6E5 cpm from Cs 137 source number 237L ALARM 1."O9E4 cpm WARNING 5.51E3 cpm Alarm Basis: This device monitors liquid waste streams frorn the chemical waste basin it is diluted by the circurating water and released to the environment. The ODCM requires that the MPCw not be exceeded. The alarm will activate when the concen-tration through the monitor reaches a value where the resul-tant concentration in the dilution water will exceed the MPCw.
The MPCw for an unidentified mixture will be used for conser-vatism.
Assumptions and Calculation:
- 1. MPCw = lxlO~uCi/cc for unidentified ~sotopes (10 CFR 20, Appendix B, Table _2_) ~
2~ Sensitivity to- Co50 = l.69xlo8 cpm/uCi/cc Sensitivity to Cs-137 = 8.83x107 cpm uCi/cc (determined from initial radiological calibration by using Victoreen Procedure AT-64 on 12/4/78 with 1.07 x io-2 uCi/cc of each isotope.
- 3. Maximum flow rate through pathway=* 300 gal/min.
- 4. Flow rate of dilution water = 370,000 gal/min (Page Q-11.3-1 of the FSAR states there will be a dilution flow of 740,000 GPM. As a conservative assumption, bnly half of the dilution flow was con-sidered).
- Adjust as Required MP 79 44 31/l 3.-24.*
LaE Dept
- TITLE: REVISION~ Q ODCM - SNGS . PAGE 2
- 3. 0 RA.DIATION INSTRUMENTS DATE: 10/16/82APP'O B'I':
Assumptions and Calculation - Cont 1 d R37
- 5. Conversion factors.
a) Conversion factor = 3.Sx103 b) Conversion factor = 1.31 x 105 min/quarter c) Conversion factor = lo-6 Ci/uCi
- 6. Sampler background = 60 cpm (Cb) Initial background as determined by Victoreen Instrument Corporation in channel 2R35, subsequent backgrounds may be higher as the sampler becomes contaminated.
Setpoint: Alarm cpm (lxlo-7 uCi/cc) *(S.83xlo7 uCi/cc) (370,000 GPM) +Cb = 10,890 cpm +Cb 300 GPM Therefore dial in a setpoint of l.09E04 cpm Warning Basis'. Warning will activate when the liquid activity concentra-tion exceed~ 1/2 the MPC of an unidentified liquid.
Setpoint: Warning cpm (1/2) (lxio-7 uCi/cc 8.83x107 ucilCC) (3.70x105 GPM) + 60 = s,50,5 cpm 300 GPM Therefore dial in a setpoint of 5.51E03 cpm NOTE: 1) If the MPC is known to be higher than 1 x io-7 then the alarm trip setpoint may be raised higher by a factor of M.PC (actual) lxlO" i uCi/cc MP 79 44 31/2 1/2 3.25
L8E Deot TITL~:' 'ODCM REVISIOHI 0 . l PA.GE SECTION: 3.0 RADIATION INSTRUMENTS 10/01/82 DA.TC:
- A.PP'D SY:
3.2 Derivations of Setpoints (Cont'd)
CHANNEL 2Rl8 Liquid Waste Disposal INSTRUMENT NO. RA-4335~2 LOCATION Auxiliary Building 86, 148/TT .
DETECTOR Photomultiplier Tube, Gamma Scintillator INTERLOCKS CONTROLLED Close valve 2WL41 Loop No. 5 INSTRUMENT RECOMMENDED SETTINGS CONF = 0.90EO DNBND = 3.69E2 CTTM = 3.00El FAIL = O.OOEO HIGH VOLTAGE ADJUSTMENT Set H.V. (test pt) *to 6.2 volts or adjust H. V. to obtain any of the following values:
a) l.9E5 cpm from Ba 133 source number 237J" b) l.6ES cpm from Cs 137 source number 237L c) l.6ES cpm from Cs 137 source number 237M ALAW4 - 4.08E04 cpm WARNING 2.05E04 cpm Alarm Basis: This device monitors liquid waste streams before ..
they are diluted by the circulating water and released to th~ environment. The ODCM requires that the MPCw not be exceeded. The alarm will activate when the concentration through the monitor reaches a value where the resultant concentration in *the dilution ~ater will. exceed the MPCw. The MPCw for an unidentified mixture will be used for conservatism.
- Assumptions and Calculation:
- 1. MPC~ = lxlo-7 uCi/cc .for unidentified isotopes (10 CFR 20, Append~~~~, Table 2).
- 2. SensTtiv-ity to Co60 = l.69xJ::o8 cpm/uCi/cc Sensitivity to Cs-137 =.8.83xl07 cpm uCi/cc (determined from initial radiological calibration by using Victoreen Procedure AT-64 on 12/4/78 with 1.07 x l0-2 uCi/cc of each isotope.
- 3. Maximum (present) flow rate through pathway = 80 GPM (PSE&G internal memorandum of 6/18/76).
SNGS-2 M P79 63 02/7 J.26
La E Dept TITl..E: ,.*
' ODCM REVISIOHl ()" P.t.9£ 2 SECTION:
- 3.0 RADIATION INSTRUMENTS DA.TE: 10/01/82 APP'O BY:
2 Rl 8 (Cont'd )
- 4. *Flow rate of dilution water = 370,QOO GPM (Page Q-11.3-1.of the FSAR states there will be a dilution flow of 740,000 GPM. As a conservative assumption, only half of *the dilution flow was considered).
a) Conversion factor = 3.8xlo3 cc/gal b) Conversion factor= 1.31 x 105 min/quarter c) Conversion factor = 10 6 Ci/uCi
- 5. Sampler background = 60 cpm (Cb) Initial background as determined by Victoreen Instrument Corporation in channel 2R35, subsequent backgrounds may be higher as the sami;>ler becomes contaminated.
Se tpoi nt: Al arm*
cpm (lxl0-7 uCi/cc) (8.83xl07 uC1/cc) (370,000 GPM) +Cb= 40;839 cpm + Cb 80 GPM Therefore dial in a setpoint of 4.08E04 cpm Warning Basis: Warning will activate when the liquid activity concen-tration'**exceeds 1/2 the MPC of an unidentified 11.quid.
Setpoint: Warni~g
-7 3 7cpm (1/2) (lxlO uCi/cc 8.8 xlO ~Ci/cc) (3.70xlo5 GPM) + Cq = 20,479 cpw 80 gpm Therefore, dial in a setpoint of 2.05E04 cpm NOTE: 1) If the MPC is known to be higher than l x l0-7Lhen the alarm trip setpoint may be raised higher by a factor of MPC(~ctual) lxl0-7uci/cc \
- 2) If the flow rate_ thro~g~ ~he pathway is 200 GPM then the setpoint should be diminished by-a f~ct~r of . 80 GPM 200 GPM I
SNGS-2 M P79 63 02/8 3.27
TITLE:
LSE Dept
' ODCM:-SNGS REVISIOHI *Q PAGE OF SEC.pOH: 4.1.LIQUID EFFLUENTS DA.TE: 10/1/82 APP'o B'I':
4.1 Limits or Restrictions.
The dose from liquids at unrestricted areas should. be limited in accordance with 10CFR20, 10CFRSO Appendix I and 40 CFR190 such that:
4.1.1 Liquid releases must b~ maintained below the concentrations of 10CFR20.106.
4.1.2 During any calendar quarter (Jan.-Mar.,
April-June, July-Sept., Oct.-Dec.) the dose delivered shall be less than 1.5 mrem to the whole body and _less than 5 mrem to any organ from each reactor.
4.1.3 During any calendar year (Jan. Dec. 31) the dose delivered shall be less than 3 rri.rem to the whole body and less than 10 mrem to any organ from each reactor.
- The values above are to be treated as limits.
However, if the calculatd dose from the release of radioactve materials in noble gaseous effluents exceeds the* limits described above; prepare and submit a Special Report (not an LER) to the conunission pursuant to Specification 6.9.2 of the SNGS-TS and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is ~ 25 mrem (except to the thyroid, which is limited to < 75 mrem) over a calendar year from all reactors.
- -- -- --- - -- --- - - ---- -~
---=- ----
M P79 18 29/01 4.1
'l LSE Dept TliiL.E:
ODCM-SNGS REVISION~ 0 PAGE S E-C Tl 0 H: 4.2 LIQUIIL.EFFLUENTS OATE: 10/1/82 .1.PP.'O BY:
4.2 ~eneral Guidance,on Dose Calculations 4.2.2 The dose shall include liquid radioactive discharges from the station and shall be classified as either a batch or continuous releases. This does not include isotopes below the limit of detection or isotopes identified in composites analysis or isotopes with very short.decay times.
4.2.2.1 *Liquid Batch Release are defined as releases from the following locations:
i) Waste Monitor Tanks ii) Laundry and Hot Shower Tanks iii) Chemical Drain Tanks iv) Chemical Volume Control System Tanks v) Waste Monitor Hold-up Tank vi) Waste Hold-up Tanks 4.2.2.2 Continuous Liquid Releases are defined as releases from the following locations:
i) Steam Generator ~lowdown 4.2.3 The dose contribution for each .radionuclide~
identified in liquid effluents released to
- unrestricted areas will be calculated using equatio~s which follow for the purpose of demonstration compliance with the Technical Specifications.* For submitting 6 month ,
effluent release reports, additional pathways J will be included and differences in the
~ ~ -~ =- .~calctiTa-t-ea~dos*es-may--ari~s-e =due- ~to~-the =in--~-~~ = = ~-~ - ~ -~l
~ --* - - - -=-c-lus fan _'.oof-'---t-:he'se=-add=i~ti-onal~ dose-_ :con trib.u 'tors -~ - -- - -- 1 and the inclusion of isotopes which are only available several weeks after the individual releases have taken place.
M P79 18 29/02 4*. 2
L8E Oe
'TITLE:
OQCM-SNGS !!EVISIOH: Q PJ.'GE OF SEC Tl.OH: 4.3 LIQUID EFFLUENTS - CONC. DJ.H: 10/1/82 APP'O Bl':.
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION ODCM - INSTRUCTION I-4.l SNGS - TS 4.11.1.1.2 Specification:
The concentration of radioactive materials in liquid effluents at the point of discharge must be below the concentration limits of 10CVR20 Appendix B, Table II, Column 2 .. For noble gases, the concentration must be less then 2Xl0-4uci/ml.
Discussion:
The locations listed in ODCM Section 4.2.2 will be analy-zed for the isotopes listed in Table 4.11-1.of the SNGS-TS. The concentration of each isotope at the point of discharge will be determined using the dilution pro-vided by the Circulating Water System.
Method for Determining Compliance:
BATCH MODE
- 1) The concentration at the point of discharge is determined as follows for batch discharges:
Ca= C -:- D Concentration at = Concentration ~ Dilution factor discharge point (Cd} in tank (Ct)
Where:
Let D = f/F where f is the flow from the waste moni-tor tink pumps based on instrument FT-1064. The normal yalue is 80 gpm. F is the dilution flow from the Circulating Water Pumps. Each pump yields 185,000 gpm. The maximum value of F for Batch re-leases is _370, ()OCL gpm._ The nominal value of D is 2300. (If no circulating water -pumps are oper-a-tional; ctedit may be taken for the volume of water contained in the discharge *pipe),
Instructions for Batch Releases Step Action 1 From the Chemistry Department find which iso-topes were detected (above LLD) in samples of liquid waste discharged, and list them in uCi/cc.
M P79 18 29/03 4.3
La E Q.~pt TITCE: ODCM-SNGS REVISIQM: 0 P.1. GE Of SECTIQ.'<: 4. 3 LI.QUID EFFLUENTS - CONC. DATE: 10/1/8 2 0 APP 0 BY:.
Step . Action 2 Divide each isotpes activity concentration by 2300 or D.
3 List the MPC for each isotope detected, along side the isotopes detected.
4 If the value of the Ca is much less than the MPC (<0.01) for each isotope then compliance is assured and y0Ul1eed go no further.
5 If the value of Ca is less than the MPC for each isotope and chemistry has found several isotopes in the liquid waste you must assure that the ratio Cd/MPC for all the isotopes is less than 1.
6 If Cd/MPC for each isotope is less than the ratio of l/N where N is the number of different ~sotopes found then compliance is assured and you need go no further.
7 If Cd/MPC for any isotop~ is greater than l/N then determine the ratio Cd/MPC and determine if its sum is less than 1.
NOTE: These instructions are merely a guide. A computer may be used to provide the required calcuations. Actual transcripton of data may differ as long as the calculation used are the same as listed her~.
Method for Determining Compliance CONTINUOUS MODE
- 1) The concentration at the point of discharge is determined as foliows for continuous discharges:
eoncentrat-ion- at -= C0neentrati0n--:- ~Dilution factor (D) discharge point (Cd) in tank (Ct)
Let D = f/F where f is the *flow fom the waste monitor tank pumps based on instrument 'FT-1064. The normal value is 80 gpm. F is the dilution flow from the circulating water pumps. Each pump yields 185,000 gpm. The maximum value of F for Batch releases is 370,000 gpm. The nomial va~ue of D *is 2300. (If no circulating water pumps are operational, credit may be taken for the volume of water contained in the discharge pipe).
M P79 18 29 3 .1 4.4
' * - - . - * - - - - - - - - - -.- - - * - - - - - - - - - - - - -**--* **-----***---*-*---*-*-*-*-**. .- *-**--..*-----*- -- - *~**-*,...-**--*---*--***-*-*******--..--***-***---*****I'
LaE Dept
- TITLE: ' ODCM-SNGS REVISIONl 0 PA6E OF
' SECTION:
I 4 .'3 LIQUID EFFLUENTS - CONC. DA.TE: 10/1/82 APP'O BY:
The concentration at the point of discharge is determined as follows for continuous discharges from steam generator blowdown:
- (Cb -:- ( b/ 5 0 0)
F Where: b is the blowdown rate of each generator lb/hr F is the dilution flow from the Circulating Water Pumps. We assume that when the blowdown is directed to the flash tank, 1/3 flashes to steam and 2/3 goes out as a liquid. See USNRC Final Environmental Statement.
The maximum value of F for continuous releases is 185,000 gpm.
Instructions for Continuous Releases Step Action 1 From the Chemistry Department, find out if any blowdown occurred during the week. If there was no blowdown compliance with Specification 4.11.1.1.2 is assured.
2 If blowdown occurred list each isotope>s concentratin above LLD, and each generator blowdown rate.
3 Divide the blowdown rate (lbs/hr) by 500 to express the result in gpm. The factor of 500 takes the steam line temerature and pressure into account and converts lbs/hr into gpm.
4 Divide the blowdown rate (gpm) by the Circulating Water Flow (gpm). This is the dilution D.
5 Divide the isotopic concentration by the d1lution D.
6 Since only 2/3 of the blowdown is discharged as a liq~id, multiply the value in Step 5 by 2/3. This is the conservative estimate of the concentration of the Chemical Waste Basin releases at the point of discharge.
7 If Cd/MPC for each isotope *is much less than the MPC for each isoptope then compliance is assured and you need go no further.
8 Continue using Step 5-7 for batch release above.
M P79 18 29/3.2 4.5
La E Dept
'TITLE: ODCM-SNGS ~EVISIOH~ 0 Pl.GE Of se:cnpH: 4 .'4 LI9UID EFFLUENTS - DOSE OA TE: 1Q/l/S2 APP'O BY:.
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE ODCM - INSTRUCTION I-4.2 SNGS-TS 4.11.1.2 Specification The dose to A MEMBER OF THE PUBLIC from liquid effluents will be limited to the values below:
SUMMARY
OF LIMITS Dose Calendar Calendar Calendar'*'
to Qu,arter Year Year Whole *Body LS mrem
- 3 mrem 25 mrem Organ 5.0 mrem 10 mrem 75 mrem
- The EPA 12 month values includes liquids, gases, and direct radiation and apply to all reactors at the site.
All other values apply_ to each number unit.
Discussion
- 1) CUMULATIVE DOSES will be determined at least once per 31 days.
- 2) A CUMULATIVE DOSE for the month, quarter, and year will be maintained.
- 3) The DOSE will be determined using the formula provided below.
~ -
~-~ ,_
M p79* 18 29/04 4.6
LSE Deot TITLe' ODCM-SNGS REVISIOIH 0 PAGE OF SECTION: 4.4 LIQUID EFFLUENTS - DOSE OJ.TE: 10/1/82 APP'O SY:
Dose Equation eq l) D = A
- t
- C * (DU)
- where D = is the DOSE (to the whole body or to any organ.
A = a DOSE CONVERSION FACTOR (See eq. 2 (mrem/hr per uCi/cc) t = the time over which the C and F terms are averaged (hours)
C = the AVERAGE CONCENTRATION *at the point of discharge isotope (uCi/cc see instruction 4.3.3 on Pg. 4.4.
DU = dose uncertainty factor = 1.25 (see instruction 6)
The composite dose coversion factor actually consists of* the impact of each isotope . to an individual due to the fish consumption and the consumption of crabs, oysters, and clams. The equation for the dose conversion factor (A) may be written as:
eq 2) A= l.14E5 (21 BF + SBI) DF where BF = the bioaccumulation factor for ~
nuclide in the fish as taken from Reg. Guide l.l091Salt water)
(pCi/kg per pCi/l)
BI = the bioaccumulation factor for a nuclide in invertebrates as taken from Reg. Guide 1.109 (salt water -
-pC-i/kg per ~Ci/l )-
21 = the # of kilograms of fish which an adult may consume in a year.
5 = the # of kilograms of clams, oysters and invertebrates which an adult may consume in a year.
DF = a dose factor for a nuclide in a preselected organ with units of mrem/pCi intake, as taken from Regulatory Guide 1.109.
M P79 18 29/05 4.7
LaE De 0
TITLE:
' ODCM-SNGS _REVISIOH: 0 P.1. GE OF SE:CTIQH: 4.4 LIQUID EFFLUENTS - DOSE 0 A TE:: l 0I1I8 2 APP'O BY':
The A factor is supplied for each isotope and is listed as Table. 4.1. The BF, BI and OF factors to calculate the A factor was taken from Reg.. Guide 1.109.
METHOD INSTRUCTIONS FOR CALCULATING RADIATION DOSE FROM LIQUID EFFLUENTS STEP ACTION 1 Determine the isotopes released. Pre-release isotopic analyses are used for routine dose calcu-lations. Post7release isotopic analyses such as strontium analyses are added at least once per 31 days.
2 Locate the dose conversion factor (A) for each isotope using Table 4.1.
3 Determine the average concentration of the release (C) at the discharge point by taking into account all dilution. An average concentration ia equal to the total number of microcuries discharged over the total amount of fluid discharged.
4 Multiply the A, C, and the duration of the relea*se ( t) .
5 The value obtained is an estimate of the total dose received by a MEMBER OF THE PUBLIC who consumes these aquatic foods at the rate. specified.
6 For purpose of complying with 10CFR50 Appendix I dose limits and, since post-release analyses may I
I caus.e
- the dose estimated in step 5 to be non-"con-servati ve, a dose uncertainty factor of 25% is added. Doses ar~, therefore, multiplied by a I factor of 1.25.
M P79 18 29/06 4.8
La E Dept TITLE.: *,> 'ODCM-SNGS REVISION: 0 P.l.9E OF SECTION: . 4.5 LIQUID RADWASTE DA.TE:
10/1/82 .l.PP'O S'I': ..
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS ODCM - INSTRUCTION I-4.3 SNG S-TS 4. 11
- 1 . 3. 1 Spe~:i)~_i_~at!_q_~
Before each release PSE&G will project the cumulativ~ dose that the public would receive if the release were to take place.
The liquid radwaste treatment system.will be used before the cumulative dose would exceed the following values during any calendar quarter:
- 0. 3 7 5 mrem to the whole body 1.250 mrem to any organ To allow for uncertainty the 1 iquid radwaste : treatment syst_em will be used if the cumulative dose exceeds the following values:
0.30 mrem to the whole body 1.00 mrem to any organ Discussion The liquid radwaste treatmen*t system is the installed waste EVAPORATOES.
- 1) . Estimates of the cumulative dose will be performed using ODCM instruction I-4.2.
- 2) When the CUMULATIVE DOSE in a calendar quarter*is main-tained and it is projected that any subsequent releases would cause waste to be discharged in excess of the above levels then the WASTE EVAPORATOR will be turned on and ut"ilized.
STEP ACTION 1 Look at liquid cumulative dose record~. *Cumulative dose calculat~ons must be performed at least once per 31 days.
2 Check to s-ee- if it fs updated-to include -latest batch -
releas*e.
3 If the dose records are up to date check the cumulative dose records to determine if the cumulative dose exceeds 0.3 mrem or 1.0 mrern to the whole body or to any organ.
These value allow for an additional uncertainty factor of 1.25. If it isn't over these values the Radwaste System need not be operated, otherwise the Radwaste System must be operated.
- I 4 If the records are not up to date, update them.
M P79 18 29/07 4.9
L8E Dept
- TITLE!' ODCM-SNGS REVISION~ Q' PAGE OF SECTION: '"5. 2 GASEOUS EFFLUENTS 04TE: 10/1/82 APP'D 81': **
5.1 Limits or Restrictions.
The dose to air at the site boundary should be limited in accordance with 10CFR20, 10CFR50 Appendix I and 40 CFR190 such that:
5.1.1 Gaseous releases must be maintained1 below the concentrations of 10CFR20.106.
5.1.2 During any calendar quarter (Jan.-Mar.,
April-June, July-Sept., Oct.-Dec.) the dose delivered to air shall be less than 5 mrads and 10 mrads from gamma and beta radiation respectively from each reactor.
5.1.3 During any calendar year (Jan. 1-Dec. 31) the dose delivered shall be less than 10 mrads\and 20 mrads from gamma and beta radiation respectively from each reactor. -
The values above are to be treated as limits.
However, if the calculatd dose from the release of radioactve materials in noble gaseous effluents exceeds the* limits described above, prepare an"d submit a.Special Report (not an LER) to the-commission pursuant to Specification 6.9.2 of the SNGS-TS.
M P79 18 29/08 5.1
L&E Dept ODCM-SNGS REVISION: Q' PASE OF 0
SECTION:
- 5.1 GASEOUS EFFLUENTS DATE: 10/ 1/ 8 2 APP 0 BY': '
- 5.2 General Guidance on Dose Calculations 5.2.l The dose from gases shall be estimated at*
least once every 31 days for each unit while releases are being made.
5.2.2 The dose shall include all gaseous radio-active discharges from the station. Isotopes identified as MDL or LLD are treated as numerically equal to zero.
5~2.2.l Release sources includes/but are not limited to* the following locations:
i) Waste Gas Decay Tan-ks ii) Containment Pur~es 5.2.3 The dose contribution for each radionuclides identified in gaseous effluents released to unrestricted areas will be calculated using equations which follow for the purpose of demohstrating compliance with the Technical Specificatiohs. For submitting 6 month effluent release reports, additional pathways will be included and differences in the cal-culated doses may arise due to the inclusion of these additional dose contributors and the inclusion of real time met~orological data.
M P79 18 29/09 5.2
L8E Dept TITl.E.:*
ODCM-SNGS REVISION! Q PAGE 1 OF 2
- . SECTION: 5 .3 GAS EFFLUENTS DOS_E DA.TE: 10/ 1/8 2 APP'O BY:
RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE ODCM INSTRUCTION I-5.1 SNGS TS 4 .11. 2. 2 Specification:
The DOSE to air due to noble gases released from each reactor from the site at and beyond the SITE BOUNDARY will be limited to the following:
SUMMARY
AIR DOSE LIMITS Air Dose Calendar Calendar*
From Quarter Year Garruna Rays 5 mrads 10 mrads Beta Rays 10 mrads 20 mrads Discussion The releaBe of noble gases will be restricted.
CUMULATIVE DOSE contribution for the current calendar quarter and current calendar year will be maintained using the formula provided below.
Dose Equations
- 1. In order to calculate the dose from Garruna Rays of noble gases, use the following equation:
D =13.17E-8 *Mi*~* Qi
- DU G Q
- 2. In order to calculate the dose ~rom beta rays of noble gases, use the following equation:
D =z3.17E-8 *Ni* X *Qi* DU B Q Method Instructions For Demonstrating That Noble Gas Releases are Within Limits A reconunended scheme for determining compliance of air-borne releases is presented below. The use of a digital computer will greatly simplify these calculations.
M P79 18 29/10 5.3
LSE Dept
~. TITLE':' Q' ODCM-SNGS REVISION~ PASE 2°F 2 SECTION:
I 5.3 GAS EFFLUENTS DOSE DATE: 10/1/82 0 APP D BY: .
Step Action 1 Determining isotopic composi t*ion of noble gases . dis-charged in uCi/ cc or equivalent. Using the equa-tions, determine the release rate requirements.
2 Using Table 5.0 which lists the dose conversion factors locate the K, L, M, and N terms for each individual isotope of interest. In addition, let the DU Term equal a dose uncertainty factor of 1.25.
3 Use the "Chi over Q (X /Q) term of 2.2E-6 sec/m3 which is the historical highest calculated annual average relative concentration according to Supple-ment 3 US.NRC Salem Nuclear Generating Station Safety Evaluation Report.
4 Determine the total number of microcuries (Qi) in the.
calendar quarter or calendar year.
5 Substitute the M, N, and Q terms into the equations provided.
6 For purpose of complying with 10CFR50 App. I dose limits and since post release analyses may cause the dose estimated in Step 5 to be non-conservative, a dose uncertainty factor of 25% is added. Doses are, therefore, multiplied by a factor 'of 1.25.
M P79 18 29/10.l 5.4
L8E Dept *
"- TIT.l.E: ODCM-SNGS REVISION: 0 PAGE 2
SECTION: 5. 4. GAS EFFLUENTS DOSE RATE DA.TE: 10/1/82 APP'O Bl':
RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE RATE ODCM - INSTRUCTION I-5.2 SNGS - TS 4.11.2.l.l specification The DOSE RATE due to gaseous noble effluents will be lim-ited to the following values:
For noble gases: <500 mrem/yr whole body (3000 mrem/yr skin Discussion The release rate of noble gases will be routinely de-termined to be continuously within the above values by use of the continuous noble gas instrumentation located in the plant vent. In order to document that the release rate of noble gases is within specifications an equation i~ to be used at least once per 31 days.
The equations to use are as follows:
Ki (X) Q < 500 mrem/yr Q"
(Li + l.lMi) (X) 2i < 3000 mrem/yr Q
where O*
-1 = microcuries per second The factors Ki, Li, M{, and Ni relate the radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These factors may be taken directly from Tab1e B-1-, of the Regulatory _Gpide 1.109 _(Ref. 6),
if the values therein are multiplied by 106 to cC>nver-t piocuries to microcuries as used in the above eq~ations.
M P79 18 29/11 5.5
l8EDept ,
- ,TITLE:
.- ODCM-SNGS REVISION~ Q" PASE 2 OF 2 SECT1'0N: 5.4 GAS EFFLUENTS DOSE RATE DATE: 10/1/82 APP'O B'I':
Instructions For Demonstrating That Noble Gas Releases are Within Limits A recommended scheme for determining compliance of air-borne releases is presented below. The use of a digital compute~ will greatly simplify these calculations.
Step Action 1 Determining isotopic composition of noble gases dis-charged in uCi/cc or equivalent. Using equations in 5.3.4 determine the release rate *requirements.
2 Using Table 5.0 which lists the dose conversion factors locate the K, L, M, and N terms for each individual isotope of interest.
3 Use the "Chi over Q (X /Q) term of 2.2g-6 sec/m3 which is the historical highest calculated annual average relative concentration according to Supple-ment 3 USNRC Salem Nuclear Generating Station Safety Evaluation Report.
4 Determine the total number of microcuries (Qi) in the calendar quarter or calendar year.
5 Substitute the M, N, and Q terms into the equations provided.
6 For purpose of complying with 10CFR50 App. I dose limits and since post release analyses may cause the dose estimated in Step 5 to be non-conservative, a dose uncertainty factor of 25% is added. Doses are, therefore, multiplied by a factor of 1.25.
M P79 18 29/12 5.6
LaE De TITLE!*'
- ODCM. - SNGS REVISION~ ,0 PASE 1 OF 4 SECTION: .S.5 G~SEOUS EFFLUENTS - CURIESAT~ 10/1/82 APP'o er:
RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS CURI*E RELEASE ESTIMATES ODCM INSTRUCTION I-5.3 Specification:
In order to determine the dose to Members Of The Public from the discharged -Of radioactive material it is necessary that estimates of the curies discharge be determined.
Discussion:
The estimate of the quantity of curies discharge from batch releases is based on the specific activities contained in the waste tanks as determined by grab samples. The specific activity in the grab sample is multiplied by the volume of gas discharge. An estimate of the *quantity of gas dis-charged from continous gaseous releases is based on the re-sults of _monthly grab samples as long as no abnormal*
releases have occurred. If either the R-16 channels or.
R-41C channel goes into alarm the abnormal releases have occurred. Curie estimates are updated by the results provided by isotopic analysis.
Method:
Instructions for Estimating Curies Discharged From Routine waste Gas BATCH Release 1 *Determine the isotopics concentration content of the waste gas tank in terms of the uCi/cc.
2 Determine the volume of waste gas dis-charge used in the following formul_a.
Pf vf = Pi vi where Pi, Pf, vi, and Vf represent the* initial and final p~essu~e and volumes.
3 The volume discharged to the environment is Vf - vi. Once the volume is determined, multiply the specific activities in Step 1 by the volume released.
M P82 132/02 1 5.7
LSE Dept TITLE::- ODCM - SNGS REVISION: 0 PAGE 2 OF 4 0
SECTION: , 5 .5 GASEOUS EFFLUENTS - CURIE~ATE: 10/1/82 APP 0 BY:
Instruction for Estimating Continuous Releases Under Normal Conditions R-16 Channel NOT In Alarm Step # Action l Estimate the quantity of radioactive materials discharged at least once each month under normal conditions using Chemistry Procedure PD-3.8.016. Requests from the Chemistry Department the results
- of the monthly grab sample of the plant vent.
2 Ensure that the grab sample taken is a routine~grab sample and not a special sample taken when the Rl6 channel is in an alarm state.
3 Multiply the specif tc activity in Step 1 by the volume of the continous release to estimate the number of curies discharge.
Instructions for Estimating Discharge from Abnormal ~ Re-leases When the Rl6 or R41C Channel Has Gone Into Alarm and Isotopfc-Anaiyses *Have Not Been completed Step Action 1 The Rl6 or R41C channel alarms which is an indication that releases from
- the plant vent are higher than usual.
- t is not an excessive high release rate at the initial setpoint of value 10 ,*ooo counts per minute.
2 Due to the complexity of the release spectrum, short lived isotopes with soft and/or hard radiation emmissions could be present and will make any attempt- to co-rrelate radiological re-0 leases with the Salem Technicial Speci-fications complex. In of itse~f a gr_oss radio-activity monitor. cannot be used to provide an exact quantification of a release due to varying release spectra, however, it can be used to gauge the magnitude of the release and will enable p*lant personnel to quickly determine if the release is abnormally high when no otherinformation is immediately available.
M P82 132/02 2 5.8
LSE Dept TITl.~~ '
.ODCM - SNGS REVISION! 0 PAGE 3 OF 4
'* SECT10H:
' 5 .5 GASEOUS EFFLUENTS - CURIES.t..TE: 10/1/82 APP'D BY:
Action 3 Use the decision table beiow after the
'Rl6 or R41C channel goes into alarm.
':'able l Rapid Decision Table Gaging Compliance With SNGS-TS Rl6 or R41C Action
- a. Below Technical Specification <10,000 cpm None
- b. Detail Technical 10,000- Take plant vent grab Evaluation Require 500,000 cpm sample and analyze promptly. Assume that
- c. Probably in excess R41C and Rl6 response of Technical Spec. >500,000 is proportional to activity disc~arge 4 Estimate the instantaneous release rate by following formula.
X E
= ,
Con*c. Rl6 cpm Conv. Const.
in Channel cpm/uCi/ cc/
uCi/ cc Response (See PD 3.8.016 Step #5)
= X
- Flow Q Vent Flow cc/sec Instructions for Estimating Discharges fro~ AbnQrmal_
Releases When the Rl6 or R41C Channel Has Alarmed and Isoto-pic Analyses Has Been Completed.
Step # Action l The Rl6 or R41C channel goes into alarm and chemistry ha~ obtained and completed their analysis of a grab sample of the plant vent.
M P82 132/02 3 5.9
LSE. Deot
- T1Tl.E: .. ODCM - SNGS REVISIOIU 0 PASE 4 OF 4
SE~'no.H: 5.5 GASEQUS EFFLUENTS - CURIESo~T~ 10/1/82 APP'O BY:
Step # Action 2 If the Rl6 or R41C channel remains constant, multiply the activity concentration by the vent flow rate, or release volume. All results obtained by isotopic analysis supercedes any early estimates developed prior to the receipt of grab sample results.
3 If the Rl6 or R41C channel increases significantly the isotopic mix could have changed significantly. An additional grab sample should be taken *
..:~ =...-::_ ____ -~ - -~ -- -- - - - -- - - -- -- ~--- ~-=--- ----=- -..=._ - -- -- -*--- - -
- - - - --- - - - - - --~
M P82 132/02 4 5.10
1, 11 i :j 1,1
~!
- I ;
I I* I I
1, TABLE 5.0 .
! ' li DOSE FACTORS FOrt NOBLE GASES ANO OAUGllTERS*
[*! 11 1
To~'al I Dody Gamma Atr ._ Beta Air Dose '!Factor Skin Dose Factor Dose Factor *
- Qose Factor I ;1 K~I L H .;* N (mr ad/ yr per 11C 1~ j mr a d/..._t.;_r-i.P. .;;;.e.;_r_.1'--aC~l/L-"m"--3..£..)
Radlonucl 1de (mrem/yrjj per 11Cl/m 3 ) (mrem/yu!r 1aC t /m 3) 1
. 1 1 :i Kr-83m 7.56E-02'* l
- 93£.tOl 2.08Et02 I' 11 Kr-ll5m l. l:71H03 II l.46£t03 1 .23E-t03 l.97Et03
[ I Kr-05 l.61~-tOJ 1. 34E tOl 1. 72Et0l l. 95Et0l I 1 11 Kr-07 5.92Et03 9.73E-t03 6. l7Et03 l .03E-t04 r: 'I 9\
Kr-08 Kr-09 Kr-90 l.~7Et04 l
- 66Ht04 1
I' l ..56E t04 1
Ii lj I
2.37Ei03 l .Ol H04 7.29003
- l. 52E+04
- l. 73£t04 l.63£t04 2.93£t03
- l. 06£-t04 7.03£-tOJ Xc- lJlm 9. 1 15~ tOl 4.76£i02* l. 56E-t02 1. l 1£t03 Xe-133m 2 .i5J E-t02
. I 9.94£t02 3. 27Et02 l. 48£ t03' 1** ,i Xe-133 2 *. 94£ -t02 3.06E-t02 1.53Eto2 l. 05E-t03 I: II Xe-l35m 3~:12~t03 7.llE+02 3.36£t03 7.'.19Et02 Xe-135 l .101 f t03 l.86Et03 l.92Et03 2.46£-tOJ Xe-137 lj42£+0J 1.22Et04 l. 51 EtOl L27E-t04 I ,I Xe-130 0.;03Et03 4~13Et03 9.21Et03 4.75Et03 1,11 :1
/\r-41 01.04:£ tffl 2.69E-t03 9.30Et03 3.20Et03
!' 1]
- The listed dose tad.ors are for radlonucl1des that may be detected 1n gaseous effluents.
- 7. 56E-02 "' 1. 56 x lo:-- 21'1.
1** i I'* Jj
- .:* :1
- 11. !I I ~W-~**""'1*'l!!§i9it4A4ift!W!Wl!?liWIUIH!!NM'§ ~.*: r-~~~*"1litt'~\!7iA_~*<>it%1tct;CE1;-aJ.ifuiJ£i5&&¥MMHYMW!£~~-w.:~~~~
_ J
La E Dept
\ITU: ,,* ODCM-SNGS "EVISIOHl 0 PA.SE OF SECTION: 6 .} I-131°, TRITIUM & PARTICULATfoS._TE: 10/1/82 0
., APP D Ill'!
RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS (NON-NOBLE)
DOSE ODCM - INSTRUCTION I-6.1 SNGS TS 4.11.2.3
. s2ecification:
The dose to a MEMBER of the PUBLIC from I-131, H-3 and particulate with half-life greater than 8 days from each reactor at the ~ite boundary will be limited to the values below:
Summary of Limits.
Dose Calendar Calendar Calendar To Quarter Year Year "
Any Organ 7.5 mrem 15 mrem 75 mrem a) The EPA, 40 CFR 190, 12 month values apply to all reactors at the site. All other values appiy tc)each .
nuclear unit. The EPA limits include liquids and--ga8"es.
Discussion:
- 1) Cumulative doses will be determined at least once per _31 days.
- 2) The cumulative dose for the month, quarter, and year will be mainta~ned.
- 3) The dose will be determined using the formula below~
I M P79 18 29/19 6,.1
L8E Dept r
TITLE: ,*,* ODCM-SNGS REVISION! 0 PAil E OF SECTION: 6. i I-131", TRITIUM & PARTICULATES.TE: 10/1/8 2 APP'O BY:
Dose Equations The dose to the public from r~dioiodine, particu-lat~s and non-noble gases with half-lives greater than 8 days shall be determined to be the sum of the terms which follows. This analysis assumes that the
-.. public drinks milk from the closest dairy farm and also breathes the air at this same location.
DT = 3.17 x io-8 * ~ih*WH + ~g*WG*Q~*DU vcl . .
Where* Du is the dose uncertainty factor of 1.25. Wh is the inhalation pathway average dispersoin fac-tor. Wg is the milk and ground pathway average .
depletion factor; Rih and Rig are dose conversion factors.
METHOD:
INSTRUCTIONS FOR DEMONSTRATING THAT I-131, PARTICULATES AND NOBLE GASES ARE.WITHIN SPECIFICATION.
Action 1 ~Determine activity concentration of I-131, particulates and other non noble gases discharged with half life >,8 days.
2 Using Table 6 .1. locate the Ri term for each individual isotope found.
3 For "~h" and "Wg" te2ms use values_ of 5.4E-8 sec/m a~d 2.lE-10/m which are the histor-ical X/Q and D/Q relative concentrations in "the NNE sector according to Supplement *3 to the Safety Evaluation Report of the SNGS ..
4 Determine the number of microcuties' discharged.
5 Substitute the R, W, and Q terms info the equations provided .
M p79:*18 29/20 6.2
)
LB E Dept TITLE: ... ODCM-SNGS . REVISIOIU
- o. PAGE 1 OF 2
10/1/8 2 APP'o sr:
- RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS-(NON-NOBLE)
DOSE RATE .
ODCM - INSTRUCTION I-6.2 SNGS - TS 4.11.2.1.2 Specification:
The release rate of radioactive iodines and particulates must be restricted as provided in Specification 3.11.2.1 Summary Dose Rate Limits To Limit Dose Protect Rate To Any organ or thyroid 1,500 mrem Discussion: ,,..*
The equation to use is as follows:
Pi Wgo < 1500 mrem/yr assuming all I 131 then Q = 7.14 uCi/sec Method:
Instructions for Demonstrating Iodine 131, Particu-lates and Non-noble Gases are* within Limits Action \
1 Determining isotopic composition of the iodine 131, particulates and other nbn noble gases discharged with half lives > 8 -days.
2 Using Table 6.2 which lists the conversion
~.
factors locate the "Pi" term for each indi-vidual isotope of interest.
I M P79 18 29/20.1 6.3
- TITLE:
L8E Dept
. ODCM-SNGS REVISION~ 2 OF 0 PAllE sEcnpH.:6 .f I-1.31, TRITIUM & PARTICULATE~TE: 10/1/82 APP'D B't'!
Action 3 For the 11 w8 " and "WG" terms use 5. 4E-8 sec/m3 and 2 .1E-10/m2 which <._',.:? the historical
- x/Q and D/Q relative concentration in the NNE sector according to Supplement 3 to the Safety Evaluation Report of the SNGS.
4 Determine the total microcuries discharged over the reporting period
- 5 Substitute the P, W, and o*terms
- into the equations provided. *
- -- - ---~ --- ---
- - - - --- -- - -- - - - - - - ~---
M P79 18 29/21 6.4
I LaE Dept .
. TITLE: ODCM-SNGS REVISION~ 0. PA6E OF sEcnoN:6 .! I-131, TRITIUM &
I PARTICULATE~A.TE: 10/1/82 APP'O BY:
RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE.FOR EQUIPMENT OPERATION ODCM - INSTRUCTION I-6.3
. SNGS - TS 4.11.2.3 Specification:
If the calculated dose exceeds 0.625 mrad for gamma radiation and 1.25 mrad for beta radia-*
tion during any calendar quarter, then the gaseous radwaste treatment system shall be operated.
Discussion:
To account for the isotopes which may not be identified until after the release has been made, a dose uncertainty factor of 25% of the applicable limit has been added. If operat-ing experience indicates that the 25% factor
- is not conservative, then the dose uncer-tainty factor will be changed.
The following are gaseous radioactive waste management systems for which credit may be taken:
i) Waste hold-up for decay ii) Iodine and particulate filtration The followin~ are not gasedus radwaste management systems:
i) Engineering Safety features such as in-ternal atmospheric Clean-up ii) Elevated vents M P7 9 18 2 9 I 2 2 6.5
TABLE 6. 1 P (I) ,. DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATES IN GASEOUS EFFLUEN'rS Pih Pig
!NHALATION MILK AND GROUND
( MREM/Y R PER ( M2
- MREM/Y R PER RADIONUCLIDE UCI/M3) UCI/SEC)
H 3* 6.5E02 2.4E03 p 32 2.0E06 7.9E10 MN 54 2.5E04 1.4E09 FE 59 2.4E04 4.5E08 co 58 1. 1 E04 4.1E08 co 60 3.2E04 2.2E10 ZN 65 6.3E04 1.3E10 RB 86 1. 9E05 1.0E10 SR 89 4.0E05 6.0E09 SR 90 4. 1 E07 7.4E10 y_ 91 7.0E04 3.6E06 ZR 95 2.2E04 2.5E08 NB 95 1.3E04 2.4E08 RU 103 1.6E04 1.1E08 RU 106 1. 6E05 4.2E08 AG 11 OM 3.3E04 1. 2E 1 0 CD 11 SM 7.0E04 2.8E07 SN 123 2.9E05 2.3E09 SN 126 1.2E06 3.2E10 SB 124 5.9E04 9.1E08 SB 125 1.5E04 2.4E09 TE 127M 3.8E04 6.5E08 TE 129M 3.2E04 7.2E08 cs 134 7.0E05 4.4E10 cs 136 1.3E05 3.0E09 cs 137 6. 1 E05 4.5E10 BA 140 5.6E04 1.4E08 CE 1 41 2.2E04 2.0E07 CE 144 1.5E05 1.4E08 I 1 31 1 .-SE07 5.2E11 I 133 3.6E06 4.8E09
- FOR TRITIUM, THE UNITS OF THE DOSE PARAMETERS ARE MREM/YR PER UCI/M3. FOR ALL PATHWAYS.
NCA:peg 11/17/82 M P80 68 14 6.6
~-----,-------------
TABLE 6.2 P(I), DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATES IN GASEOUS EFFLUENTS Pih Pig INHALATION MILK AND GROUND
. ( MREM/Y R PER ( M2
- MREM/Y R PER RADIONUCLIDE UCI/M3) UCI/SEC)
H 3* 6.5E02 2.4E03 p 32 2.0E06 1.6E11 MN 54 2.5E04 1
- 1EO9 FE 59 2.4E04 7.2E08 co 58 1.1 E04 5.8E08 co 60 3.2E04 4.6E09*
ZN 65 6.3E04 1.8E10 RB 86 1.9E05 2.1E10 SR 89 4.0EOS 1.1E10 SR 90 4.1E07 1. OE 11 y 91 7.0E04 5.9E06 ZR 95 2.2E04 3.5E08 NB 95 1.3E04 3.8E08 RU 103 1.6E04 1
- 6E08 RU 10 6 1.6E05 3.0E08 AG 11 OM 3.3E04 1
- SE 1 0 CD 11 SM 7.0E04 5.2E07 SN 123 2.9E05 3.7E09 SN 126 1.2E06 1.1E10 SB 124 5.9E04 1.4E09 SB 125 1.5E04 9.1E08 TE 127M 3.8E04 1.0E09 TE 129M 3.2E04 1.3E09 cs 134 7.0EOS 5.6E10 cs 136 1.3E05 5.7E09 cs 137 6.1E05 5.0E10 BA 140 5.6E04 2.6E08 CE 1 41 2.2E04 3.2E07 CE 144 1.SEOS 1.6E08 I 1-3T 1.5E07 1
- OE 12 I 133 3.6E06 9. 6E09.
- FOR TRITIUM, THE UNITS OF THE DOSE PARAMETERS ARE MREM/YR PER UCI/M3 FOR ALL PATHWAYS.
NCA:peg 11/17/82 M P80 68 15 6.7
LaE Dept
- TITLE: ~DCM - *sNGS REVISIOHI 0 PAGE OF sEcT10H: 7 .0 ENVIRONMENTAL MONITORING DATE: 10/1/82 0 APP 0 BY:
RADIOLOGICAL MONITORING MONITORING PROGRAM ODCM - INSTRUCTION I-7.1 SNGS-TS 4 .1. 2 .1 Specification:
The radiological environmental monitoring program will be conducted in
- accordance with Tabl.e 3 .12-1.
Discuss ion:
The potential dose contributin to the public for radionuclides detected in environmental samples is calculated using the general guidelines from Reg. Guide 1.109.
The radiological environmental monitoring program will be conducted in accordance with the attached tables and in accordan¢e with specifica-tion 3/4.12 of the Salem Technical Specification.
- (
;;:~=--=-=-=-=-=-----==-=-- - ---
- --=-=- -=--= -::--_---;; ; -;;---- -
-~ ~----
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M P80 55 10/18 7.0
Fig 7-1 ON SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 0
SCALl Of MILIS
____________ __;__ ________ ~------......,_._
.~
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sarrp1er. S3nple mlJ.octa:'i H e;e.ry vffi<. a1crg with filter !-,]
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3H3# 110 mi NE of Statim G:rrrra oo:r1 (GS) cµ:rtedy - ,. ,. "D 16El 4.1 mi~ oE vent cocp:site (OC) "Q "Q
0 Ill I-'
- Crntrol Statim 0
- Gmra ~try shall te J;Erfonra:l if QD'.B3 J::a:a exCEEd3 ten t:im:s tre cn1trol statim valte.
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- m # !:(6 J; miles NE of vent o:np:Bitro ard seale:i in a ~
H 11 i:
11 plastic ta] at ea:h la:atiDn* z 11 GJ 3H3 # 110 ljmi NE oE statim 111 A sarple will re rol:Jectaj I' I frou ea:h la:ation are fM3ry 0 ~
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wi 8.7 mi~ of ~nt 3 ym.rs >-i Ill
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...... 0 11*
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' 1'1
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~o 13F2 6 .!;> miles Wof \ent ..........
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lfi31 # l~.8 miles l'NI] of \ent ..-<
U1 1G3 # 18 .5 miles N of \ent 0
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- - z
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llAl ~tely650 ft t"1 StJ Gf vent :3:
0 zH (a) S 'Tu.o gallm sarple to m mllecta:1 Gama scan m::::nthly -
1-3 u lA::l # 2-1/2 mi W3W of \Bnt nonthly pIDJidirrJ wint:Eric:in;J 0 o:::mitias alk:w sarple ml1ectic:n H-3, 01 qwrterly oorp::sitES ~
R H F z G1 A 16Fl 6.9'mi N of vent c C&D cmal 0 :ID E ,. Pl
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0 (b) G '-...
...... 0 R 481 en site '-...
0 'Tu.o gallm grcb sarple is mllec:t.E.d
- Cf:)
N u tconthly.
- N 3El # 4.5 mi NE of vent Gama scan - OC D H-3 aialysis are d:re rronthly.
..._ en (c) D 0 Pl R 2F3 (raw)
- Sa1an W:lter Co.; 50 ml al:iqu:t: is tal<a1 daily Ch:s5 l:Bta m::::nthly "'-c I 8 mi t>i'£ of \Bnt an mrp:Eited to a nonthly N sarple of Tho gallaE Gama scan - OC "'
0 K ....
I H-3 01 qwrterly oorp::site N
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PlfilW\Y SOO'ICN GIE . mr FCTICN MEilID Ul I-'
- v. lQll\TIC Ul B 7El .1 Ini wof M:rl Ibi;se O:a:k; E 4 .5 mi SE oE <vert N
T l2Cl # ~1/2 mi WW of vent A mnth:s sarpJe crrs:istirg Gama ~ cf each sarple :::;:
0 H cf h:nthic OOJ3l-iigcs ad rem:imrually; z 0 rosx:iate:l sa::l:irrent is ~n H t-3 s S3nianrually 0
~
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<vent 0 JO VI. :J:N:E3I'ICN >
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.......z 0
(a) M 2F4 6.3 mi !'NE oE vent fron each fann senim::nthly. 1-131 m::nthly, '-..
I-' 0 I Cbl1£cte:'l va:kly if calru- '-..
L 5Fl 6.5 mi E oE vent late.j d::re exCEle'.ls 15 mran 1-131 w:ekly if cal01Jatro 00 N
K
- to child's tlyroid. d:Ee exCEErls 15 rrran m 14Fl S.5 mi WW oE vent mild 's tf¥Did.
- r;_i # 16.6 miles NE oE <vent "O
"O
-o_ II>
0 (b) F llAl Clltfall area; 6:£) I 9'J Tho ke1 s:irrpJes.. cf fiffi Gmm s::an cf a:lible p:rtion oo -..J I of vent ai.~ re3le::1 in plcstic mllect.im s lJ:l # 2- l/l mi W3W of 1.ent tag or j:3r cn:1 frozEn ...
0 H seniannually er vh:ln m recs::n
- Cmtrol Statim
i' JI i,' i r:
[il :1 TABIB 7-1
!:: ;I 111 i r*1 i
!* 11
!'* !I iq 11 1:1 i1 I. i *
'!ID keys s:nples c£ crcb Gmm. s:B1 cf e:lible p:rt:ion m (c) C llAl
- I ,Clltfall area; 65() 1 9tJ R I cl vent are realej in a plcstic rollect.irn
~
A
. I: 11 taJ or ~ am froz.En B I: *I saniannually er W'en :s:
in 0
!*' 11 ffics::n z H
l:!Cl * :
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11 Aftfticial Islard Cl)µ:Bite 1-'3 0
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!.:~t 0 lll
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- I;. ip .2 milBs N of vent 11 Sarple:> are cnllecta:i d.ir.irq tl--e mmal l:ar'\est RDioio::line retermination Qf ~**
i5 z
ffi
- 41.45 xrl r-NE of vent 0
\lE[.Effi- 2El s=as::n, SXl]a:j in plcstic, green leafy Va;JEtcDlES 00 ..........
TJCN I' I1 am £rozEn if p:ri.Etable. cnlla::tion ~o 2Fl :;. 3i mi r-NE of vent Mficient. satple :is ml- CXl .
N
- 1. :i . la:::t:OO tn yield 500 grars i,: 11 of dry ~ight
- 1 > "II "II >
I' I 0
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f I i CXl 11 !I 0
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~ire of EBhary ~
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E XXX# ;) ~ sire aE e:>b.my, :s:
0 I* ~s mi fmn wnt z
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- ' CD
- = 'Jhis s:nple is 9..Jbjoct tn, :a'19i1abilitif c£ slaitj1tered CON 0
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