ML20203K308
ML20203K308 | |
Person / Time | |
---|---|
Site: | Point Beach |
Issue date: | 12/08/1997 |
From: | WISCONSIN ELECTRIC POWER CO. |
To: | |
Shared Package | |
ML20203K296 | List: |
References | |
PROC-971208, NUDOCS 9712220301 | |
Download: ML20203K308 (7) | |
Text
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NUCLEAR POWER BUSINESS UNIT REMCAP MAJOR.
Revision 0 DRAFT
. REMCAP MANUAL '
December 8,1997
. 1
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- POINT BEACu14UCLEAR PLANT UNIT 1 AND 2 RADIOLOGICAL EFFLUENT AND MATERIALS CONTROL AND ACCOUNTABILITY PROGRAM (REMCAP) MANUAL WISCONSIN ELECTRIC Revision 0 DRAFT December 8,1997 T
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NUCLEAR POWER BUSINESS Unit
-. REMCAP
~ MAJOR -
' Revision 0 DRAFT REMCAP MANUAIf Vecember 8,'1997-r HTABLE OF CONTENTS L
Ll.0 RADIOLOGICAL EFI LUENT ANT MATERIALS CONTROL AND_ ACCOUNTABILITYo P ROG RAM ( RE M C A P).................................................................
1 1.1 Basis................................................................................................................................................!
1.2 REM C AP_ Organizati on..................................................:......................................................
1.3 Loca ti o n o f Fo rm e r RETS I t ems..............................................................................
z J
22.0DEFIN'TIONS.................................................................................................................................2-
- 2.1. Lower L evel o f Det e c ti o n ( L L D)...............................................................
L. 2 M e mbers o f the P ublic.................................................................. 1 2
[
2.3 Offsite Dose Calculation Manual (ODCM)...................................................................................... 3 2.4 Proc e s s Control Program (PC P).............................................................................................
- 2. 5 S o l i d i fi ca t i o n.....................................................................................
n I
2. 6 Unres t ri c t e d Area.....................................................................................
- 2. 7 Annual Release Limi t..............................................................................................
I i
2,8 Q uarte rly Release Limit...........................................................................................................
.o 3.0 REVISIONS.,..................................................................................................................................4 4.0 P ROG RA M I M P L E M ENTATI ON ;.................................................................................................... 4
. 5.0 EPO RTW G REQ U I RF.h1ENTS................................................................................
I5.1REMP............................................................................................................................................4-
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- 5.7 R E. C P...................
............................................................................)
L5.3'SolidWaste................................................................................................................................5 i
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NUCLEAR POWER BUSINESS UNIT-'
- REMCAP MAJOR Revision 0 DRAFT
- REMCAP MANUAL-December 8,1997 t
1.0 -
RADIOLOGICAL EFFLUENT AND MATERIALS CONTROL AND ACCOUNTABILITY
- PROGRAM (REMCAP) 1.1 ~ ' Basis The Point Beach Nuclear Plant's Radiological Ellluent and Materials Control and Accountability Program (REMCAP) is designed to comply _with Federal Regulations for ensuring the safe operation of the Plant with respect to releases of radioactive mateilal to -
the environment and its subsequent impact on the public.10 CFR 50.34a states that H
operations should be conducted so as to keep the levels of raaicactive material in effluents to unrestricted areas as lo
.s reasonably achievable (ALARA). In 10 CFR 50,.
Appendix 1, the NRC provides numerical values for what it considers to be the appropriate ALARA dose objectives to which the licensee's calculated effluent doses may be compared. These doses are a small fraction of the dose limits specified by 10 CFR 20.1301 and lower than the EPA limit in 40 CFR 190.10 CFR 20.1302 directs the licensee to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. This monitoring requirement (also found in the General Design Criterion (GDC) 64 of Appendix A to 10 CFR 50 and in PBNP GDC 17) is implemented in order to control effluent releases as required by PBNP GDC 70 and GDC 60 of Appendix A to 10 CFR 50. PBNP GDC 70 and GDC 60 of Appendix A to 10 CFR 50 also address the need for control of solid waste material. In order to confirm that the appropriate controls have been applied to effluents, surveys are conducted of.
g unrestricted areas in the PBNP environs as required by 10 CFR 20.1302, PBNP GDC 17, G
GDC 64 of Appendix A to 10 CFR 50, and Section IV.B.2 of Appendix 1 to 10 CFR 50.
The surveys provide data on levels of radiation and radioactive materials in the environment in order to evaluate the relationship between quantities of radioactive material released in effluents and the resultant radiation doses to individuals from principle exposure pathways.
1.2 REMCAP Orcanization In order to achieve the concol and accountability required by n deral regulations, REMCAP contains the following elements: a Radiological Efiluent Control Program (RECP) to assess and control radioactive material in liquid and gaseous effluent, a Pmcess Control Program (PCP) for waste solidification, a Radiological Environmental
. Monitoring Program (REMP) for assessing radioactive materials in the environment, and an C.Tsite Dose Calculation Manual (ODCM) containing the methodology for calculating -
' doses to the public from PBNP effluents. These elements of the REMCAP are defined in PBNP Technical Specification 15.7.8.
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- NUCLEAR POWER BUSINESS UNITL
- REMCAP.:
- MAJOR -
Revision 0 DRAFT
' REMCAP MANUAL-December 8,1997 --
. l.3f Location of Former RETS Items 1.3.1 -
Monitoring Instrumentation, is now in Sec*. ion 3 of the Radiological Effluent -
. Control Manual (RECM).
1.3.2' Monitoring Instmmentation Surveillance Requirements, is now in Section 4 of the RECM.
' l.3.3 -
Fonver RETS 15.7.5, Radioactive Effluent Release Limits, is now in Section 5 of the RECM.
i I
1.3.4 -
Former PETS 15.7.6, Radioactive Eftluent Sampling and Analysis Requirements, is now in Section 6 of the RECM.
1.3.5 Former RETS 15.7.7, Operational Environmental Monitoring, is now in the Environmental Manual, i
2.0 DEFitilTIONS i-The definitions for frequently used terminology in the REMCAP are stated below:
2.1 Lower Level of Detection (LLD)
The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank observation represents a real signal. For a particular measuren'ent system, which may include radiochemical separation:
LLD =
6 E x V x 2.22 x 10 x Y x exp (4.At)
Where:
the a priori lower limit of detection as defined above, in microcuries per i
=
unit volume or mass as applicable.
the standard deviation of the background counting rate or the counting rate -
Sb
=
of a blank sample as appropriate in counts per minute,
-E.
= the counting efficiency in counts per disintegration, the sample size in units of volume or mass as applicable, V
=
2.22 x 104 the number of disintegrations per minute per microcurie,
=
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NUCLEAR POWER BUSINESS UNIT REhiCAP hiAJOR Revision 0 DRAFT
' REhiCAP hiANUAL December 8,1997 i
the fractional radiochemical yield, when applicable, Y
=
i the radioactivity decay constant for the particular radionuclide, and A
=
for plant effluents,6t is the elapsed time between the midpoint of sample at
=
collection and time ofcounting: for environmental samples, at is the elapsed the between sample collection, or end of the collection period, and the time of counting.
1 Typical values of E, V, Y, and at will be used in the calculation. It should be recognized that the LLD is defined as an a pr'ori (before the fact) limit representing the capability of a measurement system and not as an a nosteriori (after the fact) limit for a particular measurement.
2.2 hiembers of the Public -
hiembers of the public include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors.
Aiso excluded from this category are persons who enter the site to service equipment or
- make deliveries. This categ 7 oes include persons who use portions of the site for d
recreational, occupational, at other purposes not associated with the plant.
2.3 Offsite Dose Calculation hianual (ODChi)
The Offsite Dose Calculation hianual contains the methodology for the determination of gaseous and liquid effluent monitoring alann or trip setpoints, the methodology for detenuirdng compliance with release limits, and the methodology used in the calculation
, of olisite doses due to radioactive gaseous and liquid elliuents.
2A Process Control Procram (PCP)
The Process Control Program contains the methodologies used to ensure that the processing and packaging of solid radioactive waste will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, and all other applicable Federal and State regulations as well :s burial grourd requirements governing the disposal of the r:,dioactive waste.
2.5 -
Solidification The conversion ofliquid wastes into a fonn that meets shipping and burial ground requirements.
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NUCLEAR POWER BUS.tNESS UNIT REMCAP MAJOR Revision 0 DRAFT REMCAP MANUAL December 8,1997 2.6 Unrestricted.AtG An unrestricted area is any area at or beyond the site boundary where access is not controlled by the licensee for purposes of protection ofindividuals from exposure to radiation and radioactive materials.
. 2.7 Annual Release Limit The quantity of radioactive material, above background, in PBNP cffluent which results in a calculated dose to the maximum exposed individual (MEI) or the air which equals j
the dose objectives of Appendix 1 to 10 CFR 50.
l
_ uarterly Release Limit 2.8 O
The quarterly release limit is defined as H the corresponding annual limit.
3.0 REVIS!QN_j l
Revisions to the various REMCAP program manuals must be documented and kept for the l
duration of the PUNP operating license. The revisions shali conform to TS 15.7.8.6 and 15.7.8.7.
i Revisions to the ODCM and the Environmental Manual (EM) are made, as necessary, by the Radiological Engineering (RE) in concurrence of the PBNP Managers' Supervisory Staff (MSS).
Revisions to the PCP and to the Radiological Effluent Control Manual (RECM) are the responsibility of the Manager.llealth Physics, with the concurrence of the PBNP MSS.
4.0 PROGRAM IMPLEMENTATION
, The responsibilities for implementing the requirements of the ODCM reside with the manager and staff of the RE. The responsibility for implementing the requirements of the EM, the PCP,
- and the RECP reside with the Manager-PBNP.
5.0 REPORTING REOUIREMENTS 5.1 EfME Results from the REMP for the twelve month period, or fraction thereof, ending December 31, shall be reported to the NRC in the Annual Monitoring Report by May 1 of the following year. In addition to a summary of the REMP results as described in RETS 15.7.8.4, the radioanalytical REMP results from the vendor and the vendor's QA program results shall be included in the Armual Report or as a sepan te, concurrent nubmittal.
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NUCLEAR POWER BUSINESS UNIT REMCAP MAJOR Paision 0 DRAFT REMCAP MANUAL December 8,1997 5.2 RECE Results from the RECP effluent measurements shall be included in the Annual Monitoring Report. Results shall include monthly summaries nnd quantities ofliquid waste and liquid used in dilution as well a monthly isotopic results of principle radionuclides released as specified in RETS 15.7.8.4. The Annual Monitoring Report also shall include the doses from effluent calculated according to ODCM methodology.
5.3 Solid Waste The isotopic content of solid waste shipments from PBNP shall be reported in the Annaal Monitoring Report in addition to the requirements of RETS 15.7.8.4.
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