ML20006B024
| ML20006B024 | |
| Person / Time | |
|---|---|
| Issue date: | 01/24/1990 |
| From: | Trottier E Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Sniezek J NRC |
| References | |
| NUDOCS 9001310210 | |
| Download: ML20006B024 (5) | |
Text
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January 24, 1990 MEMORANDUM FOR:
T. Murley B. Grimes P. McKee J. Sniezek F. Congel A. Thadani F. Miraglia, ADT J. Roe C. McCracken J. Partlow, ADP C. Grimes C. Haughney D. Crutchfield, ADSP B. Boger J. Dyer, EDO S. Varga G. Lainas F. Gillespie G. Holahan W. Travers W. Bateman C. Rossi B. D. Liaw T. Cox J. Richards.on E. Butcher J. Zwolinski THRU:
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II FROM:
Ed Trottier, Project Manager Project Directorate I-2 Division of Reactor Projects I/II
SUBJECT:
DAILY HIGHLIGHT - FORTHCOMING MEETING WITH BWROG llSIV AND LEAKAGE CONTROL SYSTEM COMMITTEE - (REVISION 1 DATED JANUARY 19,1990)
DATE & TIME:
January 25, 1990 i
One White Flint North 11555 Rockville Pike Rockville, MD Room 10B11 PURPOSE:
Discuss assumptions and mathematical model for radiological aspects of main condenser.
PARTICIPANTS:
NRC UTILITY Wu"'tler CShiraki TGreen CMcCracken Shou BBinz JKudrick RAnand CTu11y LMarsh JMazetis RLewis JCunningham CGraves JLee FWitt ETrottier HBrammer PKuo CGraves pA hfD \\
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Ok Ohdh [$ Q Ed Trottier, Project Manager C
PI:C Project Directorate 1-2 Division of Reactor Projects I/II y,
l cc: See next page NOTE: This Meeting Notice revised to include attached Table of Assumptions
Attachment:
As stated MC F1E CENTER COPY DPoI iu
DISTRIBUTION C"CitiEMaNHil.I)
NRC & Local PDRs PDI-2 Reading T. Murley/J. Sniezek D. Crutchfield S. Yarge B. Boger ETrottier W. Lanning OGC E. Jordan B. Grimes Receptionist - OWFN WButler JKudrick Liiarsh JCunningham JLee PKuo CShiraki Shou RAnand JMazetis CGraves FWitt HErammer CGraves ACRS(10)
GPA/PA V. Wilson L. Thomas JDyer,ti/S 17G21 K. Abraham, Region 1 M0'Brien 4
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_________.______m.._.
ATTACHMENT i
PROPOSED ASSUMPTIONS AND PARAMETERS TO BE USED r
IN CALCULATING RADIOLOGICAL OFFSITE AND CONTROL ROOM OPERATOR DOSES FOR EVALUATING BWROG OPERATING REACTOR MSIV LEAKAGE CONTROL SYSTEM ELIMINATION PARAMETERS QUANTITIES BASES BWROG 1.
Power level Plant Specific Max. Lic.
2.
Fission Products Released I
from Fuel Iodines 50%
Reg. Guide 1.3 Noble Gases 100%
Radioactivi'y Plate Out within Containment Iodines
[ 0% ]
TBD Noble Gases 0%
Iodine Chemical Forms I
Elemental 91%
Reg. Guide 1.3 Organic 4%
Reg. Guide 1.3 Particulates 5%
Containment Free Volume Plant Specific FSIR 1
t 6.
Reactor Building Free Volume Plant Specific FSAR 7.
Reactor Building Release Rate Plant Specific FSAR 8.
Reactor Building Mixing Efficiency 50%
SRP 6.5.3 9.
MSIV Leak Rate Plant Specific Tech Spec 10.
Primary Containment Leak Rate Plant Specific Tech Spec 11.
ESF System Leak Rate Plant Specific Tech Spec 12.
Containment Spray DF Elemental Iodine Wall Deposition
[0]
TBD Spray
[0]
[0]
I o
2-PARAMETERS QUANTITIES BASES BWROG 13.
Suppression Pool 0F MSIV Leak
[0]
TBD ESF Leak 100 SRP 6.5.5 Containment Leak 10 SRP 6.5.5 14.
Atmospheric Dispersion Plant Specific SER Factors (X/Q) for Bypass Leak and SQTS 15.
Control Room Dispersion Plant Specific III.D.3.4 Factors (X/Q) 16.
Iodine Protection Plant Specific SPLB Factors 17.
SGTS Filter Efficiency Plant Specific SPLB 18.
SGTS Flow Rate Plant Specific SPLB 19.
Containment Pressure Plant Specific SPLB Drawdown Time 20.
Control Roon. Volume Plant Specific FSAR 21.
Iodine Plateout in
[0]
TBD Main Steam Line 22.
Iodine Plateout Constant in Condenser Elemental
[0]
TBD Particulate
[0]
TBD Organic
[0]
TBD 23.
Condenser and Main Plant Specific TBD Steam Line Volume 24.
Condenser and Main Plant Specific TBD Steam Line Surface Area 25.
Deposition Velocity for Iodines (cm/sec)
Elemental
[0]
TBD Particulate
[0]
TBD Organic 0
26.
Control Room Occupancy Factors l
0 to 1 day
- 1. 0 SRP 6.4 1 to 4 days 0.6 4 to 30 days
- 0. 4 i
i f
0 3
I PARAMETERS QUANTITIES BASES BWROG 27.
Breathing Rates (m2/sec)
Offsite 0-8 hr 3.47 x 10 ICRP-2 8-24 hrs 1.74 x 10.4 1-4 days 2.32 x 10.4 4-30 days 2.32 x 10 Control Room 0-30 days 3.47 x 10' ICRP-2 28.
Computer Code TACT 5 TACTS is a FORTRAN code designed to model the possible transport of radionuclides through various compartments (nodes) of a reactor's containment and to the environment, and to report doses at two predefined locations and one user-defined location.
The code is designed to solve a system of ordinary differential equations that are set up by the user to represent the transport of mass between various compartments.
The user designs mathematical models that accurately describe the containment systems.
29.
Computer Nuclear Data File Name "JAYSKIN" 30.
Computer Plant Model File Name "BWRLCS" I
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