ML20217E197

Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening

ML20217E197
Person / Time
Site:	Three Mile Island
Issue date:	03/17/1998
From:	Boughton K, Mccoey R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20217E040	List: E000-98-012, Forwards Rev 0 to Topical Rept TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident for Review & Approval by 980630 to Support Planned TS Change Requests Addressing TMI-1 NRC Insp Open Items ML20217E081 ML20217E117 ML20217E166 ML20217E197
References
C-1101-826-E540, C-1101-826-E540-025, C-1101-826-E540-25, NUDOCS 9803300406
Download: ML20217E197 (33)

Text

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' VG uuCLEAn U CALCULATION COVER SHEET I

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Calculation Number: Rev. # System Number (s)

C-1101826-E540-025 0 826 Sheet 1 of 33 I

Calculation

Subject:

X/Q @ TMI Ventilation Exhaust Opening Yes No is this calculation within the OQA Plan Scope? X 0 (if Yes, a venfication is required)

Does this calculation contain assumptions / design input that requires onfirmation? O x (if Yes, provide EDTTS No.(s))

is this calculation performed as a design basis calculation? X O (if Yes, identify design basis parameters (section 3.3))

Reference Source Documents (Calculations, Safety Evaluations) (Section 4.3.1.3)

DOCUMENT NO. REV.NO.

C-1101826-E540-022 0 i

1 1

I APPROVALS:

Originator Date K.G.Boughton/ Ng 7 MY/P(

Venfi tion Engineer / Reviewer -

Date.

MA-I))(C]Tk1L} l /4 Section Matsger Date bC4A&O T. 4 % 61 u

- *** n!1F 9803300406 980324

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PDR ADOCK 05000289 p PDR

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Subject:

X/Q @ TMI Ventuation System Exhaust Calc. No. Rev No Sheet No.

C-1101-826 E540-025 0 2 or 33 1

l TABLE OF CONTENTS )

1.0 PURPOSE 3 2.0

SUMMARY

OF RESULTS 3

3.0 REFERENCES

4 4.0 ASSUMPTIONS 4 5.0 DESIGN INPUT 5 6.0 OVERALL APPROACH AND METHODOLOGY 5 7.0 CALCULATIONS 5 8.0 APPENCICES APPENDIX A-YEARLY EXCEL MET FILES 7 APPENDIX B -YEARLY EXCEL MET FILES FORMULAS

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LG NUCLEAN El CALCULATION SHEET

Subject:

X/Q @ TM1 Ventilation System Exhaust Calc. No. Rev.No. Sheet No.

C 1101-826 E540-025 0 3 of 33 1.0 PURPOSE The purpose of this calculation is to determine X/Q values at the TMI Control Building Ventilation System Exhaust opening which acts as an intake under certain failure modes of the ventilation system. This value will be used as part of the dose assessment analysis for control room habitability.

2.0

SUMMARY

OF RESULTS INTERVAL PERCENTILE X/Q 0-8 HOURS 95 2.13E-3 sec/m^3 8-24 HOURS 90 1.44E 3 sec/ma3 14 DAYS 80 9.42E-4 sec/m^3 4-30 DAYS 60 5.09E-4 sec/m^3

Qeu NUCLEAN CALCULATION SHEET

Subject:

X/Q @ TMI Ventdation System Exhaust Calc. No. Rev.No. Sheet No.

C-Il01826-E540 025 0 4 of 33

3.0 REFERENCES

3.1 TMl meteorological data files:

3.1.1 Tmimet76. arc 3.1.2 Tmimet78. arc 3.1.3 Tmimet80. arc 3.1.4 Tmimet81. arc I

3.1.5 Tmimet02. arc 3.1.6 Tmimet96. arc 3.2 EXCEL 97 Calculation Files:

3.2.1 Tmimet76.xis 3 2.2 Tmimet78.xis 3.2.3 Tmimet80.x!s 3.2.4 Tmimet81.xis 3.2.5 Tmimet82.xis 3.2.6 Tmimet96.xis 3.2.7 Averagexq.xis 3.3 GPUN Calculation C-1101829-E540-022, Rev. O, Estimate of (X/Q)U Values for TMI-1 Control Building Ventilation System Exhaust, James Halitsky I

4.0 ASSUMPTIONS Meteorological data for 1976.1978,1980,1981,1982 and 1996 serve as representative data for the site for evaluating X/Q values at the various percentiles of interest. Data which resulted in zero wind speed and would have yielded infinite X/Q values was reviewed to determine if these wind speeds were less than the five percentile speeds for each year. The data for zero speeds was then adjusted to .1 m/s for the cumulative frequency determination.

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4 GPU NUCLEAM CALCULATION SHEET

Subject:

X/Q @ TMI Ventilation System Exhau.a Calc. No. Ro hu. Sheet No.

C.1101-826.E540 025 0 5 of 33 5.0 DESIGN INPUT The referenced meteorological files and reference 3.3 (X/Q)U values at vanous wind sectors serve as input to this calculation.

6.0 OVERALL APPROACH AND METHODOLOGY The referenced EXCEL 97 files were created from the meteorological files for 76, 78, '80, '81, '82, and '96.

The (X/Q)U values in reference 3.3 were inserted into each year of met data as an array Ngu'. The EXCEL 97 " Match' function was used to insert the respective (X/Q)U value at each appropriate wind angle for each hour of met data. The (X/Q)U values were then divided by the hourly wind speed to determine hourly X/Q values. The data was sorted on wind angle and wind speed to separate all of the bad or missing data for that particular year. The EXCEL 97

• Percentile

• function was used to determine the cumulative frequency of the X/Q and to extract the 95 th,90 th,80 th, and 60 th percentiles for each year. These values were then avetaged for the repsective years evaluated to determine the result.

7.0 CALCUL.ATION The average value X/Q's for the years evaluated is contained in file Averagexq.xis.

The individual yearly percentiles are contained in files:

Tmimst76.xis Tmimet78.xis Tmimet80.xis Tmimet81.xis l

Tmimet82.xis l l

Tmimet96.xis  !

Portions of the yearly files are contained in Appendix A.

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X/Q @ TMI Venuladon System Exhaust C. tic. No. Ra. No. Sheet No.

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e Sheet 2.'2. of 33 C-1101-826 E540 025 NUCLEAR VERIFICATION PLAN /

SUMMARY

SHEET (EP.006) scope of Venncation Venty calculabon assumpoons, methods. and that the results are reasonable in accordance with EP.006 requirements.

Item No. Method / Depth of Venncation Required Reg'd Compi. Date i 1 Design review or attemate method to venfy X/Q values are detemined correctly from the met data and Halitsky calculation (C-1101826-E540-022). Given the input, ,

assumptions and methodology, venfy the results are accurate and appropriate.

Document the results of verfication summarizing scope, methods, and results.

Complete venfication checklist. Assigned to K. Woodard.

Assigned Verification Engineer Keith Woodard - PLG. Inc. cuanned per 4 41.3 b O Yes gasved Justincanon for Waiver See attached me o E540-98-011 section Manager (su)(san) M , khg cate hyf Summary of venfication scope, ethodsjresults and conc 3 ions.

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1. d " N' Based on this evaluation, the calculation is venfied to be acceptable. [

Venfication Engineer (pnnt) jg'h g g hgj) ($,gn3 [ // [g, ese V.;,'.f f Use additional sheets if necessary

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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Ma m.9xa r).d.u

\GUNUCLEAR subject: DESIGN VERIFICATION WAIVER Date: March 4,1998 FOR MR. KEITH WOODARD From: R. J. McGoey - Manager, Location: Morris Corp. Center Mechanical / Structural Engineering E540-98-011 To: File Ref.: Resume of Mr. Keith Woodard (attached)

This letter is the waiver of Responsible Technical Reviewer (RTR) requirement for Mr.

Keith Woodard to design verify GPUN Calculation C-1101-826-E540-025 Rev. O.

Mr. Woodard has 38 years of experience and is considered an expert in the subject of atmospheric transport also an expert on TMI atmospheric conditions which he has conducted numerous studies on that subject. The referenced resume for Mr. Woodard, which is also attached, summarizes his extensive experience. This experience, coupled with his demonstrated knowledge, confirms he satisfies the criteria for design verification of Section 4.4.1 of GPUN Calculation Procedure 5000-ADM-7311.01 (EP-006) of being competent in the subject matter of the calculation, qualified to perform the work being verified and knowledgeable on the impact it may have on nuclear and radiological safety.

Mr. Woodard has also been independent of the preparation of the calculation. Mr.

Woodard is qualified to design verify this calculation.

111 9 R. . McGo Extension 7950 RJM\cc Attachments Cc: K. G. Boughton - Engineer, Mechanical /Stmetural Engineering

m: .::w nma i

C.- \tol-926 - Es43-ot.f~

., 3MMET 2 8 eF 33 KEITH WOODARD

SUMMARY

Vice President, Washington, DC Area Office and senior engineer with PLO. Thirty-three years of experience in atmospheric dispersion modeling and analysis, radionuclide and chemical dose assessment / reconstruction, and probabilistic risk assessment. Has been directly involved in meteorological data collection and analysis, dispersion assessments, dose calculations, and emergency planning at more than half of the U. S. commercial nuclear power plant sites and at U.S. National Laboratories.

EDUCATION: Graduate Courses in Reactor Design and Safety Analysis, Catholic University, Washington, D.C., 1966-1967 Certificate, International Institute of Nuclear Science and Engineering, Argonne National Laboratories,1964 M.S., Nuclear Engineering, University of California at Los T Angeles,1%3 B. A.l Physics, Occidental College,1 % 1 RECENT EXPERIENCE: Responsible for development and continuous support of the computerized MeteorologicalInformation and Dose Assessment System (MIDAS) used in support of emergency plannmg, training, and response at more than 30 U.S. nuclear plant sites. Directed development of the chemical version of MIDAS to include assessment of chemical spills for use by the chemical process industry to support emergency planning activities at more than 35 facilities.

Continues to serve as an expert witness in support of the ongoing legal process following the Three Mile Island Unit 2 accident.

Immediately following the accident, became involved in assessing the radiation exposure in the vicinity of the plant. Working as the utility representative, developed computer models to reconstruct the fission product release source term using environmental measurements and site meteorological data.

Responsible for developing the first site-specific model (CRACIT program) to assess reactor accident consequences, which has been used in probabilistic risk assessments for more than 12 plants.

Directed development of the CRACEZ consequence model, which incorporates three-dimensional wind fields, a complex evacuation dose model, and time-dependent releases.

1

C.- no t - 0 Ue - Er +o -o 2f SWt!Ef 2.9 of: 33 OTHER EXPERIENCE: Extensive involvement in the development of radiological accident consequence codes, which required working closely with many representatives from nuclear utilities and the U.S. National Laboratories. Directly involved in dose assessment for the DOE High Flux isotope Reactor facility at Oak Ridge National Laboratory. Developed site specific consequence model for use at Rocky Flats. Project manager for installation of computerized on-line emergency dose assessment models at Los Alamos National Laboratory including both radiological and chemical versions of MIDAS. Served as co-chairman of DOE committee to review chemical dispersion computer models and made recommendations regarding best practices.

Responsible for developing computer models using probabilistic methods to determine atmospheric dispersion factors and accident doses for use in safety evaluations of nuclear plants and chemical process facilities. Developed models for establishing environmental monitoring programs and for plant siting evaluations. Directly responsible for supervising atmospheric dispersion analyses in support of more than 40 applications for approval of power plant sites and licenses, for operation and control of more than 16 weather towers, for 2 major atmospheric dispersion field experiments, and for other field measurement programs.

Responsible for developing computer models to assess environmental effects of cooling tower operations.

Was an active participant in the International Comparison Study of Reactor Accident Consequence Models (benchmark study) conducted by the Organization for Economic Cooperation and Development, and recently chaired an IAEA workshop on accident consequences.

Left the U.S. Atomic Energy Comrrission (AEC) in 1967 to join PLO. From 1963 to 1967 worked as a project leader in the AEC's Division of Reactor Licensing responsible for analysis and evaluation of nuclear safety aspects of power and research reactors.

MEMBERSHIPS: American Nuclear Society i

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SME T- so 4 33 PUBLICATIONS ,

Woodard, K., M: 1. Abrams, J. Lewis, T. J. Celi, M. J. Pine, "Using Offsite Measurements to Estimate Doses from Unmonitored Source Terms," presented at the ANS Sixth Topical Meeting on Emergency Preparedness and Response, April 1997.

Carbone, J. P., W. C. Gekler, C. M. Roy, K. Woodard, " Control Room Habitability During Releases of Toxic Substances," January 19%.

'Woodard K., M. J. Abrams, and J. Lewis, " Resolution ofissues Related to implementation of EPA 400 in Dose Assessment Models," presented at the ANS Sth Topical Meeting on Emergency Preparedness and Response, April 1995.

Abrams M. J. and K. Woodard, " Enhanced Distribution ofInformation Via Networks to Support Emergency Response Activities," presented at the ANS Sth Topical Meeting on Emergency Preparedness and Response, April 1995.

Abrams, M. J. and K. Woodard, " Remote Sensing and Automatic Dispersion Modeling,"

presented at Envirosoft '92, Ashurst, Southhampton, UK, September 1992.

Beychok, M. R., T. E. Fenstermacher, W. R. Fuller, W. C. Gekler, R. W. Myers, and  :

K. Woodard, "Offsite Cosequence Analysis for Rh6ne Poulenc Basic Chemicals Co. Martinez Plant," PLG, Inc., prepared for Stone & Webster Engineering Corporation, PLG-0839, September 1991.

Woodard, K., M. R. Beychok, T. E. Fenstennacher, W. R. Fuller, and W. C. Gekler, "Offsite Consequence Analysis for Rh6ne Poulenc Basic Chemicals Co.," PLG, Inc., prepared for Stone &

Webster Engineering Corporation, PLG-0795, February 1991.

Woodard, K., T. E. Fenstermacher, W. R. Fuller, and W. C. Gekler, "Offsite Cosequence Analysis for Rhone-Poulenc Dominguez Plant," PLG, Inc., prepared for Stone & Webster Engineering Corporation, PLG 0794, November 1990.  ;

1 Woodard, K., M. R. Beychok, T. E. Fenstermacher, W. R. Fuller, and W. C. Gekler, "Otisite Consequence Analysis for Tosco Avon RMPP," PLG, Inc., prepared for Stone & Webster Engineering Corporation, PLG-0791, November 1990.

Woodard, K., T, E. Fenstermacher, and J. Lewis, "The CRACEZ Radiological Consequence Model(with Improved Modeling of Dispersion and Evacuation)," 1990.

'Woodard, K., T. E. Fenstermacher, and N. Addison (Dow), "A Quick Running Personal Computer Model for the Evaporation and Dispersion of Dense Gases," presented at the

. International Conference of Vapor Cloud Modeling, November 1987.

Woodard, K., J. Lewis, and T. E. Fenstermacher, "Using the CRACIT Consequence Mode for Determining Spatial Risk to Suppon Emergency Planning," presented at the PS A '87 Conference.

Zurich, Switzerland, September 1987.

Woodard, K., "The Enhanced CRACIT Computer Code and insights Gained from its L'se."

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c - uot - Oaco -Esp -otf FWEET $1 oF 33 presented to the Technical Committee on Computer Codes for the Probabilistic Assessment of Accident Consequences (IAEA), June 1987.

Woodard, K., "A Touch Screen Man-Machine Interface for Emergency Dose Calculations,"

presented at the ANS Winter Meeting, Los Angeles, California,1987.

Woodard, K., J. Lewis, and M. Abrams, " Computer Trends in Accident Assessment and Routine Data Collection," presented at the HAZMAT '86 Conference, June 1986.

Woodard, K., "Real-Time Microcomputer-Based Dose Computations Using a Three Dimensional Particle Tracking Dispersion Model in MIDAS," presented at the Workshop on Real-Time Computing of Environmental Consequence of a Accident Release to Atmosphere from a Nuclear Installation, Luxembourg, September 1985.

Woodard, K., " Sensitivity of Consequence Results to More Sophisticated Atmospheric Dispersion and Other Modeling Enhancements," presented at the Workshop on Reactor Accident Off-Site ~

Consequence Modeling Assessment and Application, Tokai, Japan, April 1984.

Woodard, K., "Use of the CRACIT Consequence Mode for Real-Time Accident Dose Assessment," presented a the Workshop on Reactor Accident Off Site Consequence Modeling Assessment and Application, Tokai, Japan, April 1984.

Woodard, K., and M. Abrams, " Current Trends in Minicomputer-Based Near-Real-Time Reactor Accident Consequence Predictions," presented at the American Nuclear Society Wm' ter Meeting, ,

Washington, D.C., November 14-19,1982.

Woodard, K., and T. E. Potter, " Consideration of Source Term in Relation to Emergency Planning Requirements," presented at the Workshop on Technical Factors Relating Impacts from -

Reactor Releases to Emergency Planning, Bethesda, Maryland, January 12-13, 1982.

Alpert, D. J., P. H. Gudiksen, and K. Woodard, "Modeling Atmospheric Dispersion for Reactor Accident Consequence Evaluation," presented at the International ANS/ ENS Topical Meeting on Probabilistic Risk Assessment, Port Chester, New York, September 20-24,1981.  ;

Woodard, K., and T. E. Potter, " Assessment of Noble Gas Releases from the Three Mile Island Unit 2 Accident," presented at the American Nuclear Society 25th Winter Meeting, San Francisco, California, November i1-15,1979. 1 l

Woodard, K., and T. E. Potter, " Modification of the Reactor Safety Study Consequence i Computer Program (CRAC) to Include Plume Trajectories," presented at the American Nuclear l Society 25th W~mter Meeting, Saa Francisco, California, November 11-15,1979. j Woodard, K., and T. E. Potter, " Selecting Probability for Use in Direction Dependent Accident Dispersion Models Consistent with Past NRC Praice," Transactions of the American Nuclear Society, Vol. 26, June 1977.

Woodard, K., and T. E. Potter, "Probabilistic Prediction of X/Q for Routine Intennittent Gaseous Releases," Transactions of the American Nuclear Society, Vol. 26, June 1977.

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Woodard, K., " Feasibility of Using Richardson Number for Determining Atmospheric Dispersion," Transactions of the American Nuclear Society 1971 Winter Meeting, Vol. 22, November 1975.

Woodard, K., " Sensitivity of Atmospheric Di%sion Estimates to Meteorological Data Recovery l and Accuracy," Nuclear Technology, Vol. 25, April 1975.

Woodard, K., R. V. Calabrese, and J. Halitsky, " Prediction of Temperature and Moisture Distributions in Cooling Tower Plumes," presented at the Symposium on Atmospheric Di%sion and Air Pollution, sponsored by the American Meteorological Society, Santa Barbara, California, September 1974.

Woodard, K., " Probability Treatment of Atmospheric Dispersion for Dose Calculation," Nuclear Technology, Vol.12, November 1971.

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- l g CALCULATION VERIFICATION CHECKLIST sheet 3s of33 (Ref. EP408)

NUCLEAR caic Title X/Q @ TMI Ventilation Exhaust Opening calc. No. I Rev C-1101826-E540-025 0 Venfication Dy- (Pnnt Name) Secuon Date q Keith Woodard . PLG Inc. j Place a ehoek mark in the appileshie hos (Yes No, N/A) for seek iteen, "NO" niey 8=de==aa the design er eertAsseios is laceanplete regadrhig a task request he ase6 peed by the reopensible Sectisa Manager.

The Section Manager shes reverw ensk "NO" response to deteradme if Task Requese asede to be prepared.

"N/A"(Not Applisekte) dose est regadre any Asether acelen by the Verterealen Eastaser, j The VertArettaa Saunasary (V5)(Eskibet 7A) sesy be used to setene the Vertnestlee Engineer's work er for comuments doesned appropropremes by the Verteretten Endoser.

Review Check ITEMS Design Compliance Yes No N/A Dealan inped & Data -Were the inputs correctly seiected, referenced (latest reveson) and incorporated into the calculaeon? ,

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Annumatinas - Are soeumptene necessary to perform the calcula00n adequately descnDed and reasonable?

Raoulatorv Ragteramenta - Are the applicable codes and standerde and regulatory requiremente, including neue and addenda, property 6dentified and their requiremente met?

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Construction /Onaratina Esmerlance - Has appelcable construction and operating experience been coneedered?

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Igggfagag - Have the design interface requrements been satsened?

Methods - Wee an appropnate calculation method used?

] ]

Qldgigt - le the output reasonable compared to inpute?

] ]

Accantanca Cretaria - Are the acceptance enterte incorporated in the calculation sufficient to allow verification that the design requremente have been - WJ, accompilched? ] ] ]  ;

I Radiation Eamosure - Has the calculatlon poperty considered radiaton exposure to tre pubec and plant personnel? y ] ] ]

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