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UNITED STATES OF AMERICAj NUCLEAR REGULATORY COMMISSION1

| ATOMIC SAFETY AND LICENSING BOARD ''

Defore Administrative Judges:James P. Gleason, Chairman

Frederick J. ShonDr. Oscar H. Paris

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i)

In the Matter of )l )

CONSOLIDATED EDISON COMPAtlY OF ) Docket Nos.NEW YORK, I!!C. ) 50-247 SP(Indian Point, Unit No. 2) ) 50-286 SP

! )POWER AUT!!ORITY OF THE STATE OF ) Jan. 12, 1983

NEW YORK )(Indian Point, Unit No. 3) )

{ LICENSEES' TESTIMONY OFDENNIS C. BLEY AND DENNIS C. RICHARDSOli

ON COMMISSION OUESTION 2 AND BOARD OUESTION 2.2.1-

ATTORNEYS FILING THIS DOCUMENT:

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Brent L. Brandenburg Paul F. ColarulliCONSOLIDATED EDISON COMPANY Joseph J. Levin, Jr.OF NEW YORK, INC. MORGAN ASSOCIATES, CHARTERED

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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8301170221 830112PDR ADOCK 05000247

! T PDR

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I. TESTIMONY ON COMMISSION OUESTION 2 --DIRECTOR'S CONFIRMATORY ORDER

A. INTRODUCTION

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

a principal investigator on the Indian Point Probabilistic

Safety Study. A statement of my profesional qualifications

is attached.

My name is Dennis C. Richardson. I am the Risk Assess-

ment Technology Manager in the Nuclear Safety Departmen,t of

the Nuclear Technology Division of Westinghouse Electric

Corporation. I was a principal investigator on the Indian

Point Probabilistic Safety Study. A statement of my pro-

fessional qualifications is attached.

This section of the testimony addresses the following

portion of Question 2 of the Commission's Memorandum and

Order.

'Uhat improvements in the level of safety

j will result from measures required or! referenced in the Director's Order to

the licensee, dated February 11, 1980?Ill

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1. The parenthetical portion of Commission Question 2is omitted herein. The contentions undet that portion of

j Commission Question 2 are addressed in other testimony.

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B. IMPACT OF DIRECTOR'S CONFIRMATORY ORDER ONTHE SAFETY OF INDIAN POINT

At the time of the Director's Confirmatory Order,

February 11, 1980, no plant-specific probabilistic risk

assessment (PRA) of the Indian Point nuclear power plants

existed. Lacking a plant-specific PRA, a broad approach

addressing potential risk contributors was ordered by the

Commission. That order concentrated on important contrib-

utors to risk identified in previous generic. risk studies,

as well as contributing causes in reactor plant accidents

such as the one at Three Mile Island. Additionally, these

previous risk studies did not concentrate on external

initiating events. Therefore, the measures contained in the

Order primarily focused on reducing the risk from internal

initiating events.

Now that the plant and site-specific PRA, the Indian

Point Probabil.istic Safety Study (IPPSS), is completed and

the dominant contributors to risk from Indian Point have

been identified, the items ordered by the Director have been

assessed to determine their impact. For the dominant

scenarios in earlier generic studies, the items in thet

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Director's Order dealing with improved training and onsite

technical capability are important. The new diesel gener-

ator testing requirements will enhance reliability should

failures begin to be observed. Such failures have not yet,

occurred at Indian Point. The use of the gas turbines <

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provide reduction factors of 40 and 7 in the frequency of

late overpressurization containment failures from internally

I initiated events for Unit 2 and Unit 3, respectively.

Improvements in gas turbine reliability would reduce the

already low latent health effects contribution attributable,

to loss of AC power (1.0 x 10-6 per reactor year at Indian

Point 2 and 4.8 x 10-7 per reactor year at Indian Point

3). Prior to the Director's Order, reliability data for the

! gas turbines were not recorded; thus, reductions in risk

have not been quantified. The improvements in auxiliary

feedwater system reliability are substantial but do not

significantly affect the risk because the IPPSS found that

rare " external events" dominate the risk at both units.

Because external events were not specifically addressedi

in the Director's Order, the overall quantitative impact of

the Order on plant risk is modest but positive. These con-

clusions are consistent with results of a previous Commis-

| sion evaluation (Task Force Report on Interim Operation of

Indian Point, NUREG-0715, Aug. 1980).

C. MODIFICATIONS IN EOUIPMENT AND PROCEDURES

The Indian Point plants are under continuous review by

both the utilities and the Commission to determine if mod-ifications to equipment or procedures would result in signi-ficant safety enhancement. When warranted, such changes

have been implemented.-

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During the course of performing the IPPSS, certain

,areas were identified for improvement. Both Con Edison and

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the Power Authority have undertaken to implement these plant

improvements and have accordingly f actored them into the

IPPSS plant model. These improvements were identified with'

the submittal of the IPPSS.

The following improvements were made at Indian Point 2

and 3:,

(1) Implementation of a refueling interval surv,eil-'

lance test to verify disc integrity for RHR valvesMOV-730 and MOV-731.

(2) Implementation of a refueling interval surveil-lance test to verify disc to stem integrity forspray valve 869A (such verification is alreadyaccomplished for redundant valve 869B in thecourse of performing normal refueling operations).

(3) Implementation of changes to refueling intervalsurveillance test to clarify test method and datarecording for accumulator discharge valve flow

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verification check. '

(4) Implementation of procedures to periodicallyverify that: (a) the service water pumpsdesignated for essential header service are infact aligned to the required essential services(i.e., field valve alignment check), a r.d (b) theposition of the control room service water systemmode selector switch is such that the correct setof service water pumps is selected for automaticessential header service.

(5) System modification, procedural change or verifi-* cation testing to ensure that sufficient backpres-;

sure will be maintained in the service water'

system to prevent service water pump overload forcases in which only one service water pump isoperating with the system in accidentconfiguration.

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The following improvements were made at Indian Point 2

only:

(1) Rearrangement of diesel generator fuel oil trans-fer pump power supplies such that the primarytransfer pump for each diesel is powered from oneof that diesel's electrical buses.

(2) Replacement of manual isolation valves with motoroperated isolation valves in certain of the fancooler service water discharge lines.

(3) Seismic cushioning of the control building roof.

(4) Enhancement of installed alternate shutdownsystem.

Examples of Commission-initiated safety improvements

which are modeled in the IPPSS and are being implemented at

the plants include:

(1) Implementation of masonry wall upgrading modifica-tions for station batteries in response to IEBulletin 80-11.

(2) Additional fire protection as specified inAppendix R to 10 C.F.R. Part 50.

(3) Items covered in the Director's Order.

(4) Various post-Tf1I requirements.1

D. CONCLUSIONS

Based upon the safety features in the basic Indian

Point designs, the safety improvements ordered by the

Director and other Commission-initiated improvements, and

the equipment and procedure improvements made by the

utilities as a result of the IPPSS analysis, the risk from

the Indian Point plants is extremely low,

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II. TESTIMONY ON BOARD OUESTION 2.2.1

The implementation of the July 29, 1982 draft of the

proposed generic Steam Generator Owner's Group requirements

at the Indian Point units would not perceptibly change the

risk posed by the units as set forth in Figures 8.1-3 and

8.1-6 of the IPPSS, nor change in any way the conclusion of

IPPSS that steam generator tube rupture events are not

dominant risk contributors at these units.

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N A'E

DENNIS 0. ELEY

EDUCATION

Pn.0. , Nuclear Reactor Engineering, Massacnusetts Institute ofTecnnci o gy , 1979.C0urses in nuclear engineering and ccmouter science, Cornell Universi y,1972-1974U.S. Navy Nuclear Pcwer School,1968.4

Universi y of Cincinnati, 3.5.E.E. ,1967.Courses in Ma:nematics and Physics, Centre C0llege of Kentucky, 1961-1963.

PRCFESSIONAL EXPERIENCE

General Summary

A consultant at ?ickard, Lowe & Garrick, Inc.,1979-present. Technicalanalysis of power plant availaoility and risk. Cost-benefit analysis ofposer plant system changes. Preparation of technical recor:s, excer:testimony, and proposals. Supervision Of the tecnnical quality of PLGreports and direction of some ?LG projects. Instruct:r at avaiiacility,ri sK , and decision analysis courses offered by PLG, Oyster CreekProbabilistic Risk Assessment (OPSA). Assisted in the comoletion andreview of this complete risk assessment of an operating SWR cerformed for|

! Jersey Central Pcwer & Lign:. Work Order Scheculing System (WOSI).Assisted in cavelocing the San Onofre 2 and 3 plant mocel for a ccm:u ercased work order orioriti:ing, scheduling, and record keeping system forSoutnern California Edision Ccmpany. Steam Tur:ine DiagnosticsCost-Benefi: Analysis. Developed and applied a procedure for evaluatingdiagnostic alternatives for E?RI. Reliability Analysis Of Diaolo CanyonAuxiliary Feedwater System for Pacific Gas & Electric. Midland PlanAuxiliary Feedwater System Rel f acility Analysis for Consumers Pcwer.Tecnnical Review of the "Offi.ce of Emergency Services RecommendedEmergency ?lanning Zone Considerations..." for Soutnern CaliforniaEdison. Prioriti:ation of NRC Acticn Plan for NSAC. Development of ametnodology and participation in an AIF workshop to apply it forEPRI/NSAC. Zion and Indian Point Probabilistic Safety Stucies. Me:ncdsdevelo; ment, systems analysis, and plant modeling. 0:ner ? ras--LaSall e,3rcwns Ferry, Midland, Pilgrim 1, and Ocenee.

On USS Enterprise, Reactor Training Assistant, E months, 1971.Res onsible for tecnnical training of approximately 400 nuclear trainedofficers and men prior to annual safeguards examination. PropulsionPl an Station Officer, 9 months, 1970-1971. Responsible for maintenanceand operation of one propulsion plan: (:wo reactors, eight steamgenerators, and associated ecuipment) during pcwer range testing of newreactors and curing deployment. Approximately 50 enlisted personnel wereassigned to the olant. Shift ?reculsion Plant Wat:h Officer,15 months,1969-1970. Supervised a crew of acou: 20 navy enlisted operat:rs ancmany shioyard workers en 5-hcur shift rotation conducting maintenance

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and testing in one procuision plant during refueling-overnaul. Shioboarccualifications: Propulsion Cuty Officer, responsiole for all cropulsionecutoment during absence of Reactor Officer and Engineer Officer.Engineering Officer of ne Wat:n, coerational aat:n in Centrai Control,resconsible for all procuision and engineering scuipment and wa :nstancers. Propuision Plan- Wat:n Officer, operational wa :h in onecrocuision plant, directed and responsible for all operations in neplant.

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A: Cincinnati 3 ell, Plant staff assistant, 4 mon hs,1967. Worked incentral office and transmission grous sucolying technical assistance ::,

the line organization. Cooperative trainee, 3 years,1964-1967,work-study program with alternate three montn periods at the University

, of Cincinnati.!

Chronological Summary '

1979-? resent Consultant, Pickard, Lowe and Garrick, Inc.

1374-1979 Massacnusetts *nstitute of Tecnnology.Research assistant for Department of Energy LWRAssessment Project. Teacning assistant in engineering ofnuclear reactors.

Summer 1976 Nortneast Utilities.Engineer: economy studies, plant startup, analysis of

i physics tests.

1967-1974 U.S. Naval Reserve, active duty.Instructor of naval science, Cornell University,1971-1974;Reactor Department of USS Enterprise, deployment andrefueling-overhaul, 1969-1971;

. Nuclear ?cwer training program and Officer Candidate| School, 1967-1969.,

1964-1967 Cincinnati Bell.'

Plant staff assistant and work-study program trainee.

MEMBERSHIPS, LICENSES. AND HONORS

The Society for Risk Assessment.Institute of Electr: cal and Electronics Engineers.American Nuclear Society.Anerican Association for the Advancement of Science.The New Yor< Acacemy of Sciences.U.S. Naval Reserve, Commander.Registered Nuclear Engineer, State cf California.

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Sigma Xi (national science henors society),1975.Sherman R. Knaco Fellcwsnip (Northeast Utilities), 1975-1975.Sl oan Research Traineesnip, 197'-1975.E a Kappa Nu (national electrical engineering hences society),1957.

REPORTS AND PUBLICATIONS

"Seabrock Procabilistic Safety Assessment," Puolic Service Company ofNew Hampshire, to ce puolished in 1933.

Pickard, Lowe and Garrick, Inc., "Midlano Pr00acilistic Risk Assessment,"Consumers Power Company, to be puolished in 1982.

Cconee Probabilistic Risk Assessment," a joint effort of the NuclearSafety Analysis Center, Duke Pcwer, and otner participating utilities, tobe published in 1932.

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Tennessee Valley Authority and Pickard, Lewe and Garrick, Inc., "Br wnsFerry ?rcoacilistic Risk Assessment," :: be puolished in 1932.

Acestelakis, G. , M. Ka:arians, anc D. C. Bley, "A Methodology forAssessing the Risk from Caole Fires," accepted for puolication in NuclearSa fe ty, 1932.

Kaplan, S. , H. F. Perl a, and D. C. Sley, "A Methodclogy for SeismicSafety Analysis of Nuclear Power Plants," procosed presentation at tneInternational Meeting on Thermal Nuclear Reactor Safety,Chicago, Illinois, August 29-September 2,1932.

Sl ey, D. C. , S. Kaolan, and B. J. Garrick, " Assembling and DeccaposingFRA Results: A Matrix FormaTism," proposec presentation at theInternational Meeting on Thermal Nuclear Reactor Safety,Chicago, Illinois, August 29-Septemoer 2,1952.

Garr1c<, 3. J. , S. Kapl an, and D. C. 31 ey, "Recent Advances inProbabilistic Risk Assessment," prepared for the MIL Nuclear PcwerReactor Safety Course, Camoridge, Massacnusetts, July 19, 1982.

Fleming, K. N. , S. Kaplan, and 5. J. Garrick, "Seabrock PrecabilisticSafety Assessnent Management Plan,"PLG-0239, June 1982.

Garrick, S. J. , " Lessons Learned From First Generation Nuclear Plan:Probabilistic Risk Assessments," to be presented at the '4crkshco enL w-Procacility/High-Consequence Risk Analysis, Arlington, Virginia,June 15-17,1952.

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3arrick , 3. J. , S. Xaol an, D. C. Iden, E. 3. Cl evel and, H. F. Perl a,D. C. Bley, D. W. Stillwell, H. V. Scnneicer, and G. Acostolakis, "P0werPl ant Avail ability Engineering: Methods of Analysis Program Planning,and Applications," EPRI NP-2153, PLG-0165, May 1932.

Sl ey, D. C. , anc R. J. Mulvihill, "Ccmments en Evaluation of AvailacilityImorovemen: Options for Moss Landing Units 5 and 7," PLG-0225,

! Maren 1932.

Stillwell, D. W. , G. Acos:clakis, D. C. Bl ey, P. H. Raabe,R. J. Mulvinill, S. Kaolan, and 3. J. Garricx, "EEI Avail ability

: HancbocK," ?LG-0213, January 1932.;

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Bley, D. C. , L. G. H. Sarmanian, and D. W. Stiliwell, "ReliacilityAnalysis of Safety Injecticn System Modification, San Onofre NuclearGenerating Station - Unit 1," PLG-0205, October 1931.

" Zion Pr:bacilistic Safety Study," Commonwealth Edison C:mpany,), Septemoer 1931.

Su;temer, D. R., "Anclysis of Postulated Accicents During Lcw PowerTesting at :ne San Cncfre Nuclear Generating Station--Unit 2," PLG-0199,Seo:emoer 1981.

Sl ey, D. C. , D. W. Stillwell, and R. R. Fray, "Reliacility Analysis ofDiablo Canycn Auxiliary Feecwater System," presented at the Tentn

! Biennial Tooical Conference en Reactor Operating Experience, Cleveland,Ohi o, August 17-19, 1931.

Garrick, 3. J. , and D. C. Sl ey, " Lessons Learned from Current PRAs,"presented :: :ne ACRS Subc:=mittee on Reliacility and Probabilistic Risk

: As sessnent, Los Angeles, California, July 23, 1981.

Kapl an, S. , G. Apost:lakis, 3. J. Garrick, D. C. Bley, and K. Woodard,"Metnodology for Procacilistic Risk Assessment of Nuclear ?:wer Plants,"draf t version cf a book in precaration, ?LG-0209, June 1931.

Pe rl a, H. .~. , "Proj ect Pl an: Precasilistic Risk Assessment, MidlandNuclear Pcwer Plant," PLG-0150, May 1981.

31 ey, D. C. , C. L. Cate, D. W. Stillwell, and B. J. Garrick, "Midl andPlant Auxiliary Feecsater System Reliability Analysis Synopsis,"?LG-0155, March 1931.

Pickard, Lowe and Garrick, Inc., "A Me nodology :: Cuantify Uncertaintycf Cos: cf Electricity for A1: err. ate Designs of (00m:us ion) TuroineComsined Cycle Pl ants," PLG-0152, Maren 1931.

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Garrick, 3.. J. , S. Ahmed, and D. C. Bley, "A Methodology for Evaluatingthe Costs and Senefits of Power Plant Diagnostic Tecnnicues," suomitted4

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for presentation a: the Nin:n Turocmacninery Symposium, Houston, Texas,Decemoer 9-11, 1980.

: Pickard, Lowe anc Garrick, Inc. , " Seminar: Probacilistic Risk Assessmen:| of Nuclear Power Plants," PLG-0134, Novemoer 1980. ,

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| Pickard, Lowe and Garrick, Inc. , " Project Pl an: Procacilistic Risk; Assessment, Browns Ferry Nuclear Plant Uni: 1," PLG-0149, October 1930.1 Garrick, 3. J. , S. Kapl an, D. C. Iden, E. 3. Cl evelanc, H. F. Perl a,

D. C. Bley, and D. W. Stillwell, "Pcwer Plant Availability Engineering,Methods of Analysis - Program Planning - Applications," 2 Vols.,,

i PLG-0148. October 1980.

Bl ey, D. C. , C. L. Cate, D. W. Stillwell, and 3. J. Garrick, "Midl andPlant Auxiliary Feecsater System Reliability Analysis," PLG-Ola7,Octocer 1980.

; Sl ey, D. C. , D. M. Wheeler, C. L. Cate, D. W. Stillwell . and| 3. J. Garrick, " Reliability Analysis of Diaolo Canyon Auxiliary Feecwa ar! Sy stem," PLG-0140, September 1930.

Garrick , 3. J. , et al, " Project Plan: Oconee Probacilistic Risk4

i As sessnent," PLG-0138, August 1980.?

! Garrick, 3. J. , D. M. Wheel er, E. 3. Clevel and, D. C. Bl ey,i L. H. Reichers, and C. 3. Morrison, "Goerating Experience of Large

U.S. 5:aam Turoine-Generators; Volume 1 - Data, Volume 2 - Utilityi

Di rectory," PLG-0134, June 1980.1

Garrick , 3. J. , S. Xaplan, and D. C. Bl ey, " Seminar: Pcwer Pl an:Procabilistic Risk Assessment and Reliability," PLG-0127, May 1980.

Garrick, 3. J. , and S. Kaplan, "0yster Creek Probacilistic Safety Anal-i

ysis (OPSA)," presented at the ANS-ENS Topical Meeting on Thermal ReactorSafety, Knoxville, Tennessee, April 3-11, 1980.

Garrick, 3. J. , S. Xaplan, G. E. Apostolakis, D. C. 31ey, and,

! T. E. Potter, " Seminar: Probacilistic Risk Assessment as Applied to |

Nuclear Power Plants," PLG-0124, March 1980.|

Garrick, 3. J. , S. Ahmed, and D. C. Bley, "A Metnodology for Evaluating[

! tne Costs and Benefits of Pcwer Plan: Diagnostic Tecnnicues," PL3-01'S,'

January 1930..

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Kacl an, S. , 3. J. Garrick, and D. C. El ey, "No tes on Ri sk, ?rcoacili ty,i

and Decision," ?L3-0113, Novemcer 1979.;

; Bl ey, D. C. , C. L. Cate, D. C. Iden, 3. J. Garrick, anc J. M. Mucson,i

" Seismic Safety Margins Research Program (?hase !), Prcject VII - SystemsAnaly si s," PLG-0110, Se:::emoer 1979.

.) Ca a, C. L. , and 5. J. Garrick, "W-501 Comoustion Turcine Star-ingP.el f acility Analysis," PLG-01C3, June 1979.

Pickard, Lcwe and Garrick, Inc., " Plan: Availacility Program Scecifica-,

j tien, San Oncfre Nuclear Generating Station," Marcn 1979.I

Pickard, Lcwe and Garrick, Inc. , " Work Order Scheduling System, Designj Speci fication," March 1979.i .

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Dennis C. Richardson - Risk Assassrent Technology Manager

Penn State Universi y, B.S. Aerorpace Engineerir.;

19c3

M.S. Controi Engineering

1965 ,

San Giego State University, M.S. Mathmatics

1970

Unf verstty of P1ttsburgh, MBA

1980

Mr. Richardson has many years of professional and canagement experiercein the nuclear field. He joirad the Pressurized Water F4 actor Divisionof Westinghouse in 1972 where he manaced the Reactor Protection AnalysisGroup for perfoming nuclear plant safety analysis and, most recencly,has canaged the Risk Assess = enc Technology Organization.

Prior to this, Mr. Richardson was wi ,h Gulf General Atomic where neworked on design of contrei and safety systecs for the gas-coolednuclear plant. At Westinghouse, he has parcicipated in and directed amober of risk assessment and safety analysis studies for a wide varietyof applications. He was a. principal investigator in both the Zion Sta-tion and Indian Point Station Resctor Safety Studies. He directed tnePRA studies for the Westin;nouse Owrers Group that addressed the'

Post-TM1 NUREG requirecents on ecergency procecures and operator displayrequi recents. Mr. Ricnardson was tecnnical and program manager for theBritisn (NHC) Reference Water Reactor Safety Stuoy. He has aise led thedevelopment of econocic and financial rf sk assess =ent techniques for theuse in new reacter model design concepts.

Mr. Richardson is a mecber of the IEEE and ANS and has se-ved on theWrking groups for two standards corrittees. He is reviewing the sec-tions for the PRA canual directed by MRC to be finished in 1981. He isauthor or co-author of more than 15 reports and papers dealing with riskassessment and varicus aspects of nuclear plant designl

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UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSION

ATOMIC SAFETY AND LICENSING BOARD

Before Administrative Judges:James P. Gleason, Chairman

Frederick J. ShonDr. Oscar H. Paris

)In the Matter of )

)CONSOLIDATED EDISON COMPANY OF ) Docket Nos.

NEW YORK, INC. ) 50-247 SP(Indian Point, Unit No. 2) ) 50-286 SP

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

NEW YORK )(Indian Point, Unit No. 3) )

)

CERTIFICATE OF SERVICE|

I hereby certify that on the 12th day of January,1983,

I caused a copy of (1) Licensees' Testimony of Dennis C.

Bley on Contention 2.2(a) and (2) Licensees' Testimony of

Dennis C. Bley and Dennis C. Richardson on Commission Ques-

tion Two and Board Question 2.2.1 to be served first class

mail, postage prepaid, on the following:

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James P. Gleason, Chairman Charles M. Pratt, Esq.Administrative Judge Stephen L. Baum, Esq.Atomic Safety and Licensing Board Power Authority of the513 Gilmoure Drive State of New YorkSilver Spring, Maryland 20901 10 Columbus Circle

New York, New York 10019Mr. Frederick J. ShonAdministrative Judge Janice Moore, Esq.Atomic Safety and Licensing Board Counsel for NRC Staf fU.S. Nuclear Regulatory Of fice of the Executive

Commission Legal DirectorWashington, D.C. 20555 U.S. Nuclear Regulatory Commission

Washington, D.C. 20555Mr. Oscar H. ParisAdministrative Judge Brent L. Brandenburg, Esq.Atomic Safety and Licensing Board Assistant General CounselU.S. Nuclear Regulatory Consolidated Edison Company

Commission of New York, Inc.Washington, D.C. 20555 4 Irving Place

New York, New York 10003Docketing and Service BranchOffice of the Secretary Ellyn R. Weiss, Esq.U.S. Nuclear Regulatory Commission William S. Jordan, III, Esq.Washington, D.C. 20555 Harmon and Weiss

1725 I Street, N.W., Suite 506Joan Holt, Project Director Washington, D.C. 20006Indian Point ProjectNew York Public Interest Research Charles A. Scheiner, Co-Chairperson

Group Westchester People's Action9 Murray Street Coalition, Inc.New York, New York 10007 P.O. Box 488

White Plains, New York 10602Jeffrey M. Blum, Esq.New York University Law School Alan Latman, Esq.423 Vanderbilt Hall 44 Sunset Drive40 Washington Square South Croton-On-Hudson, New York 10520New York, New York 10012

Ezra I. Bialik, Esq.Charles J. Maikish, Esq. Steve Leipzig, Esq.Litigation Division Environmental Protection BureauThe Port Authority of New York New York State Attorney

and New Jersey General's Of ficeOne World Trade Center Two World Trade CenterNew York, New York 10048 New York, New York 10047

Alfred B. Del Bello| Westchester County Executive

Westchester County148 Martine AvenueWhite Plains, New York 10601

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Andrew S. Roffe, Esq.New York State AssemblyAlbany, New York 12248

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Marc L. Parris, Esq. Atomic Safety and LicensingEric Thorsen, Esq. Board PanelCounty Attorney U.S. Nuclear Regulatory CommissionCounty of Rockland Washington, D.C. 2055511 New Hempstead RoadNew City, New York 10956 Atomic Safety and Licensing

Appeal Board PanelPhyllis Rodriguez, Spokesperson U.S. Nuclear Regulatory CommissionParents Concerned About Indian Washington, D.C. 20555

PointP.O. Box 125 Honorable Richard L. BrodskyCroton-on-Hudson, New York 10520 Member of the County Legislature

Westchester CountyRenee Schwartz, Esq. County Of fice BuildingPaul Chessin, Esq. White Plains, New York 10601Laurens R. Schwartz, Esq.Margaret Oppel, Esq. Zipporah S. FleisherBotein, Hays, Sklar and Hertzberg West Branch Conservation200 Park Avenue AssociationNew York, New York 10166 443 Buena Vista Road

New City, New York 10956Honorable Ruth W. MessingerMember of the Council of the Mayor George V. Begany

City of New York Village of BuchananDistrict #4 236 Tate AvenueCity Hall Buchanan, New York 10511New York, New York 10007

Judith Kessler, CoordinatorGreater New Ycrk Council Rockland Citizens for Safe Energy

on Energy 300 New Hemstead Roadc/o Dean R. Corren, Director New City, New York 10956New York University26 Stuyvesant Street David H. Pikus, Esq.New York, New York 10003 Richard F. Czaja, Esq.

Shea & GouldJoan Miles 330 Madison AvenueIndian Point Coordinator New York, New York 10017New York City Audubon Society71 West 23rd Street, Suite 1828 Amanda Potterfield, Esq.New York, New York 10010 Johnson & George

528 Iowa AvenueRichard M. Hartzman, Esq. Iowa City, Iowa 52240Lorna SalzmanMid-Atlantic Representati're Ruthanne G. Miller, Esq.Friends of the Earth, Inc. Atomic Safety and208 West 13th Street Licensing Board PanelNew York, New York 10011 U.S. Nuclear Regulatory

CommissionStanley B. Klimberg, Esq. Washington, D.C. 20555General CounselNew York State Energy Office2 Rockefeller State Plaza

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Albany, New York 12223

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I Mr. Donald DavidoffDirector, Radiological EmergencyPreparedness Group'

Empire State PlazaTower Building, Rm. 1750Albany, New York 12237

Craig Kaplan, Esq.National Emergency Civil

Liberties Committee175 Fifth Avenue, Suite 712New York, New York 10010

Michael D. Diederich, Jr., Esq.'

; Fitgerald, Lynch & Diederich24 Central DriveStony Point, New York 10980

Steven C. Sholly;

j Union of Concerned Scientists' 1346 Connecticut Avenue, N.W.

Suite 1101Wa shing ton , D.C. 20036

Spence W. Perry.

Office of General Counselj Federal Emergency Management Agency

500 C Street, S.W.Washington, D.C. 20472

Stewart M. GlassRegional Counsel.

Room 1349'

Pederal Emergency Management Agency26 Federal PlazaNew York, New York 10278

Melvin Goldbergi

Staff AttorneyNew York Public Interest

Research Groupj 9 Murray Street' New York, New York 10007

Jonathan L. Levine, Esq.P. O. Box 280New City, New York 10958

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Paul F. ColaYDlli

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