ML19290D918

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Estimating Release from Radiation Monitoring Sys Data
ML19290D918
Person / Time
Site: North Anna 
Issue date: 01/31/1980
From: Hopper D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19290D916 List:
References
RTR-NUREG-0578, RTR-NUREG-578 EPIP-11, NUDOCS 8002290387
Download: ML19290D918 (27)
v • d • e


Text

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EPIP-11 Page 1 of 4 01-31-80 VIRGINIA ELECTRIC AND POWER COMPAhT NORnl ANNA P0b7.R STATION f

ESTIMATING REI. EASE FROM RADIATION MONITORING SYSTEM DATA 1.0 Operations Response 2.0 Heal h Physics Response Appendix 1, Significance and Evaluation of Release Estimates Based on Radiation Monitoring System Data Appendix 2, Black Forms EPIP 11.1, RMS Relea.e Data Worksheet Appendix 3, Procedure for Determining Release Rates and Doses Rates Using High Range Effluent Mocitors NOT A CONTRORED DOCUMENT F B 3 51980

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NOR NECESSARILY THE MTEST REylsicN

, '! f V 880 f

RECOMMEND APPROVAL:

APPROVED BY:

-l $ %

CHAIRtCTATION NUCLEAR SAFETY AND OPERATING CCMMITTEE d> L -.:Q 7 977' I7 DATE:

01-31-80 GL.:.7 7 m'['*.p)u1*L.!..u 8002 290387

i EPIP-11 Page 2 of 4 01-31-80 ESTIMATING RELEASE FROM RADIAT!ON MONITORING SYSTEM DATA 1.0 Overations Response 1.1 Obtain, from Appendix 2 of this procedure, a FORM EPIP 11.1, "RMS Release Data Worksheet".

NOTE:

IF LOW RANGE !"ONITORS ARE OFT SCALE THEN TO D3TERMINE.

RELEASE RATES AND/OR DOSE RATES USING THE HIGH RANGE EFFLL'ENT MONITORS, REFER TO APPENDIX 3.

OPERATIONS SHOULD IMMEDIATELY POST AN INDIVIDUAL TO RECORD DATA ON A FIVE !iINUTE FREQUENCY USING THE APPROPRIATE HIGH RANGE RADIATION MONITOR. FOLLCWING THE INS" RUCTIONS IN APPENDIX 3, CALCULATE THE RELEASE RATES.

1.2 Gotain the count rate of the monitor of interest from the radiation system panels as appropriate, and enter the monitor type (or number) and the count rate in CPM which is to be evaluated on FORM EPIP 11.1.

(

NOTE:

Refer to last PT-37 for background subtraction, prior to calculating release data.

1.3 Obtain from Table EPIP 11.1, " Response of Potential Release Path Radiation Monitors", the Ci per Hr Released per CIM value and the Selected Flow Rate for each monitor of interest and enter on FORM EPIP 11.1.

1.4 Obtain, by appropriate methods, the flow rate of the path being monitored (in the same units as entered on FORM EPIP 11.1) and enter on FORM EPIP 11.1.

If this is not practical or desired, a " default" value equal :o the Selected Flow Rate (design) may be used.

1.5 Perform the indicated math to obtain the gross curies of ac-tivity indicated as being released per hour.

The total amount of activity released can then be estimated based on the known s

or expected time durar. ion of the release.

EPIP-11 Page 3 of 4 01-31-80 1.0 Operations Response 1.6 Use these results for preliminary evaluation, forward the completed FORM EPIP 11.1 to HP for use in determining the need for further monitoring. The release data to initiate any offsite action will come from hP on a FORM EPIP 2.1.

2.0 Health Physics Response 2.1 If a release point has a continuous in line radiation sampler (such as process or ventilation) vent, remove the filter (s) and/or obtain a sample (s) and count using the appropriate count room equipment.

2.2 If the filter removed or the sample taken will affect the routine records of the Power Stations radioactive effluents,

(

use the appropriate Release Pecord as described in the 3.2 series of HP Procedures concerning radioactive waste and cal-culate the release accordingly.

2.3 Based on the information shown on FORM EPIP 11.1, determine the need for obtaining additional samples or other monitoring.

EPIP-11 Page 4 of 4 01-31-80 TABLE EPIP 11.1 RESPONSE OF POTENTIAL RELEASE PATH RADIATION MONITORS REFERENCE pCi/ml SELECTED Ci ner Hr Released MONITOR

SS-122, 123, 123, 222, 223, 224 DsTun - Discharge Tunnel Liquid:

SW-130, 230.

CCWSW - Cocrponent Cooling Water Ex Service Water:

SW-107.

RSC1

'ecire. Spray Cooling Service Water Outlet:

SW-124, 125, 126, 127, 224, 225, 226, 227.

SW - Service Water Discharge:

SW-108.

Clf D - Clairfier Discharge:

LW-lll.

PVG - Process Vent Radiogas:

GW-102.

PVP - Process Vent Air Particulate:

GW-101.

VAG - Ventilation Vent A Radiogas:

VG-104.

VAP - Ventilation Vent A Air Particulate:

VG-103.

VBG - Ventilation Vent B Radiogas:

VG-ll3.

V3P - Ventilation Vent 3 Air Particulate:

VG-112.

C.E - Condenser Air Ej ector Radiogss:

SV-121, 221.

EPIP-11 Appendix 1 Page 1 of 2 01-31-80 ESTIMATING RFTFASE FROM RADIATION MONITORING SYSTEM DATA APPENDIX 1 SIGNITICANCE AND EVALUATION OF RELEASE ESTIMATES BASED ON RADIATION MONITORING SYSTEM DATA Part Subject 1.0 Consideration on the RMS

(

2.0 Estimating Release of Airborne Activity Exceeding Monitor's k

Range s

EPIP-11 Appendix 1 Page 2 of 2 01-31-80 1.0 Considerations on the RMS The detectors in the RMS respond to gross activity and for this reason the response of the monitor must be interpreted using know-ledge of the system involved. For instance, liquid monitors will detect any gamma emitters, which includes dissolved radiogases which do not necessarily present the radiation hazard the monitor could be implying.

Air particulate monitors have detectors which are NaI scintillation devices and therefore count essentially only gamma enitting parti-cles.

It should not be assumed radioiodines car,be collected and counted on the filter paper. Air radiogas monitors have relative 2

thick (30 mg/cm ) walled G-M detectors, and therefere have a much lower ef ficiency for weak beta emitters, for instance the Xe-133

(

cpm / Ci is more than 10 less than that for Kr-85.

The electronics used in the RMS are designed in a maaner which should prevent a meter from reading low even if that channel's G-M detector is in continuous discharge.

2.0 Estimating Release of Airborne Activitv Exceeding Monitor's Range If activity collected by the monitor results in full scale reading tue activity released can be estimated by count room methods as described in Step 2.0 of this procedure or if a quick estimate is considered essential the following method may be used.

Measure the dose rate one foot from the actual collection point of the monitor. Esticate the curies released using the following equation.

Ci = 0.00624 x ER CFM of Monitored Path x

br CFM of Sacpling Rate

EPIP-11 Appendix 2 Page 1 of 2 01-31-80 ESTIMATING RELEASE FROM RADIATION MONITORING SYSTEM DATA APPENDIX 2 BLANK FORMS EPIP 11.1 R".S PFLEASE DATA '40RKSHEET

EPIP-11 Appendix 2 Page 2 of 2 Form EPIP-11.1 01-31-80 RMS RELEASE DATA WORKSHEET Date/ Time:

Ci per Hr RELEASED SELECTED ACTUAL Ci per Hr MONITOR CPM CPM FLOW RATE FLOW RATE RELEASED X

X

=

X X

=

X X

=

_ X X

=

X X

=

_ X X

=

Ci per Hr Estimated or Known Estimated Curies Released Number of Hours of Release Released X

X X

X X

X NOTE: Refer to last 7-37 for background subtraction, prior to calcula-ting release data.

EPIP-11 Appendix 3 Page 1 of 19 01-31-80 ESTIE\\ TING REI. EASE FROM RADIATION MONITORING SYSTEM DATA APPE:QIX 3 ESTIMATING RELEASE AND/OR DOSE RATES FROM HIGH RANGE RADIATION EFFLUENT MONITORS Part Subject 1.0 Determing 'n' hole Body Dose Using Kr-85 Equivalent k

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EPIP-11 Appendix 3 Page 3 of 19 01-31-80 CUTLINE OF THE PROCLFTRE FOR DETERMINING REIIASE RATES AND D0fi RATES DURING THE INTERIM HIGH RANGE EFFLUENT MONITORS The following is for determining the whole body gamma dose using a Kr-85 equivalent.

1.

Concentration (pCi/ce)

The concentration in the effluent stream is determined as a Kr-85 equivalent. A graph is utilized which displays dose rate (MREM /Hr) vs Kr

',5 equivalent concen-cation (pCi/cc). The Kr-85 equivalent concentration is read directly from the graph at the point on the curve corresponding to the dose rate reading from the monitor.

(Table I lists the figures and their appropriate application.)

2.

Flow Rate (cc/Sec)

See procedure in Section 2.

3.

Release Rate (pCi/Sec)

The release rate is calculated by =ultiplying the concentration (pCi/ce),

determined in Section 1, by the flow rate (cc/sec), determined in

(_

Section 2.

This is the release rate of Kr-85 equivalent.

R = Releasif Rate (pci/sec) Kr-85 equivalent C = Concen: ration (pCi/ce) Kr-85 equivalent F = Flaw Rate (cc/sec)

R = CF pCi/ rec = pCi/cc x cc/sec 4.

Whole Body Gamma Dose Rate (nREM/Hr)

The dose rate at any location may be calculated using the release rate (pCi/sec) of Kr-85 equivalent from Section 3, the dose rate conversion factor for Kr-85, and the X/Q for the location of interest-from current MET data.

The dose rate is calculated as follows, where D = Dose Rate (= REM /Hr)

X/Q - Atmospheric Diffusion Factor (sec/M ) = 2.0 x 10 '

~

K = Cose Rate Conversion Factor for Kr-85 = 1.8 x 10~

MREM /Er pCi/M~

R = Release Rate 'rCi/sec)

(see 3 above) s

EPIP-11 Appendix 3 Page 4 of 19 01-31-80 D = K x R x X/Q

~

D = 1.80 x 10 R X/Q MREM /Hr = MREM-M x pCi x sec Hr-pCi see M"

2.

Flow Rate Conversion (cc/sec)

A.

Main Steam Lines F, = m (2.8317 x 10")

p 3600 where:

F = Volume Flow Rate Main Steam, cc/sec M = Mass Flow Rate Main Steam, LBM/Hr (see Table 2)

P = Density of fluid (main steam @ Sgeam t nerator temperature and pressure) LBM/FT = 2.3625 @ 1050 psia B.

Vent Stacks and Process Vents 4

F = SCFM x (2.8317 x 10 )

s

.eo s,

where:

F, = Volume Flow Rate of Gas, cc/see SCFM = Measured volume flow rate of gas at std. conditions (NOTE:

difference between actual and std. con-ditions are negligible), SCFM (see Table 2)

NOTE:

Due to the shielding effect of the main steam safety valve riser pipe thickness, the detector response to Xe-133 will significantly under estimate the po'.m - 'al offsite dose due to Xe-133.

However, for relief valve operations immediately af ter reactor trip, this will not significantly effect the accuracy of the total potential whole body dose projection.

(

EPIP-11 Appendix 3 Page 5 of 19 01-31-80 TABLE 1 LIST OF FIGURES FIGURE 1 - Unit 1 - Main Steam Safety Line 32"-SHP-22, RM-MS170 FIGURE 2 - Unit 1 - Main Steam Safety Line 32"-SHP-23, RM-MS171 FIGURE 3 - Unit 1 - Main Steam Safety Line 32"-SHP-24, RM-MS172 FIGURE 4 - Units 1 & 2, Process Vent, RM-GE 73 Units 1 & 2, Vent Stack A, RM-VG174 l'rti

  • a 1 & 2, Vent Stack B, RM-VG175 FIGURE 5 - Unit 2 - Main Steam Safety Line 32"-SHP-422, RM-MS270 FIGURd 6 - Unit 2 - Main Steam Safety Line 32"-SHP-423, RM-MS271 F. CURE 7 - Unit 2 - Main Steam Safety Line 32"-SHP-424, RM-MS272 s

EPIP-11 Appendix 3 Page 6 of 19 01-31-80 TABLE 2 FLOW RATE DETERMINATION Source of Flow Min. Flow for Accurate Ref.

Monitor Service Measurement Measurement (MF)

Notes RM-MS 170 Main Steam Safety ET-1474 30% Llov*

1, 2 Line (32"-SHP-22)

RM-MS 172 Main Steam Safety FT-1484 30% Flow

  • 1, 2 Line (32"-SHP-23)

RM-MS 172 Main Steam Safety FT-1494 30% Flow

  • 1, 2 Line (32"-SHP-23)

RM-GW 173 Process Vent FT-GW 108 100 cfm*

1, 3 RM-VG 174 Vent Stack A l'"-HV 1212A 100,000 cfm 1, 4 RM-VG 175 Vent Stack B FT-HV 1212B 80,000 cfm I, 4 Notes:

  • or as determined by operating data

(

1.

If flow rate indicated is less than minimum flow fcr accurate s

measurement (MF), the flow must be determined using the methods outlines in Notes 2 through 4, as applicable, or a flow of MF may be assumed.

2.

Based on values determined open by inspection for a given period of time, determine total flow using design flow rates of 855,084 lb/hr for each safety valve, 690,000 lb/hr for each atmospheric steam dump valve (PCV-MS 101A, B, C), and 181,000 lb/hr for the decay heat release valve (HCV-MS 104) 3.

An evaluation of paths open to process vent must be performed to determine total flow.

4.

Based on fans operating, determine total flow based on the following design flows:

Fan Area Design Flow (Cfm each_)_

HV-F-5A, B Reactor Containment Purge 11,000 HV-F-7A, B Fuel Building 17,500 HV-F-8A, B, C Aux. Building, Central' Area 20,200 HV-F-9A. B, C Aux. Building, General Area 24,700

. HV-F-40A, B Safeguards ?.rea 12,700 HV-F-56A, B Decontamination Building 13,150

EPIP-11 Appendix 3 Page 7 of 19 01-31-80 TABLE 2 Continued FISPONSE Each steam generato. is protected with five safety valves as follows:

Capacity, each Capacity, each Set Pressure Mark No.

Set Press at Set Press at 1,135 Psig Tolerance SV-MS101A,B,C 1,C85 817,883 855,084

! 1%

SV-MS102A,B,C 1,095 825,323 855,084 1%

SV-MSIO3A,B,C 1,110 836,483 855,084 1 1%

SV-MS104A,B,C 1,120 843,924 855,084 1%

SV-MS105A,B,C 1,135 855,084 855,084 1 1%

Actual Total capacity for 5 valves 4,275,420 lb/hr Required total capacity for 5 valves 4,252,439 lb/hr Excess capacity 22,981 lb/hr

EPIP 11 FIGURE 1 p3ge a of 13 01-31-80

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s EPIP 11 FICURE 1 Page 9 of 13 (continued) 01-31-60 UNIT 1 MAIN STEAM SMm LINE 32" - SHP-22 RM-MS170 2

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