ML20024D938

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Public Version of Rev 5 to Plant Emergency Procedure PEP-03.4.1, Initial Dose Projection & Rev 3 to Procedure PEP-03.6.1, Release Estimates Based Upon Stack/Vent Readings.
ML20024D938
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 06/08/1983
From: Boyer L
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20024D935 List:
References
PROC-830608-01, NUDOCS 8308080532
Download: ML20024D938 (19)
v • d • e


Text

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I CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 l

REVISED PLANT EMERGENCY PROCEDURES SECTION NUMBER TITLE REVISION NUMBER 3.4.1* Initial Dose Projections 5 I

3.6.1* Release Estilaates Based Upon 3 Stack / Vent Readings I

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  • Partial instructions or modifications.

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8308080532 G30726 O '

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- CAROLINA POWER & LIGHT COMPANT BRUNSWICK STEAM ELECTRIC PLAST UNIT 0 INITIAL DOSE PROJECTIONS PLAST EMERGENCY PROCEDURE: PEP-03.4.1

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VOLbEXIII 1

1 Rev. 005

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Recommended By:

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Date: 7!M Director - Admifristrative Support '

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l l Approved By: d t. N M Date: SN

6eneral Manager dj W

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LIST OF EFFECTIVE PAGES  :

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PEP-03.4.1 ,

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1 BSEP/Vol. XIII/ PEP-03.4.1 i Rev. 5 1

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i 3.5 Determine Source Term i

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3.5.1 If the stack high range radiation monitor is indicating a release, perform the following steps:

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i i '- 3.5.1.1 Read the actual activity (uCi/cc) from 4 2-D12-RR-4599, channel 1, 2, er 3.

3.5.1.2 Read flow meter for the specific release point

} (SCF/ min).

  • 3 3.5.1.3 For WHOLE BODY DOSE PROJECTION, calculate total release in curies /second = specific activity (yCi/cc) x flow rate (SCF/ min) x 28,300 (cc/SCF) x 10-6 (Ci/pci) x 0.0167 (min /sec).

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3 3.5.1.4 For THYROID DOSE PROJECTION, calculate total

{ release in curies /second = specific activity y (pCi/cc) x flow rate (SCF/ min) x 28,300 (cc/SCF) j 7

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x 10-6 (Ci/pci) x 0.0167 (min /sec) x (0.15).

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, : 3.5.1.5 Record results or either 3.5.1.3 or 3.5.1.4 in column 5 of Exhibit 3.4.1-1.

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l BSEP/Vol. XIII/ PEP-03.4.1 5 Rev. 5 4

3 . 5 '. 2 If the Turbine Building High Range Radiation Monitors are indicating a release, refer to the figure below.

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l Source Term Calculation From Unit No. 1 and/or Unit No. 2 Turbine Building Vent

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, 3.5.2.1 Read the actual specific activity (Ci/cc) from the graph as a function of the dose rate (R/hr.)

.I indicated on the meter.

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'! 3.5.2.2 Read the flow meter for the specific release

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point (SCF/ min).

}, 3.5.2.3 For WHOLE BODY DOSE PROJECTION, calculate total

.j release in curies /second = specific activity 1 (Ci/cc) x flow rate (SCF/ min) x 28,300 (cc/SCF) x 0.0167 (min /sec).

OR 4

, BSEP/Vol. XIII/ PEP-03.4.1 6 Rev. 5 '-

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l 3.5.2.4 For THYROID DOSE PROJECTION, calculate total release in curies /second = specific activity

. C -

(Ci/cc) x flow rate (SCF/ min) x 28,300 (cc/SCF) x 0.0167 (min /sec) x .15.

.. 3.5.2.5 Record the results of either .3.5.2.3 or 3.5.2.4 in column 5 of Exhibit 3.4.1-1.

3.5.3 If the gaseous effluent monitors for the Stack or the l Turbine Building Vents are not indicating a release, refer to PEP-03.6.1 to calculate a source term based on one of the other low range effluent monitors. Record the l appropriate source term in column 5 of Exhibit 3.A.1-1.

3.6 Determine Dose Conversion Factor 3.6.1 Use Table 3.4.1-3 to determine the Whole Body or Thyroid Dose Conversion Factor (DCF). Record the appropriate DCF in column 6 of Exhibit 3.4.1-1.

TABLE 3.4.1-3 DOSE CONVERSION FACTORS (Rem /hr)/(Ci/m')

Accident Condition Whole Body Thyroid l Unknown / unidentified 287 7.49E+5 Major damage to fuel cladding 287 7.49E+3

RCS leaks or steam line leaks 133 1.25E+6

{ but no major cladding failure Accidental discharge of waste gas 45 2.06E+6 Fuel handling accident 19 2.94E+6 3.7 To obtain the projected dose at the property boundary, multiply

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column 4 x column 5 x column 6 = column 7. Record the product in column 7 of Exhibit 3.4.1-1.

NOTE: If the release was via the stack (elevated), maximum radiological exposures could occur beyond the property boundary depending on stability class. Step 3.8 projects doses at distances beyond the property boundary for both elevated and ground level releases.

i BSEP/Vol. XIII/ PEP-03.4.1 7 Rev. 5 r.

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3.8 Determine Extrapolation Factor 3.8.1 If the release is from the stack, use Table 3.4.1-4. (If not, go to Step 3.8.3.) Read across the appropriate row based on distance from the plant to the extrapolation s factor under the atmospheric stability class determined in Step 3.3.

NOTE: With an elevated release, maximum radiological j exposures may occur beyond the property boundary

  • depending on stability class. The following j table indicates the downwind distance where maximum exposures are likely to occur as the result of an elevated release.

Stability Class Downwind Distance A 0.27 miles (0.43 km)

B 0.45 miles (0.72 km)

C 0.76 miles (1.22 km)(Property Boundary)

D 1.8 miles (2.9 km)

E 3.5 miles (5.6 km)

.; ..F 9 miles (14.5 km) --

G 33 miles (53 km)

TABLE 3.4.1-4 EXTRAPOLATION FACTOR FOR ESTIMATING DOSES BEYOND BSEP PROPERTY BOUNDARY (4,000 ft.)

ELEVATED RELEASE DISTANCE FROM PLANT EXTRAPOLATION FACTORS BY ATMOSPHERIC STABILITY CLASS Miles km A B C t D E F G 1 1.6 4.2 E-1 6.6 E-1 9.2 E-1 2.1 8.4 E+0 2.3 E+2 4.2 E+5 2 3.2 5.2 E-2 1.9 E-1 3.8 E-1 3.4 6.7 E+1 8.8 E+4 8.5 E+11 3 4.8 1.6 E-2 8.4 E-2 2.0 E-1 2.8 8.7 E+1 3.3 E+5 3.4 E+13 4 6.4 6.5 E-3 4.7 E-2 1.2 E-1 2.2 8.6 E+1 5.8 E+5 1.8 E+14

5 8.0 3.4 E-3 3.1 E-2 8.2 E-2 1.8 8.0 E+1 7.3 E+5 4.6 E+14 6 9.7 2.0 E-3 2.1 E-2 5.9 E-2 1.4 7.3 E+1 8.1 E+5 8.4 E+14 3

.. 7 11.3 1.2 E-3 1.5 E-2 4.5 E-2 1.2 6.6 E+1 8.8 E+5 1.3 E+15

.! 8 12.9 8.2 E-4 1.2 E-2 3.6 E-2 1.0 6.0 E+1 8.8 c+3 1.6 E+15 9 14.5 5.8 E-4 9.4 E-3 2.8 E-2 8.6 E-1 5.5 E+1 8.8 E+5 2.2 E+15 10 16.1 4.3 E-4 7.6 E-3 2.4 E-2 7.6 E-1 4.9 E+1 8.8 E+5 2.5 E+15 3.8.2 Record the selected extrapolation factor in column 8 of Exhibit 3.4.1-1.

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! j: BSEP/Vol. XIII/ PEP-03.4.1 8 Rev. 5 ,, ,

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l 3.8 . 3 If the release is not from the stack, use Table 3.4.1-5.

Read across the appropriate row based on distance from the~

C plant to the extrapolation factor under the atmospheric stability class determined in Step 3.3.

s TABLE 3.4.1-5 EXTRAPOLATION FACTOR FOR ESTIMATING DOSES BEYOND BSEP PROPERTY BOUNDARY (4,000 ft.) GROUND LEVEL RELEASE I DISTANCE i FROM PLANT EXTRAPOLATION FACTORS BY ATMOSPHERIC STABILITY CLASS Miles km A B C D E F G 1 1.6 4.3 E-1 5.8 E-1 6.1 E-1 6.4 E-1 6.3 E-1 6.5 E-1 6.5 E-1 2 3.2 5.3 E-2 1.5 E-1 1.7 E-1 2.2 E-1 2.3 E-1 2.3 E-1 2.4 E-1 3 4.8 1.6 E-2 6.5 E-2 8.4 E-2 1.2 E-1 1.3 E-1 1.3 E-1 1.4 E-1 4 6.4 6.5 E-3 3.7 E-2 4.8 E-2 7.8 E-2 8.4 E-2 9.3 E-2 1.0 E-1 ,

a 5 8.0 3.4.E-3 2.4 E-2 3.2 E-2 5.6 E-2 6.3 E-2 7.0 E-2 7.6 E-2 6 9.7 2.0 E-3 1.6 E-2 2.4 E-2 4.2 E-2 4.9 E-2 5.6 E-2 6.1 E-2 7 11.3 1.2 E-3 1.2 E-2 1.8 E-2 3.4 E-2 4.0 E-2 4.4 E-2 5.0 E-2 8 12.9 8.2 E-4 9.1 E-3 1.4 E-2 2.8 E-2 3.4 E-2 3.7 E-2 4.3 E-2 9 14.5 5.8 E-4 7.3 E-3 1.2 E-2 2.3 E-2 2.9 E-2 3.3 E-2 3.8 E-2 10 16.1 4.3 E-4 5.9 E-3 9.4 E-3 2.0 E-2 2.5 E-2 2.8 E-2 3.3 E-2 3.8.4 Record selected extrapolation factor in column 8 of Exhibit 3.4.1-1.

3.9 '

To obrain projected dose at points beyond the property boundary, multiply column 7 x column 8 = column 9. Record the product in column 9 of Exhibit 3.4.1-1. Indicate the distance from the property boundary the projected dose represents.

3.10 Report the projected doses to the Site Emergency Coordinator or Radiological Control Director.

3.11 Repeat this procedure whenever source term or meteorological i conditions change or as directed.

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BSEP/Vol. XIII/ PEP-03.4.1 9 Rev. 5 ,. '

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CAROLINA POWER & LIGHT COMPANT BRUNSWICK STEAM ELECTRIC PLAST UNIT 0 .

1 RELEASE ESTIMATES BASED UPON STACK / VEST READINGS

' PLANT EMERGENCY PROCEDURE: PEP-03.6.1 VOLUME XIII 4

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Rev. 003 1

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.h 1 Reccceended By: Date: 4[7[F3-Director-Adj6istrative Support Approved By: t. N Date: ^($

General Manager dj l ,

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LIST OF EFFECTIVE PAGES PEP-03.6.1

. Page(s) Revision 1-9 3 -

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i BSEP/Vol. XIII/ PEP-03.6.1 i Rev. 3 '>

1.0 Responsible Individual and Objectives The Radiological Control Director is responsible to the Site Emergency Co'ordinator for determining.the magnitude and rate of radioactive release to the environment. The Radiological Control Director may delegate the calculational aspects of this procedure to the Dose Projection Coordinator.

2.0 Scope and Applicability This procedure shall be implemented by the Site Emergency Coordinator, or by the Radiological Control Director, whenever a radiological release through an identifiable release point is suspected, including any Site or General Emergency. The only apparatus required is a scientific calculator, r

3.0 Actions and Limitations NOTE: The detector response (uC1/cc of radioactivity per counts per minut'e or mr/hr)' will depend on the specific isotopic mixture being released at various times. Grab samples must be taken, analyzed and evaluated by use of PEP-3.6.3, " Interpretation of Liquid and Gaseous Samples," to provide an exact relationship; however, the predetermined relationship used ,in this procedure should be sufficiently accurate to guide initial emergency response actions and assessments.

s List of EXHIBITS:

3 . '6 .1 - 1 Source Term Calculation from Plant Stack Monitors 3.6.1-2 Source Term Calculation from #1 RX Gas (1-CAC-AQH-1264-3) 3.6.1-3 Source Term Calculation from #1 Turbine Gas (1-VA-AQH-3215-3) 3.6.1-4 Source Term Calculation from #2 Rx Gas (2-CAC-AQH-1264-3) 3.6.1-5 Source Term Calculation from #2 Turbine Gas (2-VA-AQH-3215-3) 3.6.1-6 Source Term Calculation from #1 and/or #2 Turbine Building Vent (High Range) 3.6.1-7 ET -Time O to 72 Hours After Reactor Shutdown 3.1 Depending upon alarming channel (s), use appropriate EXHIBIT (EXHIBIT 3.6.1-1 through EXHIBIT 3.6.1-6) to calculate the release source term. -

Note: If the time duration of the release is unknown, assume 60 minutes and perform this procedure as directed by the Radiological Control Director.

If only one channel is alarming or reading abnormally high, the source term determined on the appropriate EXHIBIT is the total. If two monitors are measuring the same source term, use the average reading of the two. ,

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l i BSEP/Vol. XIII/ PEP-03.6.1 1 Rev. 3 ,,

3.2 If multiple radiation monitors are alarming, (and not monitoring the same point) calculate the indiv' dual source terms and sum them to

( obtain the total source term.

3.3 Report the source term to the Radiological Control Director (Radio-logical Control Manager after the Emergency Operations Facility is activated) for use in appropriate dose projection procedure from PEP-Section 3.4. -

3.4 Stack monitor 2-D12-RR-4600 reads directly in pCi/see when flow instrument loop 2-VA-FT-3359 is operational. No calculations are

.. required for source term determination with these instruments operational.

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! BSEP/Vol. XIII/ PEP-03.6.1 2 Rev. 3 ,,'

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EXHIBIT 3.6.1-1

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SOURCE TERM CALCUCATION FROM STACK MONITORS l

' ' EFFICIENCY' METER * . FACTOR RELEASE" READING FLOW' VCi/sec -

RATE TIME (yCi/cc) (CFM) CFM-sec (yCi/sec) l

(

1 Monitor selects most accurate operational channel, either low, mid, or high range.

8 If not available, use sum of design flows for systems exhausting to stack:

Steam Jet Air Ejectors (A & B) 3U0 SCFM ea.

Rad Waste Bldg. Vent (2 fans) 23,100 SCFM ea.

Purge Fans (2 fans) 7,200 SCFM ea.

Standby Gas (per train - 2 trains) 3,500 SCFM ea.

The efficiency factor is channel item 011, accessible at display 2-D12-RM-235.

Release Rate = UCi/cc x cfm x 472 Release rate is read in uCi/sec directly from D12-RR-4600 when 2-VA-FT3339 flow instrument loop is operational.

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i BSEP/Vol. XIII/ PEP-03.6.1 3 Rev. 3 ,.

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EXHIBIT 3.6.1-2 C SOURCE TERM CALCULATION FROM (11 Rx GAS (1-CAC-AQH-1264-3) i METER

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RELEASE (3)

READING FLOW (1) EFFICIENCY (2) RATE TIME (com) (cfm) FACTOR (uCi/sec)

(1) If not available use 43,200 cfm per discharge fan times the number of fans operating.

( The efficiency factors posted on the front panel of the stack, reactor buildings monitors. If not posted, these values can be obtained'from

.E&RC File 13324, or use 8.6E-6.

I(3) Release Rate = cpm X cfm X Efficiency Factor

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, l-I BSEP/Vol. XIII/ PEP-03.6.1 4 Rev. 3 j

l EXHIBIT 3.6.1-3  ;

SOURCE TERM CALCULATION FROM #1 TURB1NE GAS (1-VA-AQH-3215-3) (LOW RANGE)

- C3)

METER RELEASE READING FLOW II) EFFICIENCY (2) RATE TIME (cpm) (cfm) FACTOR (uCi/sec)

% =

l (1) If not available use 15,000 cfm.

() The efficiency factors posted on the front panel of the stack, reactor buildings monitors. If not posted, these values can be obtained from RC&T File 13324, or use 1.24E-5.

(3) Release Rate = cpm X cfm X Efficiency Factor L

BSEP/Vol. XIII/ PEP-03.6.1 5 Rev. 3

EXHIBIT 3.6.1-4 SOURCE TERM CALCULATION FROM #2 Rx GAS (2-CAC-AQH-1264-3)

RELEASE C3)

METER READING FLO'4(1) EFFICIENCY ( ) RATE TIME '(cpm) (cfm) FACTOR (uCi/sec)

() If not available use 43,200 cfm per discharge fan times the number of fans operating.

() The efficiency factors posted on the front panel of the stack, reactor buildings monitors. If not posted, these values can be obtained from RC&T File 13324, or use 9.26E-6.

(3) Release Rate = cpm X cfm X Efficiency Factor

, L h BSEP/Vol. XIII/ PEP-03.6.1 6 Rev. 3

EXHIBIT 3.6.1-5 SOURCE TERM CALCULATION FROM #2 TURBINE GAS (2-VA-AQH-3215-3) (LOW RANGE)

METER RELEASE (3)

READING FLOW II) EFFICIENCY ( ) RATE J TIME (com) (cfm) FACTOR (uCi/sec)

(1) If not available, use 15,000 cfm.

() The efficiency factors posted on the front panel of the stack, reactor buildings monitors. If not posted, these values can be obtained from RC&T File 13324, or use 1.11E-5,

() Release Rate = cpm X cfm X Efficiency Factor a.

BSEP/Vol. XIII/ PEP-03.6.1 7 Rev. 3

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.. i EXHIBIT 3.6.1-6  !

Source Term Calculation from Unic No. I and/or Unit No. 2 Turbine Building Vent (High Range)

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Indicated Dose, R/hr TDIPORARY CASEOUS EFFLUENT RADIATION MONITORS To determine total release activity (curies /sec) from a Turbine Building vent:

1. Read the " actual specific activity (curies /ce)" from the graph as a function of the dose rate (R/hr) indicated on the meter.
2. Read flowmeter for the specific release point (SCD1) .
3. Calculate Total Release (C1/sec) = Specific Activity (C1/cc) x Flow Rate (SCRI) x 28300 (cc/SCF) x .0167 (min /sec)

Graph parameters based on the projected isotopic distribution 30 minutes after a TMI-based accident.

Reference:

PM-79-296.

I aSEP/Vol. XIII/ PEP-03.6.1 8 Rev. 3 .

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EXHIBIT 3.6.1-7 ET - TIME O TO 72 HOURS AFTER REACTOR SHUT DOWN TIME _ET

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0 0.720' i

.5 0.680 1.0 0.520

, 1.5 0.480 3 2.0 0.37C I

2.5 0.390 3.0 0.380

i. 3.5 0.360 4.0 0.320 4.5 0.300 5.0 0.280 3 6.5 0.230 i- 8.0 0.200
, 10.0 0.170 l 12.5 0.130 15.0 0.140 4

24.0 0.096

( 48.0 0.040 72.0 0.048 I

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BSEP/Vol. XIII/ PEP-03.6.1 9 Rev. 3

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