ML20028D171

Testimony of Jc Brons & W Josiger Re Board Question 2.2.1 on Recommendations of NRC 820729 Meeting.Certificate of Svc Encl

ML20028D171
Person / Time
Site:	Indian Point
Issue date:	01/12/1983
From:	Brons J, Josiger W POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20028D169	List: ML20028D168 ML20028D171
References
ISSUANCES-SP, NUDOCS 8301170198
Download: ML20028D171 (29)

Text

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! DOCKET,ED j

! u9su l 33 Mt 14 N1i UNITED STATES OF AMERICA l NUCLEAR REGULATORY COMMISSION

-l ATOMIC SAFETY AND LICENSING BOARD

! Before Administrative Judges:  !

j '

James P. Gleason, Chairman 3

Frederick J. Shon

! Dr. Oscar H. Paris t

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In the Matter of )

! )

CONSOLIDATED EDISON COMPANY OF ) Docket Nos.

I 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 ) <

j (Indian Point, Unit No. 3) )

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i POWER AUTHORITY'S TESTIMONY OF JOHN C. BRONS AND WILLIAM JOSIGER ON BOARD OUESTION 2.2.1 ATTORNEY FILING THIS DOCUf1ENT:

l Charles Morgan, Jr.

MORGAN ASSOCIATES, CHARTERED i 1899 L Street, N.W.

l Washington, D.C. 20036 ,

(202) 466-7000 i

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j B301170198 830112 PDR T

ADOCK 05000247 PDR I

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TABLE OF CONTENTS I. Introduction........................................ 1 II. Proposed Program.................................... 3 A. S team Genera tor In teg ri ty. . . . . . . . . . . . . . . . . . . . . . . 3 B. Plant Systems Response.......................... 4 C. Radiological Consequences....................... 4 III. Status of IP-3 Concerning the NRC's Proposed Program.................................... 4 A. Steam Generator Integrity....................... 4 B. Plant Systems Response......................... 13 C. Radiological Consequences...................... 15 l

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I. INTRODUCTION My name is John C. Brons, Resident Manager of the Indian Point Unit No. 3 Nuclear Power Plant owned and operated by the Power Authority of the State of New York. Prior to joining the Power Authority in 1980, I ,

had 21 years of experience in the United States Navy.

My duty assignments included Commanding Officer of a nuclear submarine, Deputy Submarine Squadron Commander, and senior member of the Nuclear Propulsion Examining Board. In this third assignment, my last in the Navy, my duties included conducting intensive inspection of Atlantic Fleet nuclear-powered ships and setting standards of continued safe reactor operation.

As an employee of the Power Authority, I am senior Power Authority Manager at the,, Indian Point Unit No. 3 site, and have overall responsibility for the safe, efficient, and dependable operation of the unit. A j statement of my professional qualifications is l attached.

My name is Uilliam Josiger, Superintendent of Power of the Indian Point Unit No. 3 Nuclear Power i Plant owned and operated by the Power Authority of the State of New York. I have been working at Indian Point Unit No. 3 for 10 years in progressively more responsi-ble capacities.

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l As the Superintendent of Power at the site, I am responsible for the functional operation of the Indian Point Unit No. 3 Nuclear Power Plant. A statement of my professional qualifications is attached.

The purpose of this joint testimony is to address Board Question 2.2.1 which reads as follows:

Should any of the requirements proposed at the July 29, 1982, meeting of the NRC Staff and members of the SGOG be required for Indian Point Units 2 and/or 3, considering the risk of a steam gen-erator tube rupture in this high population area?

On July 29, 1982, the NRC staff met with the Steam Generator Owners Group (SGOG) to discuss proposed steam generator generic requirements. The NRC's proposed program is based on the Staff's perception of the need l to consider issues related to the resolution of the Unresolved Safety Issues A-3, A-4, and A-5 regarding steam generator tube integrity as well as their con-cerns about steam generator tube rupture and operating experience. Their concerns about steam generator tube rupture are discussed in NUREG-0651, and their concerns about operating experience, which include various tube degradation mechanisms, are discussed in NUREG-0886. A steam generator tube rupture at Indian Point Unit No. 3 (IP-3) is not a dominant risk to the population in the area. Testimony to be presented under Question 1 will attest to this. Notwithstanding this fact nor the fact

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l that the NRC Staff's own contractor, Science Applica-tion, Inc. , has determined that "[p]ublic risk from steam generator tube rupture was assessed and found to be so low that it has a completely negligible con-i tribution to the value-impact comparison," J.H.

Morehouse, R.T. Liner, Value-Impact Analysis of Recom-mendations Concerning Steam Generator Tube Degradations and Rupture Events S 3.0, at ES-2 (Sept. 23, 1982), the following testimony compares those activities routinely performed at IP-3 with the NRC's proposed requirements.

II. PROPOSED PROGRAM The NRC program consists of the following:

A. Steam Generator Integrity

1. Prevention and detection of loose parts 1

and foreign objects.

2. Stabilization and monitoring of degraded i

tubes.

3. Tube inservice inspection program (ISI).

4. Improved eddy current inspection techniques (ECT).

5. Primary to secondary leakage limit.

6. Secondary water chemistry program.

7. Condenser inservice inspection prcgram.

8. Upper inspection ports.

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B. Plant Systems Response

1. Reactor Coolant System (RCS) pressure control during a SGTR.

2. Safety Injection (SI) signal reset.

3. Containment Isolation (CI) and reset.

C. Radiological Consequences Standard Technical Specification limit for Coolant Iodine activity.

The Power Authority has always given attention to steam generator inspection techniques, water chemistry requirements, and operating modes, both normal and emergency, at Indian Point Unit No. 3, and the rela-tionship of these factors to the integrity of the steam 1

generators. The Power Authority currently has programs which have been in effect for some time which address many of the generic requirements proposed by the NRC.

In the instances in which no program currently exists, the Power Authority is evaluating the proposed require-l ments prior to making a decision on whether implement-ing a new or revised program is necessary.

III. STATUS OF IP-3 CONCERNING THE NRC'S PROPOSED PROGRAM A. Steam Generator Integrity

1. Preventicn and Detection of Loose Parts and Foreign Objects Quality Assurance (QA) and Quality control (OC) procedures for the steam generator primary and secondary side are always in effect while any

maintenance, repairs and/or inspection operations are performed. These procedures include accounting for all tools and equipment, and for all components and parts removed from the internals of major com-ponents; appropriate controls on foreign objects; and cleanliness.

The Power Authority has scheduled a complete inspection of the IP-3 steam generators prior to their return to service. The entire periphery of the secondary side will be inspected using an optical device.

There is presently no secondary side Loose Parts Monitoring System (LPMS) for the IP-3 steam generators. The Power Authority feels that it is unnecessary because the present program of effective QA/QC controls during maintenance, periodic secondary side inspections, and effective follow-up of eddy current indications are adequate to prevent tube damage due to a foreign object.

floreover, we believe that the secondary sides of Eteam generators are so noisy that LPMS is not practically capable of determining the presence of foreign parts.

The recent value impact study of these pro-posed requirements performed by Science Applica-tions, Inc. for the NRC concluded that the

installation of LPMS provided a negligible or negative improvement over the inspection and improved QA program alone. The Power Authority concurs with this finding.

2. Stabilization and Monitoring of Degraded Tubes Despite the large number of plugged tubes in steam generators throughout the nuclear industry, there has been only one isolated case of plugged tubes later causing damage to adjacent tubes. In i

this case, the cause was determined to be the presence of a foreign part. We feel the issue of foreign parts has been addressed for Indian Point Unit No. 3. Furthermore, the types of tube degradation which have occurred at IP-3 are such that the complete severing of a tube and subsequent damaging of an adjacent tube is very unlikely.

3. Tube Inservice Inspection Program (ISI)

The Power Authority has conducted extensive

, steam generator tube inspections since the begin-ning of plant operation. These inspections have exceeded existing requirements when necessary to adequately characterize the condition of the tubes. Inspections have included:

. 100% eddy current examination of cold leg tubes

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. Extensive eddy current examination of hot leg tubes

. Eddy current testing of the tube U-bends

. Tube gauging program

. Profilometry

. Tube sample metallurgical analyses

. Flow slot photography

. Independent third party review of eddy current data.

A specific comparison of IP-3's program to the NRC proposed requirements follows:

a. Inspection of cold leg tubes - IP-3 has recognized the importance of inspecting cold leg tubes for degradation since plant start-up. The first inservice inspection of steam generator tubes in 1978 included a sample of cold leg tubes and the last two inspections have included extensive cold leg tube examinations.

b. 48-Month Inspection Interval - It has been IP-3's practice to inspect more than one steam generator at each refueling out-age. Supplementary inspections of the steam generators have also been conducted between refueling oatages. The Power Authority has no plans to reduce the

4 inspection frequency to inspecting each steam generator at least once every 48 months.

c. Elimination of Inspection Category C Technical Specifications for IP-3 cur-rently specify supplementary sampling requirements based upon the number or percentage of inspected tubes found defective or degraded. There are three categories of sampling sizes progressing from the initial 3% sample to the inspec-tion of 100% of the tubes.

The Power Authority does not agree with 1 the elimination of inspection category C-2. The implem.ntation of the technical specification as it currently exists has been adequate to determine the status of the steam generators.

d. Inspection for Denting - IP-3 performed eddy current testing to evaluate denting in its first refueling outage in 1978.

Since 1979, tube gauging has been per-formed in conjunction with eddy current examinations and a plugging limit based upon the amount of tube restriction has been established. Because of the poten-I a

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l tial for improved dent evaluation now possible with profilometry techniques, the Power Authority conducted a sample pro-filometry program during the current outage involving inspections made by two vendors with differing techniques. The data obtained from the two different techniques agreed very well. In this manner, the Power Authority is now able to establish a baseline mark to evaluate the benefits of profilometry and compare vendors for possible further examinations.

. e. InsOections following Primary to Secondary Leaks - The Power Authority is firmly committed to operating T.P-3 with as little primary to secondary leakage as possible, and every attempt is made to keep such leakage at zero. IP-3 presently has a

] very stringent limit on operations with primary to secondary leakage and will perform the required inspections when that limit is exceeded. The Power Authority has consistently performed tube inspection programs in excess of requirements and will continue to perform inservice inspec-i

tion as necessary to ensure safe steam generator operation.

4. Improved Eddy Current Inspection Techniques

, (ECT) i The Power Authority believes that improvement in non-destructive testing techniques should be a continuing goal of the nuclear industry. The Power Authority, through its participation in the SGOG, as well as in projects solely funded by the Power Authority, has supported the research and develop-ment activities designed to improve eddy current techniques. The Power Authority has used multi-frequency testing, sludge height analysis, and j profilometry to inspect the steam generators as such technology has become available. The eddy current testing techniques used at IP-3 eliminate tube support plate, tube sheet, denting, or other similar unwanted signal interferences as well as perform both absolute and differential coil inspec-

tion. From these analyses it is p'ossible to obtain

, a much better indication of the condition of the i-l steam generator tube.

The Power Authority believes that it is in its own interest to locate tube degradation as reliably as possible and that continued improvement in eddy i

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current techniques will proceed without additional requirements.

5. Primary to Secondary Leakage Limit The present IP-3 limit of .30 gallons per minute per SG (432 gallons per day per SG) is more restrictive than the NRC's proposed limit of 500 gpd. The present analysis for IP-3 concerning primary to secondary leakage limit uses a value of 500 gpd per steam generator, which is conservative.

6. Secondary Water Chemistry Program The secondary water chemistry guidelines developed by the SGOG are intended as guidelines only. Water chemistry programs must be prepared on a plant-specific basis to take into account dif-ferences in plant designs, operating conditions, sources of cooling water, and other factors. Also, such programs must be designed recognizing that large expenditures may be necessary to install plant modifications required to comply with such guidelines.

3 The Power Authority recognizes the impact that 1

I impurities in the secondary water can have upon steam generator tube corrosion, and presently has a water chemistry program in place which was developed based upon Westinghouse's recommenda-tions. The IP-3 water chemistry monitoring program

has some 54 continuous analyzers, 13 grab samples, and is considered state-of-the-art. There are corrective actions for out-of-specification water chemistry conditions. These corrective actions include power reduction and shutdowns when cor-rosive conditions exist. The Power Authority has a 2

chemist at IP-3 who is completely responsible for the plant water chemistry. He has the authority to initiate actions when appropriate to adjust the chemistry. There is also a chemist at IP-3 con-tinuously on duty to interpret water chemistry information and to ensure proper operation guide-lines are being met. With respect to SGOG guide-lines, IP-3 can meet all of the limits except those relating to chloride concentration. Measures which would enable IP-3 to meet the new chloride limits and which are presently being evaluated by the i

Po:rer Authority include improvements to the present condenser and installation of a condensate polisher.

l 7. Condenser Inservice Inspection Program l

i A condenser eddy current inspection has been completed at IP-3 to improve overall condenser l per fo rmance. The inspection involved the eddy current testing of more than 57,000 tubes. On-line condenser inspection for leaks is done by helium l

mass spectrometry techniques, a method first utilized by IP-3. The Power Authority is also evaluating an even more sensitive on-line leak detection system and has installed a prototype in one of the condensers.

8. Upper Inspection Ports This is not a proposed requirement for IP-3.

B. Plant Systems Response

1. Reactor Coolant System (RCS) Pressure Control During A SGTR The steam generator tube rupture procedure at IP-3 is designed to:

a. Minimize the releases of radioactive material by identifying and isolating the faulted steam generator and by reducing RCS pressure below the steam generator safety valve settings.

b. Establish capability to supply feedwater to all steam generators and to isolate feedwater to the faulted steam generator.

l l c. Maintain the ability to remove the neces-sary residual heat from the reactor through the intact steam generators via the condenser steam dump valves or atmospheric relief valves.

d. Maintain the RCS in a subcooled state during the recovery.

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e. Prevent overflooding of the faulty steam generator.

In this procedure, the operators are instructed to reduce and control RCS pressure by utilizing normal pressurizer spray, a pressurizer PORV or auxiliary spray, in that order. By initiating such a cooldown and depressurization, primary to secondary leakage will be minimized and.

by observing available plant instrumentation, the possibility of producing voids in the RCS will be minimized.

2. Safety Injection (SI) Signal Reset The Power Authority performed a detailed review of the reset safety injection, as well as other engineered safety features, in response to NRC requests following the TMI accident. In the specific instance referenced, the Ginna design dif-l fers from the IP-3 design in this regard and is not applicable. The improved design of having an i automatic transfer from the Boric Acid Storage Tank (BAST) to the Refueling Water Storage Tank (RUST) l l on a low BAST level does not apply to IP-3. The Boron Injection Tank (BIT) for IP-3 is on the dis-l

! charge of the SI pumps.

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3. Containment Isolation (CI) and Reset The Power Authority hs also reviewed the design of containment isolation and reset following the TMI accident. Modifications to the containment reset design deemed necessary as a result of this review have been implemented. With respect to the specifc situation which occurred at Ginna, at IP-3 the letdown orifice isolation valves receive a Con-tainment Isolation signal, and therefore the let-down relief valve will remain isolated from the RCS. Prior to resetting the safety injection signal, the operator is instructed by the emergency procedure to close the letdown isolation valve, thus maintaining the system isolated.

C. Radiological Consequences Standard Technical Specification Limit for Coolant Iodine Activity IP-3's present coolant activity limits are as required by STS.

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l-t NAME: JOHN C. bRONS PROFESSIONAL Kl.GUKD

.f;eittiar v 19 Al to PreIon~t: TOUCR AL' Tit 0RI'Tl 0F THE STATP. OF NEW YO14 Resident Manager - Indian reloc 3 Nuc1 cur Power Pitant Buchanan. New York 10511 Senior Pcwer Authority Manager at the site, having overall responsibility for tafe, efficient and dependable operation of Indian ?oint 3 Nuclear Feuer Plant. Implement all admin-isrrative controls in confor:ance with applicable regulacory requirements regarding the facility and respnnaible for j ~

coordination of all station functions through the Superin-tendent of Fowar, Plant Superintendents and other key personnel. Serve as chairman of the Plant Operations Review Co=mitece and as a member of the Safety Review Committee.

June 1959 to January 1981: UNITFD STATF,S NAVY June 1978 to January ljS1: Senior Me=ber, Suclear Propulsion Examininz Board _ reporting to Admiral 'd. G. Xickovar, USN and to Cc-aander-in-Chief, 11 . S. Atlantic Fleet. Conduct annual inspections of all Atlantic Fleet nuclear powered ships to set standards of continued saf e reactor operation. These intensive inspections, requiring f ree two to four days per ship, are conducted by a senior = caber supported by a 6tcu; of offi:ers who have served us Engineer Officer of a n. clear pcwcred ship. Each examination includes: observation of cascalty drills, maintenance evaluations, water cho:1stry and radicchemistry analyses; verification of adequa:e maintenance of systems -

af fecting reacter prctection; E1=inistrative reviews of training, qcalification, technical dccu=enta:1ca, radio-logical controls, che=1stry cont:01s, vaste dispesal a=d radiatice health; verification of edequate Operator icvel of knowledge thrcugh oral and written exs=tratiocs. Ic is within the authority of the Senter Member, based upon exam-ination results, to. allcw license for ccctinued reactor operation to re=aic with the ship cr to revoke chia license -

if deviations f rem the standard require it.

Conduct similst inspecc! css with s:phasj s en radiological centrols practices, en nuclear ship r.sintenance incilitics.

Inspect training f acilities ashore for adequacy ef t raining support for ruclear operaters. 6 Aerve and evalc.1:e drills demonstrating here iort si:cs' pr>."ared mas for envrienc'es aSEcciaLQd With the ShirdGrfA nGC1637 r e Jt. : ora.

Assignment enta11a briefing of ths Commandurs of th3 Air, Surface and Submarino Forces. Atlantic, tha technical senff l

I nf the Division of Navel Resctora. Department of Encrgy, dnd Cc=randing Officers on the performance of their ships in the reactor safcauards area.

Aurhored a technical article concerning the audit of all aspects of radicilogical controlo Operations and a nuclear fleet vide proevdure for obtaining,cend uteur, reliable r adiocheniistry san ples. Cont ributed tc ether all ielos and procedure 8 dvaling with re;,ctor plant traiaing und opet-ation, notics re' quired extensive travel on the castern scaboard and in Western Europe.

May 1977 to June 1978: Deputy Commandar, Submarine Squadron Six. Responsible for the training'and readiness of thirteen nuclear fast attuck 4 sub=arines of this iJorfolk based squadron. tJorked with the individual Cocmanding Officers to train their crew s in the areas of weapons employuent, use of tactical sansors, communicatiens equipment, deployed operations and nuclear propulsion plant matters. Prepared opera: ion plans and schedules to evaluate the results of this training and to measure the ship's readiness. Plans frequently required coordination of naval air and surface forces supporting these cperations. Conducted various inspectior.s to insure high standards were maintained in reactor plant and unapons safety. Played a prominent role in the deve.icpment of operating doctrine for the advanced digita'. sonar and under-water fire control systems of the SEN tS8 class submarine follcuing delivery of the lead Ahip and acbsequent ships to this squadron. Authcred a major article en weap;ns e ploy-ment tactics and seve:41 monegraphs an tattical sensors uhtch were adopted for submarine farce wide use. kestored a World War *1 Auhmarina for use #4 a submersible, expendable target.

June (973 to April 1977: Ccemandint Officer, USS RICHARD 3. HUSSELL ISSN 667).

Assign =ent consisted of two distiretly diffarent phases.

Initially for:ed the crew during the ship's construction at Newport News Shipbuilding, a diviaien of Tenneco, at Newport News, "irginia. Developed ship's procedures and trained watch standers to condect reactor plant testing and startup.

Operated the ship en builder's and government trials. -

Represcated the Navy in monitoring the quality and rate of construction. Acted as the government ag+At in the a:-

cc7tacce Of all ship's sys c7s preparator/ to delivery-Ccordinated tLe efforts of 80 seral ;,averre.c.nt agencies anc c'ie c i911 t an sh ip bv!1 der in a ceiplex milit.arv-i m s: rial effort. l.chie.ed ;r t.r.r.vai rappre t etween r ; e c r c ' A..d t!'e s: at;i' dur d i.n resulted in a highly 4..c essful l

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r hovornmant acceptcnce trial with a rccord low nusher of construction deficicncias, and in dalivery of'cha chip to the Navy somewhat earliet than expected. Sff orts uon wide praise frem both the government and the ship builder.

Following commissioning, USS ROSSF.LL was assigned to the Submarine Development Scuadron in New London, Connecticut f er shakedcun a.%! deple. . ' . :u rat iois . IA n loped ..ps-rat ing precedus es f .r t iie Navy *t. ittst dt.;ttal underwater fire evatrol system, lh pin n d tf.e tirst .sulmut ine sat t 11 it e evmmunications 8v= tem nr.d a bread board digital svster. f or over-the-bori?.on tareettns. Directed the urendration of wvers! digit al piogran; t o norhanize t ruise mis 4110 control algorithics and anti-submarine warfare search procedures for shipboard use. Briefed senior Navy and DOD of ficials on the se and other Atare of the are nvatoms.

Throughout both phases managed all aspects of ship's oper- .

4 ation und nintenanea including perannnel and fis..a1 matters.

June 1971 to

.lu n e 1973: Euccutive Officer, USS JACK (SSN 605). Supervised crew training ship's administration. maintenance operations and persennel matters during a thirteen month overhaul at the l'urtrmouth Naval Shipyard, Kittery, Haine. lleavily involved with the unusual aspects of maintenance und operation asso-ciated with this ship's unique steam propulsion plant.

Resolved numerous difficult peraonnel situations arising from the relocation of the ship's crew from the overhaul yard to a new home port in the midst of an Jecclerated schedule to deploy for high priority operations. Coor-dinated this home port shift, several major inspections, intensive training requirements and a change of cc:=and in one-fourth the norinal allatted time. Managed a pilot proAram which permicted nearly 50 percent of the cr=w te return t o the linited StJteG f rom the Mediterranean for leave and advanced schooling, which resulted in retention and advancement statistics for the crew which were well above r

the fleet uveraxe in spit e of the ship's de~.anding Operat ional c s n 5 ad o li-l

.iun e 147C co

. lune 1971: Graduate student. Rensselaer Folvtechnic Institute.

Avarced Master of Science in FWnagement. Clected member Epsilon Delta Sig=a Management Honor Society fer achieving a grado point acerage of 3.87 over 45 graduate bours. _

! Offered a teaching fellowship in accounting but Navy ecm-mitments precluded acceptance. Selected by the Dean to participate in a managencut consulting effort at t he hTI Corroration. Schenectudv. New Yerk. Directed the financial managecent and accc.nting portien of the wtudy. Auther of

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!e4 le- I Y 'l} l . . s ' t. 61 L ( '.' e b([8.'Vf,

. *5 6 6 k a . p .i'.-i t'- I fI .t 5 31 $ J ! I!1( A( 'd t 'd i, l til l t i.n , 'n w Y.rk. Tralr'ing uni' gyngistej o( tuo prn:ct.r.e i

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w r reacto: plants with associst cd clanroom, : aintenance and administrative f acilities is operatred for tha Navy by the-Knolls Atomic Power Laboratory (KAPL) of the Gencrs! Elec-tric Co=pany. Position of 10 ecucive Officer required a high degree of coordination between Navy, Atomic Energy Com-inission (MC), and KAPL personnel. Managed personnel administration for # combined staff and student population oft *ulti Heh 'enitorvu .11 .uovet.s of ti.sining over-

.itions. .bsisted l* ipL J pes ....nnel in Se dovslopment of new t i a ining pi c. grate.. .Monitered reactos plant i.perations including a refueling ain! nerelerac t d core ds piction f or

....iety and ; recedur:il ei.np; isnu i- r pert ing t e th0 senior AEC repr es en tst ive . Partici;iated in qualificat ion examinations for nucicar propulsion plant operators including Chief Operators as the AEC repre8entative.

Hay 1965 to Thi.= ship built i March 1968: Q1ef Engineer, USS STURGEON (SSN 637).

at the f.lectric Boat division of the General Dynamics Gnrporotton in Croton, Connecticut is tite lead $bip of the Navy's largest class of nuclear submarines. Initially working with quarter scale wonden muck-ups well before the i ship was launched, participated in inany design developments which have become standard in all follow on ships of this versatile and highly successful class. Prepared all ship's system operating procedures. Tl' eve procedurea were adopted as standards for remaining ships of the class and in some cases for other classes of ships with similar systems.

Trained the propulsinn plant crew. Acccmplished reactor plant pre-core. post core and critical testing in less time chan lud ever been donc at that shipyard. Assumed addi-tional duties as the ship's senar of ficer during its f'rst

deployment f ollowing co=tissioning.

00 t cheh r l#s M t o "

M.sv 19 0 : Supply Officer and Main Propulsicn Assistant. USS DACE (3SH 607). P.stablished Supply Department procodores as a member of the pre-cc.:missioning detail of this new con- .

struction submarine at Iny, alls Shipbu11diop,, a division of Litton Indistries, et Pascagcula MLssi utppi. Supervised initial load cut and continued repair parts support. Man-aged a three million doll.>r (1963 dollars) inventory and a S400,000 annual operating budget. Accountahle for all cor.uissary and fond service operations. rollowing delivery of the ship to the Navy in April '9M, assurted concurrent ~

dutics as P. sin Propulsion Assistant. Supervised operation and maintenance of all fluid and mechanical systems in the prcpulsion und reactor plants.

barch I N to

,. r i . he r :953 Eut srine sni iucicar traiaine. Gradustt.d in the top ten _

rcrrent Of tbtav Of f icer * . advanced enuru a, j

i t, t A t- 1943 1.

' . CS . T /1 l  : + r v.6 r V I.' ')':.U.it M i .11 i . '" . di f 1rM . 's M J l 'T. s'D!.C 10).

the p r t.- C 07.r'.1 Cs i ofl i t s y, d -( .i t i nn 1 : s i f. 61cv COe dt r.;0 t iori I

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frigate built at Puget Sound Naval .9hipyard, tirtsrcon, liashin gton. Supervised the instellation, tacting cnd

, initial operation of the fira: shipborne computer controlled, high capacity cum =unication syste:n. Worked closely with representatives of the vendor and the Navy to develop this system which is new in widespread use.

h:1- : t.c., t.1 ( s.

s te t e bie r l';un: Xavic.it er and Cewniais at ion- Officer, IS$ l. K. Stin: SON

( 1 71) 729). Siiper viria d ulsip' S it.w ir:t( ivin .sud OcemunicallenF.

durine a t.ide varietv .si otcrationi. throuchen: t he- Pacific nei,ta:i.

ECS'.iLULN ECt.*S :

Vice Chairman, Saratoga County (New York) Red Crosa 1969-1971. Chairman Industrial Tund Raising Campaign Saratoga County Red Cross 1970-1971 Member Constt r ee to evaluate and selecc mathematics t extbooks for llampton Virginis elemen-1.ary and junior high schools (1974). Member. Parish Caunci t I

of various Recan Catholic churches. Designated by the siavy as a proven subspecialist in engineering and in weupon8 systcm Jequisit ion manage::unt.

EDUCATION: U. S. Naval Acadcaty, S. S. General togtueering 1959 Rensselaer Polytechnic Inst itut e. H. S. Management , 1971.

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• Resume of William A. Josiger Power Authority of the State of New York July 1980 - Superintendent of Power Present Superintend the functional operation of the Indian Point 3 Nuclear Power Plant by exercising control over the Operations, Maintenance, Instrumentation and Control, Health Physics, Chemistry and Technical Services Departments to assure safe and efficient operation, high availability and capacity factors, and compliance with governmental regula-tions. Develop and administer outage controls so as to minimize downtime. Develop management procedures and systems to assure proper communica-tions, to develop personnel, to coordinate site i activities with New York Office Activities, to resolve Nuclear Regulatory Commission and other federal agency concerns, to promote safety, and assure proper documentation of site activities.

Act as: Vice Chairman of the Plant Operations Review Committee which oversees Nuclear safety related activities; Co-Chairman of the Industrial Safety Committee which reviews industrial accidents and safety policies and recommends plant improvements; and Alternate Emergency Director during a radiological incident having impact (potential or real) on the neighboring populace with the responsibility of implementing the Site Emergency Plan.

July 1979 - Technical Services Superintendent July 1980 Provide on site technical support and monitor performance of the plant, its components, and reactor core to ensure that they are being operated safely, reliably, and economically. Develop -

management controls to allow personnel to effectively and safely carry out their assigned responsibilities in accordance with good engineer-ing practice, quality assurance requirements, and l

governmental regulations. Direct the preparation, l evaluation, and approval of proposed modifications to the facility and approve and issue nuclear -

safety evaluations and nuclear fuel accounting procedures. Direct the resolution of technical

concerns raised by plant personnel and various l'

auditing groups to verify that the plant is ,

operated and maintained within established guidelines and regulations. Serve as a member of -

the Plant Operations Review Committee. Direct the development and physical accomplishment of the required In-service Inspection program, i

Serve as one of the site emergency directors responsible for the timely and accurate assessment of any nuclear related incident at Indian Point 3 and assume total responsibility for directing the emergency actions of the on-site emergency organization.

June 1976 - Technical Services Engineer July 1979 Supervise all aspects of engineering services required to support the continued safe operations and maintenance of the nuclear power plant.

Resolve technical concerns raised by various auditing groups to verify that the plant is operated and maintained within established ,

guicelines. Assist in critical path planning for -

major outages to reduce system and plant d own time . Coordinate the installation of new facilities with the major contractors and plant operations staff, the tie-in of new plant facilities to existing plant systems, and the testing of these facilities to ensure proper installation.

Consolidated Edison Company of New York September 1974 - Unit No. 3 Test Engineer (Startup)

June 1976 Served as the lead member of the working Joint Test Group. Responsibilities included coordinate ,

schedule and direct all plant activities and support organizations associated with the startup test program; prepare, review and approve all test procedures and test results; directly responsible for maintaining the test and plant acceptance pro-grams; and resolve technical problems and provide -

technical input for licensing issues.

September 1972 - Unit No. 3 Nuclear Support Engineer (Startup)

September 1974 Responsible for preparing written system descrip-tions, plant operating procedures, training materials, plant emergency procedures, and test procedures for Indian Point Unit No. 3 facility. _

Responsible for providing technical input for i

related problems in the areas of facility licens-ing, equipment problem resolution, and other miscellaneous problems encountered.

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General Dynamics Coro. Electric Boat Division February 1970 - Nuclear Testing Supervision (STE)

September 1972 Responsible for the safe and' orderly testing of all reactor plant systems on S5W Nava.1 Nuclear Power Plants during all phases of the test program including initial criticality, physics acceptance, and power range testing.

Nuclear Test Engineer Participated in 8 month training program to become qualified by the Naval Reactors branch of the Atomic Energy Commission and General Dynamics management personnel as a Nuclear Testing ,

Supervisor for S5W Naval Nuclear power plants.

Nuclear Projects Engineer Responsible for the design of nuclear fluid systems associated with S5W and S5Wa Naval Nuclear power plants.

Dortech Incorporated Division of Door Oliver June 1968 - Engineering Aid February 1970 Responsible for designing mechanized air cargo handling systems, evaluated proposed designs and preliminary design of mechanical components.

Draftsman Responsible for preparing drawings of proposed air cargo terminal layouts.

EDUCATION l 1967 Degree - Associate in Applied Sciences Westchester Community College Valhalla, New York 1970 Degree - B.S. in Mechanical Engineering University of Bridgeport ,

Licensed Senior Reactor Operator on Indian Unit No. 3 o

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges:

James P. Gleason, Chairman Frederick J. Shon Dr. Oscar H. Paris I

)

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 Power Authority's Testimony of John C.

Brons and William Josiger on Board Question 2.2.1 and Power l Authority's Testimony of John C. Brons, Kenneth R. Chapple, j

and William Spataro on Contention 2.2(a) to be served first clans mail, postage prepaid, on the following:

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l l

l I

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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 the 513 Gilmoure Drive State of New York Silver Spring, Maryland 20901 10 Columbus Circle New York, New York 10019 Mr. Frederick J. Shon Administrative Judge Janice Moore, Esq.

Atomic Safety and Licensing Board Counsel for NRC Staff U.S. Nuclear Regulatory Office of the Executive Commission Legal Director Wa sh ing ton , D.C. 20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Oscar H. Paris Administrative Judge Brent L. Brandenburg, Esq.

Atomic Safety and Licensing Board Assistant General Counsel U.S. Nuclear Regulatory Consolidated Edison Company Commission of New York, Inc.

Washington, D. C. 20555 4 Irving Place New York, New York 10003 Docketing and Service Branch Office 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 506 Joan Holt, Project Director Washington, D.C. 20006 Indian Point Project New York Public Interest Research Charles A. Scheiner, Co-Chairperson Group Westchester People's Action 9 Murray Street Coalition, Inc.

New York, New York 10007 P.O. Box 488 White Plains, New York 10602 Jeffrey M. Blum, Esq.

New York University Law School Alan Latman, Esq.

423 Vanderbilt Hall 44 Sunset Drive 40 Washington Square South Croton-On-Hudson, New York 10520 New York, New York 10012 Ezra I. Bialik, Esq.

Charles J. Maikish, Esq. Steve Leipzig, Esq.

Litigation Division Environmental Protection Bureau The Port Authority of New York New York State Attorney and New Jersey General's Office One World Trade Center Two World Trade Center l New York, New York 10048 New York, New York 10047 I

Alfred B. Del Bello

Westchester County Executive Westchester County 148 Martine Avenue j White Plains, New York 10601 Andrew S. Roffe, Esq. '

j New York State Assembly Albany, New York 12248 l

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Marc L. Parris, Esq. Atomic Safety and Licensing Eric Thorsen, Esq. Board Panel County Attorney U.S. Nuclear Regulatory Commission County of Rockland Washington, D.C. 20555 11 New Hempstead Road New City, New York 10956 Atomic Safety and Licensing Appeal Board Panel Phyllis Rodriguez, Spokesperson U.S. Nuclear Regulatory Commission Parents Concerned About Indian Washington, D.C. 20555 Point P.O. Box 125 Honorable Richard L. Brodsky Croton-on-Hudson, New York 10520 Member of the County Legislature Westchester County Renee Schwartz, Esq. County Office Building Paul Chessin, Esq. White Plains, New York 10601 Laurens R. Schwartz, Esq.

Margaret Oppel, Esq. Zipporah S. Fleisher Botein, Hays, Sklar and Hertzberg West Branch Conservation 200 Park Avenue Association New York, New York 10166 443 Buena Vista Road New City, New York 10956 Honorable Ruth W. Messinger Member of the Council of the Mayor George V. Begany City of New York Village of Buchanan District #4 236 Tate Avenue City Hall Buchanan, New York 10511 New York, New York 10007 Judith Kessler, Coordinator Greater New York Council Rockland Citizens for Safe Energy on Energy 300 New Hemstead Road c/o Dean R. Corren, Director New City, New York 10956 New York University 26 Stuyvesant Street David H. Pikus, Esq.

New York, New York 10003 Richard F. Czaja, Esq.

Shea & Gould Joan Miles 330 Madison Avenue Indian Point Coordinator New York, New York 10017 l New York City Audubon Society 71 West 23rd Street, suite 1828 Amanda Potterfield, Esq.

New York, New York 10010 Johnson & George 528 Iowa Avenue Richard M. Hartzman, Esq. Iowa City, Iowa 52240 Lorna Salzman Mid-Atlantic Representative Ruthanne G. Miller, Esq.

, Friends of the Earth, Inc. Atomic Safety and 208 West 13th Street Licensing Board Panel New York, New York 10011 U.S. Nuclear Regulatory Commission Stanley B. Klimberg, Esq. Washington, D.C. 20555 General Counsel New York State Energy Office 2 Rockefeller State Plaza Albany, New York 12223

Mr. Donald Davidoff Director, Radiological Emergency Preparedness Group Empire State Plaza Tower Building, Rm. 1750 Albany, New York 12237 Craig Kaplan, Esq.

National Emergency Civil Liberties Committee 175 Fifth Avenue, Suite 712 New York, New York 10010 Michael D. Diederich, Jr., Esq.

Fitgerald, Lynch & Diederich 24 Central Drive Stony Point, New York 10980 Steven C. Sholly Union of Concerned Scientists 1346 Connecticut Avenue, N.W.

Suite 1101 Washington, D.C. 20036 Spence W. Perry Office of General Counsel Federal Emergency Management Agency 500 C Street, S.W.

Washington, D.C. 20472 Stewart M. Glass Regional Counsel Room 1349 Federal Emergency Management Agency 26 Federal Plaza New York, New York 10278 Melvin Goldberg Staff Attorney New York Public Interest Research Group 9 Murray Street New York, New York 10007 Jonathan L. Levine, Esq.

P. O. Box 280 New City, New York 10958 N'dt b ObA r.

Joseph J. Levin, Jr. I g, .