ML20028D191

Testimony of DC Bley Re Contention 2.2(a).WL Fleisher Statement That Brackish Water Must Be Removed from Containment Bldg Unjustified.Brackish Water Issue Is Primarily Maint Concern.Prof Qualifications Encl

ML20028D191
Person / Time
Site:	Indian Point
Issue date:	01/12/1983
From:	Dennis Bley CONSOLIDATED EDISON CO. OF NEW YORK, INC., PLG, INC. (FORMERLY PICKARD, LOWE & GARRICK, INC.), POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
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ML20028D192	List: ML20028D191 ML20028D194
References
ISSUANCES-SP, NUDOCS 8301170218
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UtiITED STATES OF AMERICA NUCLEAR REGULATORY COMt1ISSIO!I N DEN I4 fj0M9 ATOt!IC SAFETY AND LICENSING BOARD -

Before Administrative Judges: . [: ;, , ,

James P. Gleason, Chairman T'?

Frederick J. Shon Dr. Oscar H. Paris I

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In the !!atter of )

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, COtiSOLIDATED EDISON COf1PANY OF ) Docket Nos.

NEW YORK, INC. ) 50-247 SP (Indian Point, Unit tio. 2) ) 50-286 SP

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POWER AUTHORITY OF THE STATE OF ) Jan. 12, 1983 NEW YORK )

(Indian Point, Unit Flo. 3) )

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LICENSEES' TESTIMONY OF DENNIS C. BLEY ON CONTENTION 2.2(a) i ATTORNEYS FILING THIS DOCUf!ENT:

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Brent L. Brandenburg Paul F. Colarulli i

COtiSOLIDATED EDISON COMPANY Joseph J. Levin, Jr.

OF NEW YORK, INC.  !! ORGAN ASSOCIATES, CHARTERED i 4 Irving Place 1899 L Street, N.W.

New York, New York 10003 Washington, D.C. 20036 (212) 460-4600 (202) 466-7000 "

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i 8301170218 830112 PDR ADOCK 05000247 T PDR 3

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TESTIMONY ON CONTENTION 2.2(a)

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My name is Dennis C. Bley. I am a consultant in reliability, risk, and decision analysis for electrical generating plants at Pickard, Lowe and Garrick, Inc. I was i a principal investigator on the Indian Point Probabilistic

Safety Study. A statement of my professional qualifications is attached.

4 I have read the testimony of Mr. Walter L. Fleisher, l Jr. covering the problems of using brackish water inside the

- containment building. Mr. Fleisher has not established the i

link between brackish water-initiated equipment problems and

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i the probability or consequences of events resulting from such problems.

The brackish water issue is primarily a maintenance concern with minimal implications for health effects risks, even in the unlikely event that containment fan cooler leakage were to go undetected for a long period of time.

D.H. Uhite, D.H. Williams, et al., Indian Point #2 Reactor i

Vessel Structural Evaluation for Accumulation of Water in Containment Incident (Dec. 1980) (attachment to letter from John D. O'Toole to Boyce Grier (Dec. 22, 1980)). Therefore, f Mr. Fleisher's conclusion that "there is no solution other than removing the brackish water from inside the containment building" is unjustified.

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The likelihood of significant flooding due to service water leaks in containment was discussed in the Indian Point Probabilistic Safety Study, S 7.4.2.2.5:

The detailed investigation into the causes and consequences of the Unit 2, October 17, 1980, flooding event has lead to numerous hardware and admin-istrative changes for both units (detailed in References 7.4-10 and 7.4-11 for Unit 2), including for both units:

o Improved level control and indica-tion devices for the containment sump pumps, o Upgrading of the reactor cavity pumps control and CCR cavity level indication.

o Revised technical specifications regarding limiting conditions for operation of the various leakage detection systems and operating leakage limits.

o Continuous containment sump level indication in the control room.

In addition, for Unit 2 there are new design fan cooler heat exchangers with rolled rather than brazed tubes and improved access to the tubes via water boxes, television camera mcnitoring of the containment water levels, and improved fan cooler and weir system and dew point recorder.

As a result of these and many other improvements, substantial leakage or flooding in the containment building will be detected and controlled, which l reduces the probability of damage to l safety related equipment and decreases j the frequency of occurrence of flooding i inside the containment building.

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. The impact on plant risk due to concur-rent service water system rupture and LOCA was investigated for possible increases in plant risk (due primarily to increased water in the containment sump and possible flooding of equipment a

necessary for the recirculation phase).

This event is an insignificant contrib-utor to plant risk and is not quantified for the following reasons:

1. The service water pipe rupture must either occur as a result of the LOCA I

or occur randomly after the start of the LOCA.

2. If the service water pipe were to rupture, the individual service water lines to the containment fan cooler units can be readily isolated from outside the containment build-ing (two MOVs in series in each of the inlet lines and two MOVs in series in each of the fan cooler outlet and fan cooler motor outlet service water lines for Unit 2, and similar manual valves for Unit 3).

3. Flow and temperature indication is available to allow rapid detection of a failed service water line.

The metallurgical and/or design improvements in the fan cooler units of the Indian Point plants, as discussed in the Power Authority's Testimony of John C. Brons, Kenneth R.

Chapple, and William Spataro and in Consolidated Edison's Testimony of Arthur H. Tuthill and Samuel Rothstein on Con-tention 2.2(a), are not incorporated in the IPPSS analy-d sis. These improvements would further reduce the risk asso-ciated with the potential corrosive properties of brackish water. -

NAME DENNIS C. BLEY EDUCATION Ph.D. , Nuclear Reactor Engineering, Massachusetts Institute of Tecnnolo gy , 1979.

Courses in nuclear engineering and ccmouter science, Cornell University, 1972-1974.

U.S. Navy Nuclear Power School,1968.

University of Cincinnati, B.S.E.E. ,1967.

Courses in Mathematics and Physics, Centre College of Kentucky, 1961-1953.

PROFESSIONAL EXPERIENCE General Summary A consultant at Pickard, Lowe & Garrick, Inc.,1979-present. Technical analysis of power plant availaoility and risk. Cost-benefit analysis of power plant system changes. Preparation of technical reports, expert te-timony , and proposal s. Supervision f the technical cuality of PLG reports and direction of some PLG projects. Instructor at availability, risk, and decision analysis courses offered by PLG. Oyster Creek Probabilistic Risk Assessment (OPSA). Assisted in the comaletion and review of this complete risk assessment of an operating BWR performed for Jersey Central Power & Light. Work Order Scheculing System (WOSS).

Assisted in developing the San Onofre 2 and 3 plant model for a computer based work order prioritizing, scheduling, and record keeping system for Southern California Edision Company. Steam Turbine Diagnostics Cost-Benefit Analysis. Developed and applied a procedure for evaluating diagnostic alternatives for E?RI. Reliability Analysis of Diablo Canyon Auxiliary Feedwater System for Pacific Gas & Electric. Midland Plant Auxiliary Feedsater System Reliability Analysis for Consumers Power.

Technical Review of the " Office of Emergency Services Recommended Emergency Planning Zone Considerations..." for Southern California Edison. Prioritization of NRC Action Plan for NSAC. Development of a methodology and participation in an AIF workshop to apply it for EPRI/NSAC. Zion and Indian Point Probabilistic Safety Studies. Metnods development, systems analysis, and plant modeling. Other ? ras--LaSail e, Browns Ferry, Midland, Pilgrim 1, and Oconee.

On USS Enterprise, Reactor Training Assistant, 5 months, 1971.

Responsible for technical training of approximately 400 nuclear trained officers and men prior to annual safeguards examination. Propul sion Pl ant Station Of ficer, 9 months, 1970-1971. Responsible for maintenance and operation of one propulsion plant (two reactors, eight steam generators, and associated equipment) during power range testing of new reactors and during deployment. Approximately 50 enlistec personnel were assigned to the plant. Shif t Propulsion Plant Wat:h Officer,15 months, 1969-1970. Supervised a crew of about 20 navy enlisted operators and many shipyard workers on S-hour shift rotation conducting maintenance

BLEY - 2 and testing in one propulsion plant during refueling-overnaul. Shipboard qualifications: Propulsion Duty Officer, responsible for all propuision equipment during absence of Reactor Officer and Engineer Officer.

Engineering Officer of the Watch, operational waten in Central Control, responsible for all propulsion and engineering equipment and watch standers. Propulsion Plant Waten Officer, operational watch in one propulsion plant, directed and responsible for all operations in the plant.

At Cincinnati Bell, Plant staff assistant, 4 months,1967. Worked in central office and transmission group supplying technical assistance to the line organization. Cooperative trainee, 3 years,1964-1967, work-study program with alternate three month periods at the University of Cincinnati.

Chronological Summary '

1979-P resent Consul tant, Pickard, Lowe and Garrick, Inc.

1972-1979 Massachusetts Institute of Tecnnology.

Research assistant for Department of Energy LWR Assessment Project. Teacning assistant in engineering of nuclear reactors.

Summer 1976 Northeast Utilities.

Engineer: economy studies, plant startup, analysis of physics tests.

1967-1972 U.S. Naval Reserve, active duty.

Instructor of naval science, Cornell University, 1971-1974; Reactor Department of USS Enterprise, deployment and refueling-overhaul, 1969-1971; Nuclear Power training program and Officer Candidate School, 1967-1969.

196A-1967 ' Cincinnati Bell .

P1 ant staff assistant and work-study program trainee.

MEM3ERSHIPS. LICENSES, AND HONORS

} The Society for Risk Assessment.

1 Institute of Electrical and Electronics Engineers.

American Nuclear Society.

American Association for the Advancement of Science.

The New York Academy cf Sciences.

U.S. Naval Reserve, Co=ander.

Registered Nuclear Engineer, State of California.

BLEY - 3 Sigma Xi (national science honors society),1976.

Sherman R. Knapp Fellowship (Northeast Utilities), 1975-1976.

Sl oan Research Traineeship, 1974-1975.

Eta Kappa Nu (national electrical engineering honors society),1957.

REPORTS AND PUBLICATICUS "Seabrook Probabilistic Safety Assessment," Public Service Company of New Hampshire, to be published in 1983.

Pickard, Lowe and Garrick, Inc., " Midland Probabilistic Risk Assessment,"

Consumers Power Company, to be published in 1982.

Oconee Probabilistic Risk Assessment," a joint effort of the Nuclear Safety Analysis Center, Duke Power, and other participating utilities, to be published in 1982. .

Tennessee Valley Authority and Pickard, Lowe and Garrick, Inc., " Browns Ferry Probabilistic Risk Assessment," to be published in 1982.

Apostolakis, G. , M. Kazarians, and D. C. Bley, "A Methodology for Assessing the Risk from Cable Fires," accepted for publication in Nuclear Sa fe ty , 1982.

Kaplan, S. , F. F. Perla, and D. C. Bley, "A Methodology for Seismic Safety Analysis of Nuclear Power Plants," proposed presentation at tne

' International Meeting on Thermal Nuclear Reactor Safety, Chicago, Illincis, August 29-September 2,1982.

Bl ey, D. C. , S. Kaplan, and B. J. Garrick, "Assemoling and Decomposing PRA Results: A Matrix Formalism," proposed presentation at the International Meeting on Thermal Nuclear Reactor Safety, Chicago, Illinois, August 29-September 2,1982.

Garrick, 3. J. , S. Kaplan, and D. C. Bl ey, "Recent Advances in Probabilistic Risk Assessment," prepared for the MIL Nuclear Power Reactor Safety Course, Cambridge, Massachusetts, July 19, 1982.

Fleming, K. N. , S. Kaplan, and B. J. Garrick, "Seabrook Probabilistic Safety Assessr.ent Management Plan,"PLG-0239, June 1982.

Garrick, B. J., " Lessons Learned From First Generation Nuclear Plant Probabilistic Risk Assessments," to be presented at the Workshop on Low-Probacility/High-Consequence Risk Analysis, Arlington, Virginia, June 15-17,1982.

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BLEY - 4 Garrick , B. J. , S. Kapl an, D. C. Iden, E. B. Cl evel and, H. F. Perl a, D. C. Bley, D. W. Stillwell, H. V. Schneider, and G. Apostolakis, " Power Pl ant Availability Engineering: Methods of Analysis, Program Planning, and Applications," E?RI NP-2168, PLG-0165, May 1932.

Bley, D. C., and R. J. Mulvihill, " Comments on Evaluation of Availability Improvement Options for Moss Landing Units 6 and 7," PLG-0225, Marcn 1982.

Stillwell, D. W. , G. Acostol akis, D. C. Bl ey, P. H. Raabe, R. J. Mulvihill, S. Kaolan, and B. J. Garrick, "EEI Availability Handbook," PLG-0218, January 1982.

Bl ey, D. C. , L. G. H. Sarmanian, and D. W. Stillwell, " Reliability Analysis of Safety Injection System Modification, San Onofre Nuclear Generating Station - Unit 1,".PLG-0205, October 1981.

" Zion Probabilistic Safety Study," Commonwealth Edison Company, September 1931.

Buttemer, D. R., " Analysis of Postulated Accidents During Low Power Testing at the San Onofre Nuclear Generating Station--Unit 2," PLG-0199, Septemoer 1981.

Bl ey, D. C. , D. W. Stillwell, and R. R. Fray, " Reliability Analysis of Diaolo Canyon Auxiliary Feedwater System," presented at the Tenth Biennial Topical Conference on Reactor Operating Experience, Cleveland, Ohio, August 17-19, 1931.

Garrick, B. J. , and D. C. Bley, " Lessons Learned from Current PRAs,"

presented to the ACRS Subcommittee on Reliability and Probabilistic Risk Assessment, Los Angeles, California, July 28, 1931.

Kaplan, S. , G. Apostolakis, B. J. Garrick, D. C. Bley, and X. Woodard,

" Methodology for Probabilistic Risk Assessment of Nuclear Power Plants,"

draf t version of a book in preparation, PLG-0209, June 1981.

Perl a, H. F. , "Proj ect Pl an: Probaoilistic Risk Assessnent, Midland Nuclear Power Plant," PLG-0150, May 1981.

Bl ey, D. C. , C. L. Cate, D. W. Stillwell, and B. J. Garrick, " Midland Plant Auxiliary Feecsater System Reliability Analysis Synopsis,"

. PLG-0166, March 1931.

Pickard, Lowe and Garrick, Inc., "A Methodology to Quantify Uncertainty of Cost of Electricity for Alternate Designs of (Combustion) Turoine Combined Cycle Plants," PLG-0162, Marcn 1981.

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BLEY - 5 Garrick, B.. J. , S. Ahmed, and D. C. Bley, "A Methodology for Evaluating the Costs and Benefits of Power Plant Diagnostic Tecnniques," suomitted for presentation at the Ninth Turbemachinery Symposium, Houston, Texas, Decemoer 9-11, 1930.

Pickard, Lowe and Garrick, Inc. , " Seminar: Procabilistic Risk Assessment of Nuclear Power Plants," PLG-0154, Novemoer 1980.

Pickard, Lowe and Garrick, Inc. , " Project Plan: Probabilistic Risk Assessment, 3rowns Ferry Nuclear Plant Unit 1," PLG-0149, October 1930.

Garrick, B. J. , S. Kapl an, D. C. Iden, E. B. Cl eveland, H. F. Perla, t D. C. Bley, and D. W. Stillwell, "Pcwer ?lant Availability Engineering, Methods of Analysis - Program Planning - Applications," 2 Vols.,

PLG-0148. October 1980.

Bl ey, D. C. , C. L. Cate, D. W. Stillwell, and B. J. Garrick, " Midland Plant Auxiliary Feedsater System Reliability Analysis," PLG-0147, Octooer 1980.

Bl ey, D. C. , D. M. Wheeler, C. L. Cate, D. W. Stillwell, and B. J. Garrick, " Reliability Analysis of Diablo Canyon Auxiliary Feedwater System," PLG-0140, September 1980.

Garrick, B. J. , et al, " Project Plan: Oconee Probabilistic Risk As sessment," PLG-0138, August 1980. '

Garrick , B . J. , D. M. Wheel er, E. B. Cl evel and, D. C. Bl ey ,

L. H. Reichers, and C. B. Morrison, " Operating Experience of Large U.S. Steam Turbine-Generators; Volume 1 - Data, Volume 2 - Utility Directory," PLG-0134, June 1980.

Garrick, B. J. , S. Kaplan, and D. C. Bl ey, " Seminar: Power Plant Probabilistic Risk Assessment and Reliability," PLG-0127, May 1980.

i Garrick, B. J. , and S. Kaplan, "0yster Creek Probabilistic Safety Anal-

ysis (OPSA)," presented at the ANS-ENS Topical Meeting on Thermal Reactor Safety, Knoxville, Tennessee, April 8-11, 1980.

j Garrick, B. J. , S. Xapian, G. E. Apostolakis, D. C. Bley, and l T. E. Potter, " Seminar: Probabilistic Risk Assessment as Applied to Nuclear Power Plants," PLG-0124, March 1980.

Garrick, B. J. , S. Ahmed, and D. C. Bley, "A Methodology for Evaluating the Costs and Benefits of Pcwer Plant Diagnostic Techniques," PLG-0115, January 1980.

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1 Kaplan, S., 3. J. Garrick, and D. C. Bl ey, " Notes on Risk, Probacility, and Decision," PLG-0113, November 1979.

Bl ey, D. C. , C. L. Cate, D. C. Iden, 3. J. Garrick , and J. M. Hudson,

" Seismic Safety Margins Research Program (Phase I), Project VII - Systems j Analysis," PLG-0110, Septemoer 1979.

Cate, C. L. , and B. J. Garrick, "W-501 Comoustion Turbine Starting Reliability Analysis," PLG-0103, June 1979.

Pickard, Lowe and Garrick, Inc., " Plant Availability 'rogram Specifica-

tion, San Onofre Nuclear Generating Station," Maren 1979.

4 Pickard, Lowe and Garrick, Inc., " Work Order Scheduling System, Design Specification," March 1979.

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