ML18081A718

From kanterella
Jump to navigation Jump to search
Offsite Dose Calculational Manual
ML18081A718
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/31/1979
From:
Public Service Enterprise Group
To:
Shared Package
ML18081A716 List:
References
P79-23-02, P79-23-2, NUDOCS 7912060339
Download: ML18081A718 (44)
v • d • e


Text

'I I. I I 0 ODCM OFFSITE DOSE

  • 1 PSEG The Energy People CALCULATIONAL MANUAL I

I SALEN NUCLEAR GENERATING STATION UNITS NO. 1 & 2 I OPERATING LICENSE NOS.

DPR- 70 AND DPR-I I

I I

I - NOTICE -

I THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY I BRANCH 016. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST DECEMBER 1979 I ~~:E~~~/~rtSONNEL.

,, DEADLINE RETURN DATE Ltf" 1l..2Lo *1-"l i ** 1GTO 1'l1'20~D318~

RECORDS FACILITY BRANCH

.I

  • I I
I . -*~ ,  ;

I

  • , ** * -*; -'-- **-* ¥.

I I OFFSITE DOSE CALCULATION MANUAL (ODCM)

I UNITS 1 AND 2 OPERATING LICENSE NO. DPR-70

\I AND OPERATING LICENSE NO. DPR-I SALEM NUCLEAR GENERATING STATION PUBLIC SERVICE ELECTRIC AND GAS COMPANY I

I I

I I

I I

.I P79 23 02 I

I I TABLE OF CONTENTS I Chapter

1.0 INTRODUCTION

Page 1.1 I 2.0 IMPLEMENTATION 2.1 3.0 RADIATION INSTRUMENTATION 3.1 I 3.1 Effluent Monitor Setpoints I 4.0 3.2 Derivations LIQUID EFFLUENTS 4.1 I 4.1 Limits or Restrictions 4.2 General Guidance on Dose Calculations I 4.3 Dose Equations 4.4 Instructions I 4.5 Radwaste System Operation I 5.0 GASEOUS EFFLUENTS (NOBLE GASES) 5.1 Limits or Restrictions 5.1 I 5.2 .General Guidance on Dose Calculations 5.3 Dose Equations I 5~4 Instructions 6 .i I 6.0 IODINE, PARTICULATES AND NON-NOBLE

  • GAS AEROSOLS 6.1 Limits or Restrictions I 6.2 Geneial Guidance on Dose Calculations I 6.3 6.4 Dose Equations Instructions I 6.5 Operation of Radwaste Equipment I

ODCM I SNGS-1&2 P79 23 03 i I

I I

I

1.0 INTRODUCTION

I The offsite Dose Calculation Manual (ODCM) is required by the Radiological Effluent Technical Specification.

The ODCM was prepared incorporating the guidance supplied by the USNRC Effluent Treatment Branch in I their letter to all power reactors dated January 18, 1979.

I It provides additional facts and administratives con-trols to be used at the Salem Nuclear Generating Station to incorporate the principals of 10CFRSO Appendix I. This document should be used in conjunc-I tion with other station procedures and documents which are reference herein. Surveillance and calibration methods and procedures are provided in greater detail I in.the station's technical specifications and in the station's test procedures lPD-4,3001 through lPD-4.30011. All setpoints provided are those currently installed and are subject to change.

I In order to.provide reasonable assurance that 10CFR50 Appendix I limits are not violated, initial dose I estimates will assume that 8 curies of Carbon 14 is discharged annually. To assure doses remain within 10CFR50 Appendix I guidelines, the conversative un-I assumption is to increase the dose calculated by 25%.

Analysis performed to demonstrate compliance with 10CFR50 Appendix I indicates that this assumption should be conservative.

I I

I I

I ODCM SNGS_.1&2 I M P79 56/15 4 1.0 I

I

I

. 2.0 'tMPtEMENtATidN I This ODCM shall be maintained in accordance with radio-logical effluents technical specification 6.15. It s~all I be reviewed at least once a year by the Station Operation Review Committee or their designee. Temporary thanges are permitted as long as Section 6.8.3 of the Technical Specifications are compiled with. Distribution of amend-I ments will be by controlled copies.

I I

I I

I I

I I

I I

I I

I ODCM SNGS-1&2 I P79 23 05 2.0 I

I 3.0 RADIATION M~NI~bRIN~ INSTRUME~TATION I 3.1 EFFLUENT MONITOR SETPOINTS I 3 .1.1 Gaseous Effluent Setpoint Channel - 1Rl4 Gas Decay Tank Monitor I Purpose - Monitors the discharge from the waste gas holdup system and terminates discharge on high alarm.

I Location - Elevation 100, beneath the Nurnber.11 and 12 fuel handling building fan intake ducts.

I Detector - Geiger-Mueller tube I Range Interlocks

- 10 to 106 cpm waste discharge valve 1WG41 is locked close.

I Setpoint - 20,000 cpm The basis. for h6w this setpoint was derived I is described in section 3.2.

I I

I I

I I

-1 I ODCM SNGS-1&2 I P79 23 06 3.1 I

I I 3.0 RADIATION MONITORING INSTRUMENTATION 3.1.l Gaseous Effluent Setpoints (Cont'd)

I Channel - 1Rl2A Containment/Plant Vent Noble Gas Monitor I Purpose - May monitor the plant vent effluent or containment atmosphere for radioactiVTty after particulate and iodines are removed.

I Location - ~orth penetration electrical side west wall, elevation 78.

I Detector - Beta-Gamma sensitive GM tube Range I Interlocks

- 10 to 106 cpm

- Al~ six containment ventilation isolation valves (lVCl through 1VC6) are closed on I high alarm. Pressure vacuum relief valves also isolates containment.

I Setpoint - 30,000 cpm The basis for how this setpoint was derived is described in section 3.2.

I I

I I

I I

I I

I ODCM SNGS-1&2 P79 23 07 3.2 I

I I 3.0 3.1.l RADIATION MONITORING INSTRUMENTATION Gaseous Effluent Setpoints (Cont'd)

I Channel - 1Rl6 Plant Vent Effluent Purpose - Monitors all effluent exiting the plant I vent for radioactivity.

backup for charinel 1Rl2A.

Serves as a Location - Elevation 194 of plant vent I Detector. - 4 GM tubes, beta-gamma sensitive I Range Inerlocks

- 10 to 106 cpm

- None I Setpoint - 500,000 cpm The description of ho~ this setpoint was derived is in section 3.2 ..

I I

I I

I I

I I

I I ODCM SNGS-1 I

  • P79 23 08 3.3 I

1-i I

-*-- - - -- - - --- - ~ - --

3.0 RADIATION MONITORING INSTRUMENTATION I 3.1.2 Liquid Effluent Setpoints (Cont'-d)

I Channel Purpose

- 1Rl8 Liquid Waste Disposal Monitor

- Monitors all liquid radioactive discharges I Location - Inside Auxiliary Building on elevation 86 behind the Number 12 Waste Monitor Pump I Detector - Sodium-iodide crystal with PM and preamp-lifier for gamma scintillator Range - 10 to 106 cpm I Interlocks - Closes liquid waste discharge valve lWLSl.

I Setpoint - 800,000 cpm The basis for how this setpoint was derived is described in section 3.2.

I I

I I

I I

I I

-1 I ODCM S~GS-1 I P79 23 09 3.4 I

I I 3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd) i I Channel l-Rl4 Waste Gas Effluent Monitor Alarm: 20,000 cpm I Basis: The alarm will activate when the concentration reaches 37% of the Tech. Specs. instantaneous release rate I limits for noble gases. FSAR Tables 11.1-6 and 11.1-7 are used to determine the fractional noble gas releases.

I Calculations:

1. Instantaneous release rate limits for noble gases:

I A) 2. O * (Qtv

  • Kv) < 1 where Otv = the total noble gas release rate I from the plant vent in Ci/sec and Kv = the average t~tal body dose factor due to g~mma emission (rem/yr per Ci/sec)
  • I *Assuming Xe-133 is the dominent gamma emitting
  • isotope present then:

I rem/yr 0.31 Ci/s.ec I 1

< 2(0.31)

I QTv < 1.6 Ci/sec I and I where Qtv = the total noble gas release rate from the plant vent in Ci/sec.

I

-1 I

ODCM I SNGS-1 P79 23 10 3~5 I

-1 3.0 RADIATION MONITORING INSTRUMENTATION I 3.2 Derivations of Setpoints {Cont'd)

I l-Rl4 Waste Gas Effluent Monitor Lv = the average skin dose factor due to beta emissi-0ns (rad/yr per Ci/sec)~ and I Nv = the average air dose factor to gamma emissions (rad/yr per Ci/sec).

I Assuming Lv = 1.6 Kr~85 is dominent for skin dose therr rem/yr and assuming Xe-133 is dominant Ci/sec I rad/yr for air dose, then Nv = 1.3 Ci/sec I therefore:

Otv .< l 0.33 {1.6 + 1.1 x 1.3)

I Otv < 1.0 Ci/sec I which is a more restrictive limit, I 2. Maximum waste gas release flow rate = 150 ft3/min (PSE&G internal memorandum of 6-18~76).

I 3.

4.

Conversion factor = 2.8 x 104 cc/ft.3.

Weighted sensitivty of l-Rl4 for Kr-85 and Xe-133 = 5~4 x 103 cpm I uCi/cc 5.- F~action of total releases expected to come from I *gas decay tanks = O. 37 (Obtained* from FSAR Tables 11.1-6 and 11.1-7).

  • 1 I

1---~ -

I ODCM SNGS-1 P79 23 11 3.6 1*

I '

I 3.0 RADIATION MONITORING INSTRUMENTATION

3. 2 Derivations of Setpoints (Cont'd) l-Rl4 Waste Gas Effluent Monitor
6. Meter error factor~ 0.75 assumes wor~t case for meter response error of + 25% (Radiation Monitoring System Technical Manual).
7. Conversion factor= 106 uCi/Ci.

I 8. Conversion factor = 60 sec/min.

II Setpoint:

I (0.37) (1.0 Ci/sec) (106 uCi/Ci) (60 sec/min) (5.4 x 103 cpm/uCi/cc) 150 ft3/min x (2.8 x 104 cc/ft3 (0. 75) =

21,400 cpm I

Therefore, choose the nearest major graduation on the I meter face; 20,000 cpm.

I I

I I

I I

1-1 ODCM I SNGS-1 P79 23 12 3.7

I I 3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd)

I 1Rl2A Containment/Plant Vent Gas Effluent (Plant Vent Mode)

I Alarm: 30,000 cpm Basis: The alarm will activate when the concentration reaches I 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 noble gas releases.

I Calculations:

I 1. Instantaneous release rate limits for noble gases:

A) 2.0 (Qtv

  • K~) < 1 I where Qtv = the total noble gas release rate from the plant vent in Ci/sec and Kv = the average total budy dose factor due to gamma emission (rem/yr per I Ci/sec).

Assuming the fractional releases (Qt) from FSAR Table I 11.1.-7 and the respective Kiv from Tech. Specs. then:

rem/yr Kv = 0.31 Ci/sec I 1 Qtv < (2) (0.31)

I and B) 0.33

  • Qtv (Lv + 1.1 Nv) < 1 I where Qtv = the total noble gas release rate from the plant vent in Ci/sec.

I L = the average skin dose factor due to beta emission (rem/yr per Ci/sec).

I I

I ODCM I SNGS-1 P79 23 13 3.8 I

I I 3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd)

I 1Rl2A Containment/Plant Vent Gas Effluent (Plant Vent Mode)

I and Nv = the average air dose factor due to garruna emissions (rad/yr per Ci/sec).

I Assuming the fractional releases (Qi) from FSAR Table 11.1-7 and the respective Liv and Niv from Tech. Specs, then:

I rem/yr L = 0.82 Ci/sec I and rad/yr N = 1. 7 Ci/sec I

I therefore:

1 0.33 (0.82 + 1.1. x 1.7)

I < 1.1 Ci/sec which is the more restrictive limit.

I 2. Maximum plant vent flow rate = 1.2 x 105 ft3/min (PSE&G internal memorandum of 6-18-76).

I 3. Conversion factor = 2.8 x 104 cc/ft3 cpm

4. Sensitivity to Xe-133 = 2.1 x 106 uCi/cc I (Determined from initial radiological calibration using procedure lPD 4.3.004).
5. Meter error factor= 0.75 assumes worst case for I meter response error of + 25% (Radiation Monitoring System Technical Manual).

I 6. Conversion Factor= 106 uCi/Ci.

I I ODCM SNGS-1 M P79 62 04 4 3.9

I I 3.2 Derivations of Setpoints (Cont'd)

7. Conversion factor = 60 sec/min.

I Set point:

I ( 1. 1 C i ) ( 1 0 6 u C i ) 6 0 s e c ( 2

  • 1 x 1 0 6 c pm sec -cl ffiTi1 uC1/cc

) (0

  • 7 5 )

= 29,700 cpm I (1.25.x 1-05 ft3/min) {2~8 x 104 cc/ft3)

Therefore choose the nearest major graduation on the meter face I o f 3 0 , 0 0 0 c pm I

I I

I I

I*

I I -

1 ODCM SNGS-1

  • 3.10 I P79 23 15 I

I I 3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd)

I 1Rl6 Plant Vent Effluent I Alarm:

Basis:

500,000 cpm The alarm will activate when the concentration reaches the Environmental Tech. Specs. instantaneous I release rate limits for noble gases (Salem Environmental Technical Specifications Section 2.3.3.a.l). FSAR Table 11.1-7 is used to determine I the fractional noble gas releases.

Calculations:

I 1. Instantaneous release rate limits for noble gases:

I A) 2.0 (QTv Kv) < 1 where QTv = the total noble gas release rate from the plant vent in Ci/sec and K = the I average total body dose factor due to ganuna emission (Rem/yr_per Ci/sec).

I Assuming the fractional releases (Qi) from FSAR Table 11.1-7 and the respective Ki v

from Tech. Specs. then:

1- Kv = 0.31 rem/yr Ci/sec I. Ot v

< 1

) ~(0-.-3-1 )

( -2.....

I and B) 0.33 QTv (L + 1.1 Nv) < 1 I where Ot = the total noble gas release rate from thevplant vent in Ci/sec.

I I

I ODCM SNGS-1 M P79 62 04 5 3.11 I

I

I 3.0 RADIATION MONITORING INSTRUMENTATION I 3.2 Derivations of Setpoints (Cont'd)

I l-Rl6 Plant Vent Effluent Lv = the average skin dose factor due to beta emissions (rad/yr per Ci/sec).

I and Nv = the average air dose factor to gamma emissions (rad/yr per Ci/sec)

I Assuming the fractional releases (Qi) from FSAR Table 11.1-7 and the respective Liv and Niv from Tech. Specs then:

I rem/yr Lv = 0.82 Ci/sec I and rad/yr I Nv = 1. 7 Ci/sec I 1 0.33 (0.82 + 1.1 x 1.7)

I Qtv 1.1 Ci/sec which is the more restrictive limit.

I 2. Maximum plant vent flow rate= 1.25 x 105 ft3/min {PSE&G internal memorandum of 6-18-76).

=

I 3. Conversion factor 2.8 x 104 cc/ft3 cpm

4. Sensitivity to* Xe-133 = 3.6xl07 uCi/cc I

5.

(Determined from initial radiological calibration by using procedure lPD 4.3.008).

Meter error factor - 0.75 assumes worst case for meter response error of + 25% (Radiation Monitoring System Technical Manual)~

I 6. Conversion factor 106 uCi/Ci.

7. Conversion factor = 60 sec/min.

I I ODCM SNGS-1 I P79 23 17 3.12 I

~----:------------------~-------------

_I I 3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd)

I 1Rl6 Plant Vent Effluent Setpoint:

I Ci uCi sec

  • cpm (1.1 sec) (106 Ci) (60 ffiin) .(3.6x107 UCT/cc) (0.75) =-509,ooo cpm I (l.25~105 ft3/min)* (2.Bx104 cd/ft3)

Therefore choose the nearest major graduation on the meter face of I 500,000 cpm I

I I

I I

I I

I I

~

ODCM I SNGS-1 M P.79 62 04 6 3.13 I

I

I

,- 3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd) 1 l-Rl8 Liquid Waste Disposal Monitor Alarm: 800,000 CPM is permissible if and only if MPCw is I greater than 2.5 x lo-5 uCi/cc.

Basis: This device monitors a liquid waste stream before it is diluted by the circulating water and released to the - environment. Section 3; 11. 1. 1 of the - Tech.

Specs. requires that the MPC not be exceeded. The alarm will a_ctiviate when the concentration through the monitor reaches a value where the resultant.

concentration in the dilution water will exceed. the MPCw for an historical mixture will be- used as-an example.

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 TR #150).

CPM

2. Sensitivity of monitor is 2.9 x 107 uci/cc as calculated and documented iri the original* _calibration -of the - Rl8

-I 3.

detector based on iPD4.3.001.

Flow rate through the liquid radwaste discharge line of 80 GPM.

I 4. Meter error factor= 0.75 assumes .worst case -for meter response of +25% (Radiation monitoring system technical I 5.

  • manual).

_Flow rate-of 185,000 GPM assuming operation of one circulating -water pump @ full flow. If a procedure is

-1 ',written to assure both circulating water pumps are operating a value of 370,000 GPM may be used (two.pumps discharge to a single discharge line).

_ 6. , Throttling factor of 2 should be -used is the flow rate

- through the sampler* is less than 40 GPM.

I Calculate the setpoint as-follows:

- - ---Setpoint:

= MPCw (Rl8 sensitivity)(#circulators)(circulator flow rate)(meter error)

-I (Pump speed) (throttle error (if any))

ODCM SNGS-1 M P79 6204 7 3.14

I Method of Arriving at Variable Setpoint l-R-18 Liquid Waste Disposal Monitor (Cont'd)

Example uCi CPM (2.5 x lo-5 cc * (2.9E7 uCi/cc * (1) * (185,00 gal) * .75 + l.01E6 CPM min

_80 gal

  • 2 min Select the closest value other than ful scale or 800,000 CPM where MPCw is calculated as:

MPCw = 1

~~%~A~~~---~-+---~--~~%.,..-B~~.-.-.---.-.-.-.-.-etc.

I* Therefore, choose the nearest graduation on the meter face less than the full scale.

I I

I I

I I

I I ODCM-I SNGS-1 M P79_ 62 04 8 3.15 I

I

3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd)

CHANNEL 2R41C Plant Vent (Noble Gas)

INSTRUMENT NO. RA-1.0155-2 LOCATION Elec. Penetration Area Elevation 100, columns Cl9A C20A DETECTOR Photomultiplier Tube, Beta Scintillator INTERLOCKS 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) l.1E5 cpm from Sr90 source number 237P c) 1. iE5 cpm from Sr90 source number 2370 ALAR.1-1 4.89E05 CPM WARNING l.10E04 CPM ALARM SETPOINT BASIS: The alarm will activate when the concentration reaches the instantaneous release rate limits for noble gases The detector utilized is a beta scintillator arad 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 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

  • Qv < 500 mrem/yr 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).

Kv = 2.94 Eo2 mrem/yr uCi/m3 ODCM SNGS-2 M P79 63 02/1 3.16

I ASSUMPTIONS AND CALCULATIONS: (Cont'd) 2R41C I then:

I and Ov < 0.77 Ci/sec B. The Skin dose must be less than 3 rem as follows:

I [L +1.1 M] X/Q < 3000 mrem/yr Lv = the average skin dose factor due to beta emissions I (mrad/yr) per uci/m3 and Mv = the average air dose factor to ganuna emissions I (mrad/yr per uCi/m3)

For Xe-133 the dose factors are as follows:

'I and Lv Mv

=

=

3.06E02 3.53E02 mrem/yr uci/m3 mrad/~r uci/m I Qv < 3000

[3.06E02 + (1.1) (3.53E02)]* [2.2E-6]

I therefore:.

I Qv < 1. 96 Ci/ sec 0.77 Ci/sec is more restrictive limit than the 1.96 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 cpm
4. Sensitivity to 133xe = 3.75x107 uci/cc I (Determined from initial radiological calibration by using Victoreen procedure AT-65 on 12/12/78 with 3.39 x lo-2 uCi/cc of Xe-133.)

I 5. Conversion factor = 106 uci/Ci.

6 . . Conversion factor = 60 sec/min I 7. X/Q = 2.2E-6 sec/m3 ~hich is the historical highest calculated annual average relative concentration.

I 8.

(USNRC, SER SNGS - Unit 2)

In sampler background = 20 cpm (Victoreen procedure AT-65)

  • I ODCM I SNGS-2 M P79 63 02/2 3.17

I

,. ASSUMPTIONS AND CALCULATIONS=. (Cont Id) 2R41C Setpoint: Alarm Ci uCi sec I (o.7-=r-sec) (106 er-) (60 minT (3.75x107) = 489,407 cpm (1.25xlo5 ft3/min) (2.832xlox4 cc/ft3)

I Therefore, dial in a septoint of 4.89E05 cpm WARNING SETPOINT BASIS: The alarm will activate when the concentration reaches Ii a fraction of the Technical Specifications quarterly release rate limits for noble gases. The alarm/trip setpoint will be set to prevent the air dose from I gaseous effluents form exceeding 5 mrad due to gamma emitters and 10 mrad from beta .emitters during any calendar quarter from each. reactor at the site.

I (l/3.15E7)

  • M
  • x
  • Q Q < Smrad (.equivalent to lOmrad) quarter yr I (l/3.15E7)
  • N
  • x
  • Q Q < lOmrad (equivalent to 40mrad) yr where M, N, x and Q are defined in the ODCM I Q By solving for Q and dividing by the number of seconds I 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.

I Setpoint: Warning cpm (l.73x lo-2ci/sec) 106 uCi/Ci) (60 sec/min) *3.75x107 UCI/cc = 10,996 cpm I (1.2sx105 ft 3/min) (2.832x104 cc/ft3)

I Therefore, dial in*a setpoint of l.10E04 cpm t

I I

I* ODCM SNGS-2 I M P79 63 02/3 3 .18

3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd)

CHANNEL 2Rl6 Plant Vent (Gross)

INSTRUMENT NO. RA-8346-2 LOCATION Plant Vent Elevation 195 DETECTOR* Photomultiplier Tube, Beta Scintillator INTERLOCKS CONTROLLED None LOOP NO.

I 4 INSTRUMENT RECOMMENDED SETTINGS

  • 1 CONF =

CTTIM =

0.90EO 3.00El DDBND FAIL

= 1. 41E3

= O.OOEO II HIGH VOLTAGE ADJUSTMENT Set H.V. (test pt.) to 9.7 volts or adjust H.V. to obtain either of the following values:

I a) b)

3.2E5 cpm from Co60 source number 237D l.1E5 cpm from Sr90 source number 237P I ALARM c) l . lES cpm from Sr90 source number 2370 4.57E05 CPM WARNING 1. 03E04 CPM I ALARM SETPOINT BASIS: The alarm will activate when the concentration reaches

  • I 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, I 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 I radiation setpoint.

ASSUMPTIONS AND CALCULATIONS I 1. The ODCM limits the instaneous release rate for noble gases:

Ii A. The whole body dose must be less than 0.5 rem as follows:

Kv* X/Q

  • Qv < 500 mrem/yr where Ov = the total noble gas release rate from the plant vent in Ci/sec and Kv = the average total body dose I factor due to gamma emission (mrem/yr per Ci/sec).

mrem/v I Kv = 2.94 Eo2 uci/m I* ODCM SNGS-2 I M P79 63 02/4 3.19

I ASSUMPT:[ONS AND CALCULATIONS: .(Cont'd) 2Rl6 I then:

av < 0.77 ci/sec I and B. The skin dose must be less than 3 rem as follows:

[L +1.1 M] X/Q < 3000 mrem/yr I Lv = the average skin dose factor due to beta emissions (mrad/yr) per uCi/m3 I and Mv = the average air dose factor to gamma emissions (mrad/yr per uCi/m3 I For Xe-133 the dose factors are as follows:

mrem/yr

=

3.06E02 uCI/sec/m3 and mrad/~r I = 3.53E02 uci/m Qv < 3000 I therefore:

[3.06E02 + (1.1) (3.53E02)J*[2.2E-6]

I Qv < 1. 96 Ci/sec 0.77 Ci/sec is a more restrictive limit than the 1.96 Ci/sec.

I 2. Maximum plant vent flow rate = 1.25 x 105 ft3/min (PSE&G internal memorandum of 6-18-76)

I 3. Conversion factor = 2.8 x 104 cc/ft3 cpm

4. Sensitivity to 133xe = 3~50x107 uCi/cc I (Determined from initial radiological calibation by using Victoreen procedure AT-65 on 12/12/78 with 3.39 x io-2 uCi/cc of Xe-133.)

I 5. Conversion factor = 106 uCi/Ci.

6. Conversion factor - 60 sec/min I 7. X/Q = 2.2E-6 sec/m3 which is the historical highest calculated annual average relative concentration.

I 8. In sampler background AT-65).

= 22 cpm (Victoreen Procedure I

I ODCM I SNGS-2 M P79 63 02/5 3.20

--- - -ASSUMPTl0Nfr-AND- E!AL-CUL~TTONS:- (-Cont-' d)--2Rl-6 Setpoint: Alarm Ci uCi sec (0.77sec)(106 cTJ (60 minm.sox107) = 773,915 cpm (l.25xlo5 ft3/min) (2.832xl04 cc/ft3)

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 will be set to prevent the air dose from gaseous effluents from exceeding 5 mrad due to gamma emitters and 10 mra:d from beta emitters during any calendar quarter from each reactor at the site.

I (l/3.15E7)

  • M
  • x
  • Q Q < *5mrad (equivalent- to lOmrad)
  • quarter yr I (l/3.l-S#7)
  • N
  • x
  • Q Q < lOrnrad (equivalent to 40mrad) yr I where M, N, X and Q are defined in the ODCM Q

I By solving for Q and dividing 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 1. 73E-2 Ci/sec I for each.reactor at the site.

Setpoint: Warning cpm_

I ( 1. 7xio-2ci/ sec) ( 106 uCi/Ci - ( 60 sec/min)* 3. 50xl0 7 uCT/Cc = 17,388

-- (1.2sx105 ft 3)min) (2.832x104 cc/ft3)

!I Therefore dial in a setpoint of 1.03E04 cpm I

I I

,I

- ODCM I SNGs.:..2 M P79 63 02/6 .3. 21

I 3.0 RADIATION MONITORING INSTRUMENTATION 3.2 Derivations of Setpoints (Cont'd)

I CHANNEL 2Rl8 Liquid Waste Disposal INSTRUMENT NO. RA-4335-2 I LOCATION Auxiliary Building 86, 14.8/TT DETECTOR Photomultiplier Tube, Gamma Scintillator INTERLOCKS CONTROLLED Close valve 2WL41 Loop No. 5 I INSTRUMENT RECOMMENDED SETTINGS I CONF CTTM

=

=

0.90EO 3.00El DNBND =

FAIL=

3. 69E2 o.OOEO HIGH VOLTAGE ADJUSTMENT I Set H.V. (test pt) to 6.2 volts or adjust H.V. to obtain any of the following values:

I a) l.9ES cpm *from Ba 133 source number 237J b) 1. 6ES cpm from Cs 137 source number 237L I c) 1. 6ES cpm from Cs 137 source number 237M ALARM 4.08E04 cpm WARNING 2.05E04 cpm I Alarm Basis: *This device monitors liquid waste streams before I they are diluted by the circulating water and released to the environment. The ODCM requires that the MPCW not be exceeded. The alann will activate when the a concentration through the monitor reaches a value where the resultant concentration in the dilution water will exceed the MPCW. The MPCW for an unidentified mixture will be used for conservatism.

1. Assumptions and Calculation:
1. MPCw = lxlO 7 uCi/ cc for unidentified isotopes ( 10 CFR 20, I Appendix B, Table 2).
2. Sensitivity to Co60 = l.69x108 cpm/uci/cc I 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 lo-2 uCi/cc of each isotope.

I 3. Maximum (present) flow rate through pathway= 80 GPM (PSE&G internal memorandum of 6/18/76).

I 4. Flow rate of dilution water= 370,000 GPM (Page Q-11.3-1 of the FSAR states there will be a dilution I flow of 740,000 GPM. As a conservative assumption, only half of the dilution flow was considered).

I ODCM SNGS-2 I M P79 63 02/7 3.22

I 2Rl8 (Cont'd)

I a) b)

Conversion factor = 3.8xlo3 cc/gal Conversion factor= 1.31 x 105 min/qua~ter c) Conversion factor = 106 Ci/uCI I 6. Sampler background = 60 cpm (Cb) Initial background as determined by Victoreen Instrument Corporation in channel I 2R35, subsequent backgrounds may be higher as the sampler becomes contaminated.

I Setpoint: Alarm cpm

.I (lxlo-7 uCi/cc) (8.83xlo7 uci/cc) (370,000 GPM) + Cb = 40,839 cpm + Cb 80 GPM Therefore dial in a setpoint of 4.08E04 cpm I Warning Basis: Warning will activate when the liquid activity concen-tration exceeds 1/2 the MPC of an unidentified liquid.

I Setpoint: Warning

  • cpm (1/2) (lxlo-7 uCi/cc 8.83xlO'liei/cc) (3.70xl05 GPM) +Cb=

80 gpm Therefore, dial in a setpoint of 2.0SE04 cpm NOTE: 1) If the MPC is knovm to be higher than 1 x 107 then the alarm trip setpoint may be raised higher by a factor of MPC(actual) lx10-7uci/cc I 2) If the flow rate through the pathway is 200 GPM then the setpoint should be diminished by a factor of 80 GPM 200 GPM I

I I

I ODCM I SNGS-2 M P79 63 02/8 3.23

I I

4~0 LIQUID EFFLUENTS I 5.1 Limits or Restrictions I The dose to air at the site boundary should be limited in accordance with 10CFR20, 10CFR50 Appendix I and 40 CFR190 such that:

I 4.1.l During any instant release activities must be maintainedd below the concentrations of 10CFR20.106.

I 4.1.2 During any calendar quarter (Jan.-Mar.,

April-June, July-Sept., Oct.-Dec.) the dose I delivered shall be less than 1.5 mrem to the whole body and less than 5 mrem to any organ from each reactor.

,I 4.1.3 During any calendar year (Jan. 1-Dec. 31) the dose delivered shall be less than 3 mrem to the whole body and less than 10 mrem to any I organ from each reactor.

The values above are to be treated as limits.

However, if the calculatd dose from the release of I radioactve materials in noble gaseous effluents exceeds the 1 imi ts described above, prepa*re and submit a Special Report (not an LER) to the 1

1 Commission 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 I to the thyroid, which is limited to < 75 mrem) over 12 consecutive months from all reactors.

I Table 4 .1.1

.Summary of Limits Calendar 12 Consecutive I Dose to Whole Body Calendar Quarter 1.5 mrem Year 3 mrem Months*

25 mrem Organ 5. 0 mrem 10 mrem 75 mrem I *The EPA 12 month values includes liquids, gases and direct radiation and apply to all reactors at the I site. All other values apply to each nuclear unit.

ODCM I *sNGS-1&2 M P79 18 29/01 4.1

I I

4.0 LIQUID EFFLUENTS (Cont'd)

I 4.2 Dose Calculations 4.2.1 The dose from liquids shall be estimated at I least once every 31 days for each unit while releases are being made.

I 4.2.2 The dose shall include liquid radioactive discharges from the station and shall be classified as either a batch or continuous I releases. This does not include isotopes below MDL or isotopes identified in com-posites analysis or isotopes with very short decay times.

I 4.2.2.1 Batch Release includes:

1*, i) Waste Monitoring Tanks ii) Laundry and Hot Shower Tanks I iii) Chemical Drain Tanks iv) Chemical Volume Control CVC I v)

CVC Tanks Waste Hold-up (monitor) Tank I vi) Waste Hold-up Tanks vii) Abnormal Releases I 4*2.2.2 Continuous Releases include:

I i) Intermittent Steam Generator Blowdown 4.2.3 The dose contribution for each radionuclides I identified in liquid effluents released to unrestricted areas will be calculated using equations which follow for the purpose of I demonstration compliance with the *Technical Specifications. For submitting 6 month effluent release reports, additional pathways will be included and minor differences in the I calculated doses may arise due to the in-clusion of these additional dose contributors and the inclusion of isotopes which are only I available several weeks after the individual releases have taken place.

ODCM I SNGS-1&2 M P79 18 29/02 4.2 I

I I

4.0 LIQUID EFFLUENTS (Cont'd)

I 4.3 Dose Equation

eq 1 ) D = A
  • t

I where I D = is the total dose (to the body or to any organ.

I A = a total dose conversion factor (See eq. 2 (rnrern/hr per uCi/cc) t = the time over which the c and F I 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 I 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 I written as:

eq 2) A= l.14E5 (21 BF +BI) DF I where BF = the bioaccumulation factor for a I nuclide in the fish as taken from Reg. Guide l.109(Salt water)

(pCi/kg per pCi/l)

I BI = the bioaccurnulation factor for a nuclide in invertebrates as taken I from Reg. Guide 1.109 (salt water -

pCi/kg per pCi/l) 21 = the # of kilograms of fish which an I adult may consume in a year.

5 =*the # of kilograms of clams, oysters I and invertebrates which an adult may consume in a year.

ODCM I SNGS-1&2 M P79 18 29/03 4.3 I

I I

4.0 LIQUID EFFLUENTS (Cont'd)

I The A factor is supplied for isotopes and is listed as Table. 4.1. The BF, BI and DF factors to calculate the A factor was taken from Reg.

I Guide 1.109. Our site is nota fresh water site, therefore, the Uw or Dw terms were not necessary.

I INSTRUCTIONS FOR CALCULATING RADIATION DOSE FROM LIQUID EFFLUENTS I 4.3.l Determine the isotopes released. The station technical specifications describe which isotopes must be monitored and also describe detection I limits which are used for dose calculations.

Post-release isotopic analyses are used for dose calculations. Post-release isotopic analyses such as strontium analyses will not be included.

I 4.3.2 Locate the dose conversion factor (A) for each isotope using Table 4.1.

I 4.3.3 Determine the average concentration of the release (C) at the discharge point by taking into account all dilution. An average concen-I tration is merely equal to the total number of microcuries discharged over the total amount of fluid discharged.

I 4.3.4 Multiply the A, C, and the duration of the release(t).

I 4.3.5 The value obtained is the official estimate of the* total dose received by a member of the pub-lic who consumes these aquatic foods at the rate I specified.

4.3.6 For purpose of complying with 10CFR50 Appendix I I yearly dose limits and, since post-release analyses may cause the dose estimated in step 5 to be non-conservative, a dose uncertainty fac-tor of 25% is added. Doses are, therefore, mul-I tiplied by a factor of 1.25.

4.4 Operation of R~dwaste Equipment 1- If during any calendar quarter the whole body or organ dose exceeds 0.375 mrem or 1.25 mrem respect-fully, then the liquid radwaste system will be 1 operated.

I ODCM SNGS-1&2 4.4 M P79 18 29/04 1.

I I TABLE 4.1 LIQUID EFFLUENT INGESTION DOSE FACTOR$*

I Ai Dose or Dose Commitment Factors I (mrem-ml per hr-uCi)

Radionuclide Total Body Critical Organs*

I H-3 2.8E-l 2.8E-l P-32 6.4E+5 l.9E+6 I Cr-51 Mn-54 Fe-55 5.6E+O

1. 4E+3 8.2E+3 l.4E+3 2.2E+4 5.11E+4 Fe-59 7.3E+4 6.3E+5 I Co-58 Co-60 l.4E+3 3.8E+3 l.2E+4 3.3E+4 Zn-65 2.3E+5 5.1E+5 I Rb-86 .

Sr-89 Sr-90 2.9E+2

1. 4E+2 3.0E+4 6.2E+2 5.0E+3
1. 2E+5 Y-91 2.4E+O 4.9E+4 I Zr-95 Zr-97 3.5EO 8.lE-2
1. 6E+4 5.5E+4 Nb-95 l. 3E+2 l.5E+6 I Mo-99 Ru-103 Ru-106 2.4E+l 4.6E+l 2.0E+2 3.0E+2 l.2E+4
1. OE+5 Ag-llOm N/A N/A I Sb-124 Sb-125 N/A N/A N/A N/A Te-125m 2.9E+l 8.8E+2 I Te-127m Te-129m 6.7E+l l.5E+2 5.7E+l 2.2E+3 4.7E+3 6.8E+3 Te-13lm I Te-132 I-131 I-133
1. 2E+2 l.8E+2 3.9E+l 6.2E+3 l.OE+5 l.9E+4 Cs-134 l.3E+4 l.6E+4 I Cs-136 Cs-137 2.0E+3 7.9E+3 2.8E+3
1. 2E+4 Ba-140 l.1E+2 3.4E+3 I La-140 Ce-141 Ce-143 2.lE-1 2.6E-l 4.9E-2 5.8E+4 8.9E+3 l.7E+4 Ce-144 9.6EO 6.0E+4 I Np-239 1. 9E-3 7.1E+2
  • The listed dose factors are for radionuclides that may be de-I tected in liquid effluents.

ODCM I SNGS-1&2 P79 23 27 4.5 I

. ~ .:. . .

I I

5.0 GASEOUS EFFLUENTS (NOBLE GASES)

I 5.1 Limits or Restrictions The dose to air at the site boundary should be I limited in accordance with 10CFR20, 10CFR50 Appendix I and 40 CFR190 such that:

I 5.1.1 During any instant release activities must be maintained below the concentrations of 10CFR20.106.

I 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 I and 10 mrads from gamma and beta radiation respectively from each reactor.

I 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 radiatin respectively from each reactor.

I The values above are to be treated as limits.

However, if the calculatd *dose from the releas*e of I radioactve materials in noble gaseous effluents exceeds the limits described above, prepare and submit a Special Report (not an LER) to the Commission pursuant to Specification 6.9.2 of the I SNGS-TS.

I Table 5.1.1 Summary Air Dose Limits I Air Dose Calendar Calendar From Quarter Year I Gamma Rays 5 mrads 10 mrads I Beta F.ays 10 mrads 20 mrads I

I

  • 1 ODCM SNGS-1&2 M P79 18 29/01 5.1 I

I I

5.0 GASEOUS EFFLUENTS - NOBLE GASES (CONT'D)

I 5.2 General Guidance on Dose Calculations I 5.2.1 The dose from gases shall be estimated at least once every 31 days for each unit while releases are being made.

I 5.2.2 The dose shall include all gaseous radio-active discharges from the station. Isotopes identified as MDL or LLD are treated as I numerically equal to zero.

5.2.2.1 Release Points includes but are not I limited to the following locations:

i) Wast~ Gas Decay Tanks I ii) Containment Purges 5.2.3 The dose contribution for each radionuclides I identified in gaseous effluents released to unrestricted areas will be calculated using equations which follow for the purpose of demonstration compliance with the Technical I Specifications. For submitting 6 month effluent release reports, additional pathways will be included arid minor differences in the I calculated doses may arise due to the in-clusion of these additional dose contributors and the inclusion of isotopes which are only available several weeks after the individual I releases have taken place.

5.3 Dose Equations I 5.3.1 In order to calculate the dose from Gamma Rays of noble gases, use the following equation:

I D = 3.17E-8

  • Mi
  • X
  • Qi
  • DU G Q I 5.3.2 In order to calculate the dose from beta rays of noble gases, use *the following I equation:

D = 3.17E-8 *Ni

  • X
  • Oi

I ODCM SNGS-1&2 M P79 18 29/02 5.2 I

I I

5.0 GASEOUS EFFLUENTS - NOBLE GASES (CONT'D)

I 5.3.3 In order to further protect the public from exposure to noble gases, the release rate I must be restricted as provided in specification 3.11.2.1.

Table 5.3.1)

I Summary Release Rate Limits I To Protect Limit Dose Rate To I Whole Body 500 mrem/yr Skin 3,000 mrem/yr I

I 5.3.4 The equations to use are as follows:

Ki * (~)

  • Q < 3000 mrem/yr I Q I (Li + l.lMi) (X)

Q Qi < 3000 mrem/yr where Qi = curies per second I

Therefore, don't release a gas decay tank I containing noble gases so rapid that it causes a* release rate in excess of the values above.

I Note:

The factors Ki, Li, Mi, and Ni relate the radionuclide I airborne concentrations to various dose rates assuming a semi-infinite cloud. .These factors may be taken directly from Table B-1, of the Regulatory Guide 1.109 (Ref. 6),

if the values therein are multiplied by 106 to convert I piocuries to microcuries as*. used in the above equations.

I I ODCM SNGS-1&2 M P79 18 29/03 5.3 I

5.0 GASEOUS EFFLUENTS - NOBLE.GASES (CONT'D)

I 5.4 Instructions For. Demonstrating Noble Gases Releases are Within Limits I A recommended scheme for determining compliance or airborne releases is presented below. The use of a digital computer will greatly simplify this I determination.

1) Determining isotopic composition of noble gases I discharged in uCi/cc or equivalent. Using equations in 5.3.4 determine the release rate requirements.

I 2) Using Table 5.0 which factors locate the K, lists the dose conversion L, M, and N*terms for each individual isotope of interest. In addition, I let the DU Term equal of 1.25.

a dose Uncertainty factor

3) Use the "Chi over Q (X /Q) term of 2.2E-6 .sec/m3 I which is the historical highest calculated annual average relative-concentration according to Supplement 3 USNRC Salem Nuclear Generating

.1 Station Safety Evaluation Report.

4) Determine the total number of microcuries (Qi).

I 5) Substitute the L~ *K, M, N, and Q terms into the equations provided.

I I

I I

ODCM.

SNGS-1&2 M P79 18 29/04 5.4

I I

6.0 IODINES, PARTICULATES AND NON-NOBLE GAS AEROSOLS I 6.1. Limits or Restrictions I In order to protect the public from exposure to radioactive aerosols, radioiodines, particulates and other non-noble gases with half-lives greater than 8 days, releases should be limited in accordance with I 10CFR20, 10CFR50 Appendix I and 40CFR190 such that:

6.1.1 During any instant release activities must be I maintained below the concentrations of 10CFR20.106.

6.1.2 During any calendar quarter (Jan.-Mar.,

I April-June, July-Sept., Oct.-Dec.) the dose delivered shall be less thart 7.5 mrem to any organ from each reactor.

I 6.1.3 During any calendar year (Jan. 1-Dec. 31) the dose delivered shall be less than 15 mrem to I any organ from each reactor.

The values above are to be treated as limits.

However, if the calculated dose from the release of I radioactive materials in liquid effluents exceeds the limits described above, prepare and submit a Special Report (not an LER) to the Commission I 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 I the thyrol.d,.which is limited to< 75 mrem) over 12 consecutive months from all reactors.

I I

I I

I ODCM I SNGS-1&2 M P79 18 29/14 6.1 I

I L_.

I 6.0 IODINES, PARTICULATES AND NON-NOBLE GAS AEROSOLS (Cont'd)

I The release limitations are summarized below.

I Table 6.1.1 Summary Airborne Iodines, Non-Noble Gases and Particulate Limits I

I Dose To Calendar Quarter Calendar Quarter 12 Consecutive Months I

Any Organ 7.5 mrem 15 mrem 75 mrern I

I NOTES:

a) The EPA 12 month values apply to all reactors at the I site. All other values apply to each nuclear unit. The EPA limits include liquids and gases.

6.2 General Guidance on Dose Calculations I 6.2.2 The dose shall be calculated for all gaseous release points. The guidance supplied in I Section 5.2 also applies to section 6.2 I

I I

I I

ODCM I SNGS-1&2 M P79 18 29/15 6. 2

  • I

I I

6.0 IODINES, PARTICULATES AND NON-NOBLE GAS AEROSOLS (Cont'd)

I 6.3 Dose Equations I 6.3.1 The dose to the public from radioiodine, particulates and non-noble gases with half-lives greater than 8 days shall be determined to be the sum of the terms which follows.

I This analysis assumes that the public drinks milk from the closest dairy farm and also breathes the air at this same location.

I Where Du is the dose uncertainty factor of I 1.25. If operating experience indicates that the Du factor is not conservative, then it will be changed.

I 6.3.2 For the direction sectors with existing path-ways within 5 miles from the unit, use the values Ri for those pathways. If no real I pathway exists within 5 miles from the center of the building complex, use the cow-milk Ri assuming that this pathway exists at the I 4.5 to 5.0 mile distance in the worst sector.

If the Ri for an existing pathway within 5 miles is less than a cow-milk Ri at 4.5 to 5.0 miles, then use the value of the cow-milk I Ri at 4.5. to 5.0 miles. The pathway values used for calculating dose contribu-tions shall be consistent with the results of I the land use census performed pursuant to Specification 3.12.2. The controlling value of Ri for each radionuclide is determined I and provided in tabular form in this ODCM as Table 5.1. The parameters W corresponds to the applicable pathway location and are sub-ject to change. The Licensing and Environ-I ment Department will determine if the values of W need to be altered.

I I

I ODCM I SNGS-1&2 M P79 18 29/16 6.3 I

I I

6.0 IODINES, PARTICULATES AND NON-NOBLE GAS AEROSOLS (Cont'd)

I 6.3.3 The release rate of radioactive iodines and particulates must be restricted as provided in Specification 3.11.2.l Table 6.3.l Summary Dose Rate Limits I To Protect Limit Dose Rate To I Any organ or thyroid 1,500 mrem I

6.3.4 The equation to use is as follows:

I Ri W Q < 1500 mrem/yr I assuming all I 131 then Q = 6.5 uCi/sec Therefore don't release a gas decay tank such that the resulting dose rates exceed the I values above. This is achieved by keeping Q under 6.5 uCi/s~c I 6.4 Instructions for Demonstrating Iodines, Particulates and Non-noble Gases are Within Limits I 6.4.1 Determining isotopic composition of the various iodines particulates and other non noble gases discharged with half lives > 8 days (uCi/cc or equivalent).

I 6.4.2 Using Table 5.1 which lists the conversion factors locate the "Ri" term for each I 6.4.3 individual isotope of interest.

For the "WH" and "WG" terms use 5.4E-8 sec/m3 and 2~1E-10/rn2 which is the historical I X/Q and D/Q relative concentration in the NNE sector according to Supplement 3 to the Safety Evaluation Report of the SNGS.

I ODCM I SNGS-1&2 M P79 18 29/17 6.4 I

6.0 IODINES, PARTICULATES AND NON-NOBLE GAS AEROSOLS (Cont'd)

I 6.4.4 Determine the total microcuries discharged over the reporting period.

I 6.4.5 Substitute the R, W, and Q terms into the equations provided.

I 6.5 Operating of Radwaste Equipment 6.5.l If the calculated dose exceeds 1.25 mrad for I gamma radiation and 2.5 mrad for beta radiation during any calendar quarter, then the gaseous radwaste treatment system shall I 6.5.2 be operated.

To account for the isotopes which may not be I identified until after the release has been made, a dose uncertainty factor of 25% of the applicable limit has been added. If opera.ting experience indicates that the 25%

I factor is not conservative, then the dose uncertainty factor will be changed.

I 6. 5. 3 The following are gaseous radioactive waste management systems for which credit may be taken:

  • I i) Waste hold-up for decay ii) Iodine and particulate filtration I The following are not gaseous radwaste management systems:

I i) Engineering Safety features such as internal atmosphere I ii) Elevated vents I

I I

  • 1 ODCM SNGS-1&2 M P79 18 29/18 6.5 I

TABLE 5.0 OOSE FACTORS FOR NOBLE GASES AND OAUGllTERS" Total Body Gamma Atr Beta A1r Dose. K Factor .

Skin Dose factor Oose factor Dose factor 1 l "1 "1 .

Rad1onuc 11 de (mrem/yr per ,.ct /r1 3) (mrem/yr plr 1* Ct /m 3) (mrad/yr per ~Ci/m3) jmrAd/yr per 11Cj/m 3).

Kr-83m 7. 56[- 02"* l. 93Et0l 2.88Et02 Kr-85m 1.17£+03 l.46Et03 l .23E-t03 l. 97H03 Kr-05 l .61E tOl l. 34H03. l. 72Et0l l. 95Et03 Kr-07 5.92£+03 9.73H03 6.l7Et03 1.03Et04 Kr-88 l.47E+04 2. 37E+03 l.52Et04 2.93Et03 O'\

Cl'\ Kr-09 1. 66Et04 l .01H04 1. 73H04 1. 06Et04 Kr-90 1. 56E +04 7.29Et03 l.63E+04 7.83E-t03 Xe-13lm 9.l5E+Ol 4.76[+02 1. 56E+02 L llft03 Xe- l 33m 2. 51£+02 9.94Et02 3.27Et02 l.48Et03 Xe-133 2. 94£+02 3.06(-102 3.53Et02 l .05E-t03 xe-l35m 3. l 2Et03 7. l l Et02 3.36Et03 7.j9[-t02 Xe-135 1.81[+03 l. 86Et03 l.92E+03 2.46E-t03 Xe-137 l.42E+o3 1.22[+04 l.51Et03 1. 27Et04 Xe-138 8.83E-t03 4. l 3Et03 9.21E-t03 4.75Et03 Ar-41 8. 84E-t0'3 2.69Et03 9.JOE+Ol 3.20Et03

    • The listed dose .factors are for rad1onucl1des that may be detected 1n gaseous e.ffluents.
    • 7.56E-02;:;;. '7.56 x 10- 2
  • TABLE 5.1 DOSE Pl\MMEHPS FOH f!/\DWir.ornES J\.l!O nf\OI01KTIVE

--.--r>r:-r.-=r L1{

.. 1* -c**1T1-A"'--E-----,.J.t\.i,_.

J _ ! : l 1

  • -*r=-,-,-l

-,-i"r i'*--.J.) ._f ..

f;-.. ' j--::-s*' _____ _

.)~_(*, ~

--- --.---------**---- -~--*--

R.

R.

1 R1 1

. Milk & Ground Pathways

  • Milk & Ground Pathways Radio- lnhalat1on Path~ay . 2 Radio- Inhalation Pathway 2 nuclide (rnrern/,l!~r pC1/m3)t\. mrem/yr per uCi/sec) _!lucjide (rnremtyuer J:C i/mj l ~<_m_._m_r_e_m-"/-=y'-r--=-p_e_r_u_C_i._/_s~e_c)
  • 11- 3 6. 5E -t02 2.4[+03 Cd-l15m 7 .OE-:*04 4.8£t07 P-32 2. 0[+06 l. 5E-t- ll Sn-123 2.9£+05 J .*i[ I 09

'Mn-54 2. 5E**04 L l E-t 09 Sn-126 1. 2E+06 1 . l Et-09 Fe-59 2.4E-tO'l 7.0E+OU Sb-124 5. 9E+04 l . l f +09 0)

Co-5.ll Co-60

l. lt*t04 3.2E-t04.
5. 7£**00

'I. 6E **09 Sb-125 le- l 27m

l. 5[+04 3.0E-t04 1.1£+09 7 .qf i}O Zn-65 6.3[-1()4 l.7E+l0 Te-l29m 3.2[+04 l. JE-t 09 Rli-06 l.9E*t05 l. ()[ t* 10 Cs-134 7.0E+05 5. JE-t-10 Sr-09 4.0Et05 1. OE t-10 Cs-136 l.3E+C5 5.'1[109 sr..:<Jo 4. lE-107 9. 5[1-10 Cs-137 6.l[-1*05 4.7Et-l0 Y-91 l. OE *104 l. ')[I 09 Bn-140 5. 6Elll4 2 .1][100 Zr-95 2.2Et04 3.5E10B Ce-141 . 2~ 2E*t 04 0.7Et07 t.lb-95 l.3E+04 3.6E*OB Ce-144 l. 5£-105 6.5E+OO Ru-103 l. 6E-t04 3.4£+10 I-131 l . 5Et07 l.llt\2 Hu-106 l.6[*105 4. '1£+ 11 J ,..133 . 3 .6[-t-06 9.6H09 Ay- l lOm 3.JE t04 . l. 5E+ i0

r-the l i s:ted dose parameters are for rad ionucl ides that may Lie detecLd 1n gaseous effluents.

Retrieved from "https://kanterella.com/w/index.php?title=ML18081A718&oldid=2412435"