ML20063C700

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure HP/0/1009/10 Re Procedures for Quantifying Gaseous Releases Through Steam Relief Valves Under post-accident Conditions
ML20063C700
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 05/06/1982
From: Coy S, Owen T
DUKE POWER CO.
To:
Shared Package
ML15238A611 List:
References
PROC-820506-01, NUDOCS 8206300101
Download: ML20063C700 (8)


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DUKE P01JER COMPANY (1) ID No: HP/0/8/1009/16 PROCEDURE PREPARATION Change (s) I to l PROCESS RECORD NA Incorporated f

(2) STATION: Oconee i (3) PROCEDURE TITLE: Procedure for Emeraency Decontamination of Persnnnel i

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l DUKE POWER COMPANY (1) ID No: HP/0/B/1009/1%

PROCEDURE PREPARATION Change (s) I to PROCESS RECORD N/A Incorporated j (2) STATION: ocnno, l (3) PROCEDURE TITLE: Procedure for nunntifvine Caseous Releases Throuch i

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DUKE POWER COMPANY OCONEE NUCLEAR STATION PROCEDURE FOR QUANTIFYING GASEOUS RELEASES THRU STEAM RELIEF VALVES UNDER POST-ACCIDENT CONDITIONS 1.0 Purpose This procedure describes the method used for calculating total noble gas and radioiodine activities released thru steam relief valves following a q nuclear accident.

2.0 Re ferences 2.1 Technical Specifications, Oconee Nuclear Station, Appendix A, Section 3.1.4, Reactor Coolant System Activity.

2.2 FSAR, Oconee Nuclear Station, Section 11.1.2.4, Process Radiation Monitoring.

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"1 3.0 Limits and Precautions j ,

3.1 Carefully review the date and time of the steam release with the j date and time of the RIA readings. RIA 16 and 17 readings will vary

relative to the date and time of the steam release. Although they l may not exist, the most conservative monitor readings will be recorded j just prior to open or just after close of the steam relief valves.

1 4.0 Procedure 4.1 Obtain and record, on Enclosure 5.1, the following information for i the particular unit following a steam release.

4.1.1 The unit number.

4.1.2 The date of the steam release.

4.1.3 The time the steam release started.

4.1.4 The time the steam release ended.

4.1.5 The RIA 16 and 17 net mr/hr readings.

4.1.6 The date and time the RIA readings were recorded.

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l l 4.2 Calculate the duration of the release (T), in minutes, by subtracting the start time from the end time.

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(c!C j 4.2.1 Record T on Enclosure 5.1. ,

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4.3.1 R, = (R s + Rt7) 0.5 i

4.3.2 Record R, on Enclosure 5.1.

l 4.4 Calculate the total gas concentration (C) as follows:

1 4.4.1 C = (Ra) (.03 /[")

4.4.2 Record the total gas concentration (C) in pCi/ml on Enclosure 5.1.

4.5 Calculate the noble gas activity released.

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4.5.1 An = C x T x 8.95 x 102

! A = Total noble gas released in curies C = Total noble gas concentration, in pCi/ml, of the steam release (fi W' T = Duration of the steam release in minutes.

i 8.95 x 10, = 63,330 ft3 x 2.832 x 104 ml/ft3 x 1 x 10 6 Ci/pCi

2 Min.

l j 63,330 ft3 = Steam volume released in a 2 minute period.

. This is based on releasing 1.5 x 10 5 lbs

.i of steam at 1050 psia with a 2 minute ll average steam release rate of 0.4222 ft 3/lb-m.

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NOTE: T is actually the numerator in a correction factor ( T ) used for adjusting the assumed (2 min) y release volume of 2 minutes to the actual release volume in T minutes.

4.5.2 Record the noble gas activity released (An) on Enclosure 5.1.

I 4.6 Calculate the radiciodine activity released.

4.6.1 A7=A x 0.05 A = Total radiciodine released in curies 3

A = Total noble gas released in curies.

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0.05 = The fraction of the total activity in the reactor (h:r)) coolant system which is equal to the radioiodine

%' activity. No coolant activity d,ecay assumed.

4 4.6.2 Record the radioiodine activity released on Enclosure 5.1.

4.7 Initial the appropriate box in the coiumn marked "Pertormed sy". .

4.8 Record the date the calculations were performed.

5.0 Enclosures

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! - Table of Contents (Implementing Procedures - Continued)

.j CP/2/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81)

CP/3/A/2002/04B Post Accident Liquid Sampling of the Low l Pressure Injection System (12/01/81)

I CP/0/A/2004/2C Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter (04/26/82, Original Issue) i j CP/0/A/2004/2E Post Accident Determination of Boron Concentration j Using Carminic Acid (04/26/82, Original Issue)

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CP/0/A/2005/2D Post Accident Determination of Gamma Isotopic l Activity (04-26-82, Original Issue) l

'i CP/0/B/4003/01 Procedure for Environmental Surveillance i Following a Large Unplanned Release of

Gaseous Radioactivity - (01/13/82) i

! CP/0/B/4003/02 The Determination of Pluine Direction and Sector (s)

'l to be Monitored Following a Large Unplanned i , Release of Gaseous Activity - (08/20/81) v7s HP/0/B/1009/09 Procedure for Determining the Inplant Airborne

{ Radioiodine Concentration During Accident Conditions - (07/09/81)

'! HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases Through Steam Relief Valves Under Post-Accident Conditions - (05/06/82)

HP/0/B/1009/11 Projection of Offsite Dose from the Uncon-trolled Release of Radioactive Materials Through a Unit Vent - (07/08/81)

.{ HP/0/B/1009/12 Distribution of Potassium Iodide Tablets in

' the Event of a Radioiodine Release - (03/02/82)

HP/0/B/1009/13 "

Procedure for Implementation and Verification

$ for the Availability of a Back-Up Source of Meteorological Data - (04/23/82)

HP/0/B/1009/14 Project Offsite Dose from Releases other i than Through a Vent - (01/29/82)

. HP/0/B/1009/15 Procedure for Sampling and Quantifying High li Level Gaseous Radioiodine and Particulate ll N;7 ' Radioactivity - (04/29/82) 7 EPM 001/A Revision, 06/02/82

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_ Table of Contents (Implementing Procedures - Continued)

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j i (Gl.)'lf HP/0/B/1009/16 Procedure for Emergency Decontamination of Personnel and Vehicles on-site and from Off-site Remote Assembly Area - (03/02/82)

IP/0/B/1601/03 Environmental Equipment Checks - (04/08/82)

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