ML20148G615

Informs Commission of NRC 780205-18 Visit to Ussr Re Exchange of Info & Cooperation in Nuclear Endeavors. NRC Should Sign Arrangement to Cooperate W/Ussr in Exchange of LWR Safety Info.W/Supporting Documentation

ML20148G615
Person / Time
Issue date:	03/21/1978
From:	Lafleur J, Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP)
To:
References
SECY-78-011B, SECY-78-11B, NUDOCS 8011120687
Download: ML20148G615 (63)

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n UNITED ST ATES NUCLEAR REGULATORY c0MMISSION g

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C- '"5 March 21, 1978 SECY-78-llB INFORMATION REPORT F*

lE ElLE COPY;

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g;1=W WE For:

The Comissioners lgg From:

Joseph D. Lafleur, Jr., ' Acting Director.

=#K Office 'of. International Programs Victor Stello, Directer

.......E E=

Division of Operating Reactors Office of Nuclear Reactor Regulation Thru:

Executive Director for Operatione

Subject:

NRC TEAM VISIT TO USSR, FEBRUARY 5-18, 1978 s

5

-To report to th' Comission on the NRC Team Visit and the con-purpose:

e clusions of the team.

Discussion:

SECY 78-11 reviewed the history of discussions between NRC and the various Soviet agencies involved in regulation of light water reactors, concerning possible cooperation on light water E=

safety matters. ' The staff recommended, and the Commission c

approved, (1) that there should be an exchange of visits, start-

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ing with a visit to the USSR; (2) that the NRC decision should be -

deferred on whether the LWR safety cooperation should fall within

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either the existing US-USSR Agreements on Cooperation on Energy or Atomic Energy, or whether the LWR safety cooperation should be independent; (3) that the Soviets should be invited to make their return visit during the period March 26-April 8,1978, and (4) that EI.

the SECY 78-11 revision of the outline entitled " Discussion points" i.]

that was passed to the Soviets earlier should constitute the NRC

.st.E position for discussion, during the visits, of an arrangement for gj.j.!l <

cooperation.

EO Mif The purpose of the visits is to let each side see what is being EEx done on the other side that is of interest for the cooperation, Es.

and to further discuss. ions about the scope and.other provisions s.i of an arrangement for cooperation, sss?

E THIS DOCUMENT CONTAINS POOR QUAUTY PAGES 7

Contacts:

p V. Stello, NRR, 492-7672 COPY SENT REGION g-M

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J. D. Lafleur, Jr., Ig 9}-7,1 10-gg7 mm w

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.5 The names of the US team, as reported in the January 25 memo-randum of the EDO to the Commission, are included in Appendix A, which also contains nimes: and titles of the key

[ss; Soviet officers we met.

Since DOE elected not'to send a

~

representative, and the interpreter, Mr. Joseph Lewin of ORNL E

is a contract employee of NRC, the team was an NRC group, sup--

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ported by the Department of State missions of Moscow and Leningrad.

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The $tinedf7of the trip and notes on all technical meetings are MF given in Ap (pendix B.

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Appendif C:isla loint' report'of:the discussions on cooperation,

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the " Protocol" of the visit, signed by the heads of the Soviet gg=e

.and.US Delegati 6nsa:::-

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Our host was L.-M. 'Voronin, Chief. Engineer of "Glavatomenergo,"

EP the' Main Administration for Atomic Power Plants of the Ministry s:l:

6f: Power:and Electrification :(MPE). Voronin probably will head the W

Soviet Delegation of their return-visite A luncheon meeting with m=-

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th6 C6mmissi65efi sHddld255 arranfed.i Th'e team was fully satis-

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fied with the program as hosted by MPE.

Despite the serious com-

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inunications: gap:that sur. faced -frequen'tly~,' we were well received at each site and were given thorough presentations on safety and environmental protection matters.

The itinerary as noted in SECY 78-11 included all. the sites that we had requested. 'The'.

people at.each si.te 'seemed :to fiav'e been instructed to' talk frankly wi th - u s :a od : to.a n swe s. -qu e s.tio ns -fr' eely...

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One minor problem-occurr.ed, when the Ministry of Foreign: Affairs g~

held up-approval. of the vistt of. Allen;Greenburg, an official' member qf our dele.gation, to.the -Leningrad Power Plant.

Because thi.s.appeqred to-be deliberate harassment, because the Embassy -

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advised ;that i,t ;is.~ typic.al.of.~r,ecent; e.fforts to isolate the:

Embassy.from~ visiting teams,-and because it was not clear that.

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MPE 'had'h'a'd k.chan'ci.~to' rea'ct,- th'edea'mdimply del ayed. the: /isit E

u6till:the:ap?pr6valia's Irec'eide'd.. '-Thissas reported in telegram ---

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Ce616 grad 479 anadhe'd.. It' dayUb' -that-our' hosts.indhe kinistry" 5

e 6f:Powdh ddd EfecYrffi' cit' ion'Ead"no.t hea'rd.of the dsfpRovaiy j.3..

rob'aSTy made'by security'peo'ple.

In any case, soon 5

whictiwas.p'dlined to proceed, and assured that MPE was aware of sftEF W6'de

-~~~

4t, the.vis.it of.the ful.l. teant was. approved..The. net,effect was

!=EE that'We'did our. 's.i~ghts:eeing1'in"LeningFa~d on Thursday ind thE crew at.the Leningrad. Power Station' had to come.in to receive.us.on E=f Saturday,Linstea'd.'of'.vic~e 'vey.sY.:. At' thh ~ tart of our meetings on lEg s

retdrn 'to Mdsco~w,' Yo'ronTn~ YpoTog'iz' d for any inconvenience this PE e

had caused.

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Although it had not been planned that eithef. side would give' writti.n technical reports, that being one. of the purposes of the E

future cooperation, we learned of the existeoc'e.of.several interest-

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ing standards and technical safety reports..;0ur suggestion of an early exchange of such reports fram.both sides is recorded.10 the Protocol, in,which the Soviets agree.to. respond bf _ March'15GIThe.

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team believes a favorable response would indicate' good progress has been.made..and.would. tend to show. good faith on the.part.of..

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the Soviets.-

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A. separate listing of LWR safety research. projects is.in Appen-dix E.

These projects are also discussed;in;Appendig'B..-

Despite a der [fuil work schedule, we were treated to an impres-sive program of cultural and social. events.. We.saw performances of the new ballet Anna Karenina at the Bolshoi Thsater in? Moscow, and the classical. ballet Sleepina Beauty.at!thelirov; Theater.in...

Leningrad, tojname.only the highlights.. 'We are advised.that" :.:

tickets.to'sugh evente are very. difficult to obtain. a6d that.FjPE obtained them,'for a group'cf our rant,16dicites;high-level'sup-port of our visit..At each site, the:offidial:dieal5.a6d.other. '

hospitality were outstanding: This will'be' difficult fof NRC to equal during the return visit.

The.Commi.ssion.will be advised of preparations for the: Soviet visit within.the.next-fegdays...

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The following are the~ conclusions'opthe OS

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1.

NRC should sign an arrangement to cooperate.with the USSR in~exchangeof. LWR. safety.informatiorj.

2.

MPE is'the best Soviet agency.with.which to enter?into a cooperative :arrangsment...Their responsibility,'wflich includes the design, construction and' operation.cf light water:nuclsar power plants, also includes.the responsibilities :for~specifying.and :..

enforcing' safety! design. details. ~ThEy are the.Qo19'igenc9.that has. records.of oper4 ting expefience that NRQ would like:to~ exchange.

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nigal.,"('and."Mee inspection agencies ?(for "cCificality,"[ tech-M.

3..The.

sanita ry'.'.cQntrol ). operate "EEs like.ouf ASME (in_ performing. inspections;i6dependentlyrand.more

).and 'the 1ational.Radia-

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tion 'Cduncil l(in making radiation exposurd'reconTjiendation5):than 55 like NRC. -It would not"be practicable to have.an agreement'with

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these:" inspection". agencies, because Qf'their limited areas.of.,

[gg responsibility'and'because they.are mot organized.under:a. single Es=

head.

Instead, we should propose-in understanding that MPE and

=m NRC each would assist the other in obtaining information originating sE from such organizations.

Such a proposal is included in the

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Protocol.

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s 4.

It is not clear whether the Soviets want to exchange information on both PWR's and BWR's or only on PWR's.

Their BWR's are graphite-moderated, like the pressure tube reactors at Leningrad, which are quite different from US BWR's.

As noted in the Protocol, the US Delega~ tion proposal for early exchange of documents includes safety reports on PWR's only, because.we be lieve.their 1000-MWe PWR desi.gn incorporates their latest safety:

concepts and is more similar to latest US designs than anything else they have.

The team believes the US side shodid. explain:to the Soviets that restriction of the exchange to PWR's would penalize them more than us: US BWR experience is largely appli-cable to -all of their plants, and we.have many.BWR's.-

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.,AcMngDirector[

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eur, fice of International Programs

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Vi or Stello, Director-Division of Operating Reactors

- Office of Nuclear Reactor Regulation

Enclosures:

1.

Appendix A, Names of US Delegation

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and Soviet Officials met on trip.

2.

Appendix B, Itinerary and Notes on Technical Discussions' 3.

Appendix C,."Protoc.ol" of Visit 4.

Appendix D, Telegram Leningrad 479 5.

Appendix E, LWR safety.research

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Appendix A

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s fii USNRC Delegation to the USSR on Reactor Safety - Feb. 5-18, 1978

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Joseph D. Lafleur, Jr., Deputy Director, Office of International Programs Victor'Stello, Director, Division of Operati6i Reactors, Office of Nuclear

~

Reactor Regulation EE:=

~ " "

Boyce Grier, Director, Region I, Office of Inspection and Enforcement'.

Long Sun Tong, Assistant Director for Water Reactor Safety Research, isiEiE Office of Nuclear Regulatory Research Frank Schroeder, Deputy Director, Division of Systems Safety, Office of 2

Nuclear Reactor Regulation Joseph Lewin, Interpreter, Oak Ridge National Laboratory

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LJ Appendix A I

USNRC Deleastion to the USSR on Reactor Safety - Feb. 5-18, 1978 Ei Joseph D. Lafleur, Jr., Deputy Director, Office of International Programs Victor Stellos Director, Div'ision of Operating Reactors Office of Nuclear

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Reactor Regulation

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' Boyce Gr;ier.; Director. Region I, Office of Inspection and Enforcement

.Long Sun _ Tong, Assistant Director for Water Reactor Safety Research,

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. Office of Fuclear Regulatory Research

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Frank Schroeder Deputy Director, Division of Systems Safety. Office of

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Nuclear Reactor Regulation

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Joseph Lewin. Interoreter, Oak Ridge National Laboratory hz:..

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Notes on the List of Soviet personnel that met and interacted with the U.S.N.R.C. delegation to the USSR, Feb.5-18,1978.

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E ~" The transliteration system used in this list is the British Standard institution (BSI) System in use h at ORNL and at DOE-TIC. Some obbreviations that may be used cre: "j:: . =fi. APS = ctomic power station i HE! = heat engineering institute KIAE = Kurchatov Institute of Atomic Energy, also colled Institute of Atomic Energy named offer Kurchotov. Minenergo= Ministry of Power and Electrification Giovatomenergo= Main Administration for Atomic Energy (of Minenergo)

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SCST = State Committee on Science and Technology of the Council of Ministers SCAE = State Committee on Atomic Energy (of the Council of Ministers) Photographs and comments on previous roles of some of the personalities involved will be forwarded at the earliest opportunity. i a .loe t.ewin ORNL l[ Bldg.3500 DIO f!! Ook Ridge [.;- Tenn. 37830 g y= :: - bb 5 !' r-- h-E... ""~.I = .-7 ~ -*-* 3 q -m

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L:. G.:.. : - a. : -_..w ~.... -. w j l 4 r 3 &l I 4 listino of Soviet eersonnel that met with end interceted with the US orovo: Lopotin,Nikolai Alekseevich - Deputy Minister of Power ano Electrificati on fo 16th of February.

l. Met at the airport (Sheremetevo I )y with Drs.LoFleur and Stello o briefl by:

Karell'n,.EYg'enii Petrovich PMinistry of. Power and Electrif F r PorerMovilg'o'r' Serge'evidh' Minenerge, Division of Foreign Relations, Services Branch [-' Myogk'ov, Victor Nikoidievidh"-Novovoronezh Atomic Power Station,Inform =.,, Relations Worker, Interpreter. ]. + ......F c '-~ ~ 7-e.. 1 At the first riie'eli6g cFMin'energo Division of Foreign Relations conference room: .... a.. Voronin,Leonid Mikhailovich - Chief Engineer of Giovatomenergo. n Ex... Mol'tse'v,Vlo~difen Nikolce'vich -Minenergo; Executive: Secretary of Soviet Port o '~ , Committee on Energy. ,,,,*;, :* ; -.. a t : ;;:,.::...,.....g....., Karelin,Evgenii Petrovich - Glovoromenergo (os in part !. above). ) r.r Troshin,Vossilii MikhcIlovtch - Senior Consultant, Division of Foreign Relations,Minenerso. ,.u Doroshchuk,V.E. M Director of the All-Union Heat Engineering Institute name Bukrinskii,A.M. - Laborotory (Department) Head, HEl. n [ Okhotin,Vladimir Nikolaevich - Chief Engineer of Heat-Power Design Institute (T

g. ;

Totornikov, Victor Petrovich - Deputy Chief Engineer of Teploelektropreekt. b 4:- Kirillov,Aleksandr Petrovich - Deputy Director of Reinforced Con ~.. E Station jnspectior) Department of State Engineering E l Kononov, V.I. - Deputy Chief of Atomic Power Inspection Service (GosgortekhnodzorT:-

p 6

i g". Turovskit,Volentin Dmitrievich - Chief of Atomic Power StationInspection Service (Gossonnedzor). Aii=N Arifmetchikov,E.F. - Group Leoder in Division of International Re T, E ' only as a possive observer). {j. Filatov,A.S. - Giovatomenergo, Operating inspection Division, Assista i.i;p Deputy Director of Gossonnadzor. h Kosotkin,B.I. - Chief Inspector of Gosgortekhnodzor,Kovalevich,0

1 g-Romodin, Sergei Vladimirovich - Interpreter Emel'yonov,Vsevolod Nikolaevich - Abstractor (or literature searcher)of the S s.

~ and Technology. -i-- =.: ~ - -. h 1

u -4..-= t..=.=.-- M...... iw =.? $5 -":=

3. At the meeting and briefing at M_a_in _ Admin __istration., Build _ing.of Teploelektrop E.-

--v= a.

==,

• ='?'

Okhotin,Vladimir Nikolaevich - Chief Engineer. .== d i il tation on VVER-1000 design). i=:=. .= .Totornikov, Victor Petrovich, Deputy Chief Engineer (ma e pr nc pa presen -.--.-.: =. +.. r== Vokhromeev,Evgenii Gri'g'o'ribvich - Deputy Director of institute. E- ; ~ ~ ~Smirnov, Oles Ivonovich 'En,gine.. ?..

= :.

= =.. - er

=.:.r

-.. :- !.. ': !.i : ~ 'Neshu'rnov, Feliks Serse'ev.i,5h - E.n. gins.er- ? g:.... - = ~ '~ n.feb7+]978 ~ W.~. At 'the 41stt t'o 'the tr siit'ute[oi At6miciEne'rgy nomedafte'r Kurchato Sidorenko,V.A. - Director, Division of Power Reactor Projects ~" ' Kovolevich,Oleg Mikhail. ir.h....- Sen~ior Scientific'Wdrker. ~ ~.- 3.:..a ov . u ;-.

==

Kromerov,A.Yo, - Senior Scientific Worker; pressure tube reactor specialist. gn= =... Dikarev,V.S. - Senior Scientific Worker, member of Gosatomnadzor for criticolity ; reviews. ll.2 = Poletoev,G.N. - Scientific Worker, PWR onalysis specialist. TE.- e li ,Khudoyorov,A.V. - O,fficer of Division of Foreign Re at ons. ,w.... [::= S.:.=.

5. At the visit to the HEl no~med of ter Dzerzhinskii, Feb.7,1978.

r= : i.E. E . e.:.

2*::.

Doroshchuk,V.E. - Director.. ...v-Bukrinskii,A.M. - Director of Nuclear Power Station Department. g:= .= E:' - Taretskii,'L1.N Directof of'another Nucleor' Power Statiori Depoitmerit. p.==. 7= : .: w :.....s .::: p - =... L,...1 Mironov,V.N. - Director of. Nuclear Physics Department.

==:

g:p Mol'rsev,B.K. - Director of 6 nether Nu~ clear Power Station Department.

===1 .-..~-.....:- ..,J.D...,.

==j ~ ~,.] ' ", ~ ~ ._,Grvzdev,N.1. -7 Directof,(.. -. WetEr;Ch6mistry D.epdrtinent. ~. ... a Morskevich,G.'V. - Engineer, head of a water chemistry laboratory.

s

= :y:::l =~-: EEE ..--.e. .:.v- . :. v....... ~. Kon%v,A.S. - Dirdefor'of ch6fhVr'Nu'dlear Power Station Department.

3 23

. Belyon'skoyo;N.I. _- E'ngineer in charge of foreign relations section.

r.:=.... [r 11epko,V.F... Director of: Metallurgy Department.- w :- @j ~ r=e 3: Melemed,M.M. - Scientist in Electron Microscope i.ob. (not formally introduced). g =. ,r

+ i (y ) m i i e

6. At the visit to the Gidropreekt Scientific Research Station named ofter S.W.Zhuk, on Feb.8,1973 Kirillov,Aleksandr Petrovich - Deputy Director of Reseo ch Station.

l Somorin,Vodim G. - Deputy Director for Administration. i." ~. Golutsey,Konstantin Zakhorovich., Director of Structural Design and Testing for APS. .. Engineer,, Ko.nevskii,. Mikhailov, - Engineer.. Arnberashvili, - Engineer

Gladkov,

. Prestressed. Concrete Specialist.

l., - - -3

Nikolaev,

-Thermal Stress Analyst - lr...

7. Izhoro Heavy Fabrication Plant named ofter Zhdanov.at.Kolpino,.on Feb.lo,1978..

Sobolev,Yurii Vassilievich - Chief Engineer, General Manager. Maslonok,Boris Arkadievich - Chief Designer of nuclear pressure components. l. Molutin,Evgenii Nikolaevich - Chief of inspection Department. Shvedkov,Voteril Vassilievich - Deputy Director of Gosgortekhrsodzor for North-West Region of USSR.

Tobosman,

- Chief of Inspection laboratory (non-destructive methods). =., -. = i t

8. of 1.eningrad Atomic Power Station, Sosnovyi Bor, on Feb.ll,1978.

Lukonin,Nikolai Fedorovich.. Director.. m_.,_ Epc'r',Anatolit Povlovich - Chief Engineer. - ..febov,Vladimir Ivanovich,. Deputy Chief, Engineer for Science..._,. Zinchenko,Nikolai Gavrilovich., Deputy Director _for Adtninistration. Bukin, Victor Ivanovich.- Senior Engineer. e

• M.

r; o o.e, w- ~ .s. 2. m. .a,_ m..

= -

'12. The following are people whom we did not meet on this trip but who hold significant positions in the Soviet nuclear safety structure. Director of Glavatomenergo - A. N. Grigoryants Director of Gosatomnadzor'- N. I. Kozlov

Deputy -Chairman of State Committee-

ee b

on Atomic Energy - A. G. Meshkov Deputy Minister of Health for - Radiation' Problem. - A'. I:. Burnazyan ~ ~Hinister :of HeaTth: :Acadeini'cian Pe'trdvskii Chief of Nuclear Branch of ii.. Gostekhnadzor - I. P. Alekseev I- ... ~... p ['. ((:'. ...p: t.u ~ - - ;;- 3 : - : :.- 1 : : :

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mmu a _ _. ; m _ _.4 N. u ~ L P. Appendix B ,F [ I. Technical Notes on Visit of NRC Delegation to the USSR ~ To Discuss Light Water Reactor Safety February 5-18, 1978 ,/ i=

• 1.

Introduction gl From February 5 to 18,1978, an NRC delegation visited the USSR for dis- .=..; cussions of light water reactor safety, and to explore topics of interest for ..;;;:.7;j future exchange if an agreement for LWR safety cooperation is achieved. T This Appendix summarizes the technical discussions held at the Ministry 9

=

of Power and Electrification, the Teploelectroproject Institute, the .5i5.... ' Kurchatov Institute, the Dzherzhinskiy Institute, the Gidroproject Institute, the Izhorsk Manufacturing plant, the Leningrad. Power Station, ..y s the Novovoronezh Power Station, and the Armenian Power Statio... E.;. 1 E. Section 2 provides a general discussio~n of the impressions of the NRC delegation regarding the roles of the several Soviet organizations involved 5 in the design, construction, operation and regulation of nuclear plants ~~"~~ .in the USSR. Sections 3 through 11 summarize technical infomation ~, obtained at each of the organizations and facilities visited. Attachment f=i i 1 provides an annotated list of documents obtained on the trip. i i 2. General Discussion E= EE==) In the Soviet Union, the design, construction and operation of a nuclear E=r5 power station involves complex interfaces between a number of institutes Wii and ministries, and the review and approval of a number of independent I government agencies. It was stated that as many as forty different agencies

• hii7.=g must approve a nuclear project before operation is permitted. The Ministry

=

of Power and Electrification (MPE) is responsible for the design, construc-tion and operation of nuclear and fossil-fired power plants in the USSR. MPE reports to the Council of Ministers. MPE initiates the design of nuclear p= power stations, to a large extent plays the role of an architect- !.i engineering fim in the U.S. in integrating the inputs of the various !E.L design organizations, guides the project through the needed reviews j=?:: and approvals and finally operates the plant. Although the responsibilities G. of MPE are broader than those of NRC, and although certain regulatory and E1=- - inspection ft ':tions are not their responsibility, it is clear to the NRC

== =

delegation tot MPE is the appropriate counterpart organization on the E@.( Soviet side for the purposes of an exchange agreement on light water

===f reactor safety. E=1 EEii iE W !=1 l 1 EE l r= r-l V:_=. w E=5 l E:E::: 2 . 7 g;. "

g =- = =.: b _z_ The need for a nuclear power plant is detemined by the Ministry of Powed h and Electrification. Regional growth patterns and the availability of alternate supplies of energy, such as fossil and hydroelectric, are considered. When it is decided that a particular region needs a si nuclear plant to supply its energy needs, the planning for the nuclear igEs plant is begun. A State Project Commission is appointed with the l=? responsibility for the entire project (from the time of initial planning E. through construction, until the plant is put in commercial operation). p2 The State Project Commission is responsible for getting the required rg = approvals of the various organizations and developing the various necessary documents, as will be discussed later. When the project is

==

in its early planning stages, various other governmental agencies are consul ted. For example, in the case of the Armenian Power Station (see ="i.i discussion in Section 11) in a high seismicity area, the Institute of Engineering Seismology of' the Soviet Academy of Science was involved early in the project in selecting the seismic design values for the site. L. g= As the design criteria, reactor type and site are selected, the actual [ _.. facility design is performed by a number of institutes for the Ministry of Power and Electrification.0ne 'of the largest of the institutes @+ is the All-Union State Design Institute "Teploelectroproject" (TED). Z. TEP reports to MEP, and appears to play a central role in the overall plant E design. Other institutes perform parts of the design; e.g., Gidroproject Institute does structural design and Kurchatov Insi.itute does core physics and themal-hydraulics dusign. j3 As the design develops, a set of design documents is prepared. These documents are made available to a variety of agencies for review and i approval. p. There are three independent agencies that are primarily responsible [E= for the State control and inspection of nuclear power plants for safety: E Gossannadzor (State Health Inspectorate), Gosstekhnadzor (State Technical f Inspectorate), and Gossatomnadzor (State Atomic Inspectorate). The State 1.. Health Inspectorate, under the Ministry of Health, is responsible ,P for radiation safety matters for nuclear plant:, as well as for sanitary, public health, and occupational safety matters as at any industrial facility. E.. The State Atomic Inspectorate has responsibility principally for criticality lEL safety and related matters, such as reactivity control systems, core design, f= and control of fissionable materials. The State Technical Inspectorate EF has review, approval and inspection responsibility for pressure vessels, EW5 primary system piping, mechanical handling equipment, fabrication, installa - EEi# tion, in-service inspections, quality assurance, etc. Apparently, both the EEE ~ Health Inspecto-ate and Technical Inspectorata assign resident inspectors =_ at each nuclear station, but the Atomic Inspectorate has'an inspector on EE= site only for the initial startup, testing of plant operators, reloads, ,Z.1 etc. " = = se ?=

:P

....p i= - 7 = The Atomic Inspectorate approves and authorizes the initial criticality of the core, not only from the point of view of the adequacy of the nuclear equipment at the plant, but also on the basis of the competency of the = , plant staff to perform the safety functions (analogous to the NRC opera. tor ~. = licensing function).*. Following initial operation of the facility,'there

=

5ppeirs to be only perf 6dic ' inspection of the facilities by,this : inspectorate. Thd $salth;andiTdchnical'Id5pedtdrites aie'hd5v'ily inv61vsd thro 6gF f ~ odt'the entf rd ' design,-donstrdctid6 'ind 6perdtion cfI hs:fadiliti. t Thess'inspectofs have the authority 'to require design changes of the: facility. E== They'have 'responsibilifi~f6p sett'ing : standards and various req'uf femd6ts

== - f6r: facility design which appiear to be similar to NRC Regulatory :Guidds, ~ ind :have responsibilities that are 'a mixture 'of both inspection - : - [":.=

== a6d'Tidensing fd66ti,6nsi' 1' i ' Q ~~ i i E Technical inspectors are assigned to manufacturing facilities which !.i.= supply plant components.. -They issue approvals for all project elements Used i 2 The ma,n construction :6fjth[e,[ plant beford,these -elements [are 0 sed.,,,,,, '( 51rif f ar in thdir:f 6t'5nt'y components is : governed by requir,emerits. - ~ -..,f nufact0 ping.of hsav t6 74SMC 'c'ddei)' which 'the 'in,spdctors use - h{:7 for certification. A copy of a particular requirements document was shown =- at one meeting. Based simply on its thickness, it does not appear to have F the same coverage as the ASME code, although it was asserted that this was, in fact, intended, b. Each of the.three -inspectorates is involved.with the plant from the':ti ne 6fIc6ndeptuil desig6 thr6ughout faciliti life. ' They fdraially apprdve g tiie initial siting of the facility, as well as a variety of other aspects ~ thecughout the construction of the plant. = TH6 involvement of ~ vari 6us other state ' agencies appears to.be similar' ~ in :s~ cope to the involvemsnt in the U.S. of the Dept. of Fisheries,- Dept. of Interior, EPA, etc. Through the Council of Ministers, the V.arious other' agencies 'can~ exert influence.to have a pr6fset cnariged isd. I dr 'mo~di fied :to -acc6mpTii6 la':pirt'idurar objectiv'e. For exaniple, therd.i' - ~ ~ wa5 cdnsicefible ~ dis 6dssf 6n :6f a :rigdirdMnti.~to :fnstalTcporids ifioms1 ' ';; -

==- ! "I'23. ndcleif "f acilities "f6 Mfdv;f dd fish 'Hitchs?iss 'for " ' " ~ ~ i=

• It' was statdd :that thd tiaminit' ion of : operators prior ton ne 'i-niti'il:

^'" t

&ftfcaTitfifs d6ns ?by 't66 IInspecidi, but' that 'sub'ieqds6t"6p'd?it'or ' ~ 3 ti F

==~ 'eisminiti'on's 'are 'ddn'e Ei"the Chief 'Enginee'r of the pl ant 'drgadizatidn" "i

s and certified 'by the Inspector.

=,4 2E,

EE:

+:: i2 t::. h?b' p 1.... .e:-== f".~EE

? w.- is.... -ye -d. -2... =. A. 3 ..} . _..: g.... = = =. .......;.7

== .g ^4. '?I m:: f5?.5k; 'developint 'i strains of fish. 'When the-need for a change in ~.._. design of "oject is stated by some agency outside of the =. ~.

• Ministry ot. swer and Electrification,' there is direct negoti--

66.?

ation.between:the -Ministry of Power and Electrification and the : .y ~~" other agency:to resol.ve:the issue. - If a resolution cannot be achieved e ;;.; at.that. level, it may be necessary to elevate the matter for resolu-tion. In such a case, the Council. of Ministers would be called on x... to+ resolve the issue;:although.it-appearsithat this step is seldom '7: ~ necessary:- Ailist was not 3provided of.a113the agencies 3that hav.e.

== :: to. approve:various. aspects.of a project to. reflect special interests,.. but. the ovetall-discussion:seemed*to indicate:about the :same:.breadtU ; U.S. to. achieve:a:simi.lar objective, The. Ministry of Power:and .....j and depth of federal.anOstate agencies as would.be involved ;in,the us, 2:1 Electrification.has the. responsibility.for assuring an adequate supply -...J of ' electricity. Their interest in keeping a project streamlined so 6=:2? that they can get it online quickly obviously may conflict with other L agencies which.do.not.have th,is direct. responsibility.. 3- : ::

==" .5::

.i

. -. 3 : ; m :+.. t-

3:.

The Ministry.of Power and El.ectrification *seems to be heading 3toward a form E: of standardization. The 440 MW.PWR' design of Units III:and-IV at Novovoronezh ~~"~ appears to be equivalent to the " product line" approach used by NSSS vendors in the:U.S-. and the ~1000 MW'PWR unit now under construction at Novovoronezh.seems ,s L to be intended as the prototype for a new product line. It' appears

a that the Soviets have an incentive for stendardization because of the il J desire to market their designs in other countries.

E= .) ..:i The-Soviet. Union: relies heavily on." district heating", that is, central

=

station heating plants-that supply hot water or steam to residential. E=.: ? and business buildings in their cities..,It was stated that 55-60% E" of all residential heating in the USSR is provided by district heating. lEgag Both Moscow and Leningrad:are 100% district heating. The central station r~~ plants are primarily' fired by gas or crude oil at present. Because of i '.h increasing concern for conservation'of fossil fuel resources and for $=:Q environmental problems withifossil fuels,;there is considerableiinterest E:. 1 in the potential:for:Using: nuclear. plants.for district heating. :It -i s !E I apparent that: some early designtwork.is:. underway' on-this: concept,: called " Atomic Boilers";; Although goedetails-were provided, PWR's are [.~.ll., considered to be most suitable. The Soviets stated that 25 to 30 km """ J is-about-the-maximum economic distance between the power station and the user. with substantial: heat: losses at that-distance;; This means, 3 in-effect,. metropolitan siting;:tbus-there i.s3 concern:over the t :- . difficulty of convincing the. health organizations of t.he safety and- - 4 reliability of nuclear.unitt for district heating. Tne general ......] approach now under study seems to be simple low thermal power 7::~.1 level, low pressure and temperature units to produce only heat and H no electricity. It is thought that such low performance units c,ould

==4 be made simple and reliable. .T;::U ". "2K t. .J

h Throughout the visit, it was apparent that there is a growing concern in the USSR for the quality of the environment. The use of cooling towers appeared widespread. The Armenian Power Station and part of the Novovo-ronezh Power Station had natural draft cooling towers. Control of the release of radioactive. effluents in normal operation and monitoring of the environmental effects seem to be receiving substantial emphasis by - designers. There al'~o appears to be considerable einphasis'within, other s government agencies-to' assure that efforts 'are made to minimize-e.nviron-mental impacts from nuclear po,wer statio_ns. !?=:: l :. 3... j. 3 3. Visit to fiinistry of' kower ahd Elbefrfficatloh! e [*9 in Moscow, February 6,1978- =k A'tf th'e initial'm'eeting at i;h'e Ministry!of Power;and Ele'ctrifi' Tat'i'oh (MPE) E ? 2 c .in Moscow, Mr. L. M. Voronin, Chief Engineer of the Directorate for Atomic

.=

St'a'tions, M'PE,' welcoine~ the NRC delegation and-introduced rep'rbsbn't'atives ~ d of many of the installations that the delegation would be visiting'. (See Appendix A). The principal subjects of discussion involved the roles b of the various organizations (summarized in Section 2 above), and the '= for the visit. The NRC. delegation listed some of the major. . itinerary' inte'res't,* ind' firi Voronin! rAsponded' by' Fin'd.icasing'WhTch2ihs'ta F - t'ophs of ~ lations could best addrbss' these topics. ' It' was i' dicated thatthe' N'RC' ~C' n g delegation would be accompanied throughout the trip by Mr. Y.- P. Karelin, ' :'~' Chief Specialist, Glavatomenergo, MPE, who is in charge of a small-staff group at MPE dealing with operational safety matters, and by Mr. Victor Myagkcv from the Novoyoronezh Power Station, who served as an inte' preter r for the vis'it. [ 4. Visit' t' Teploelectroproject Institute' ~ o in Moscow - February 6,1978 Th' NRC delegation was welcomed to the Teploelectroproject In'stitu't'e '(TEP) ~ ~ l e ~ by Mr. Vladimir N. Okhotin, Chief Engineer (See Apper. dix'A for other .c.on ta cts ).. .=:. 'T'he TEP In's't'itu te is the -largest single institute inthe Sov'iet U'n'io'n'. ~ 7 Ti'.r[epo'r.t's.tlo..'MPE, 'ah:d.is! ~r'esons3 b.1 e. 'far. thh Bes;ig'n ahd. d'eVeJo~pment oY ~ p .al.1 type's of' power s.tations: nuclear plants, fossil-fi're'd 'pl' ants and ~ . hydroelectric plants-TEP has designed approximately 80% of all th'e 6:. 3 ~ si', E! ~.. '

• i:

2:..., = =:J:f b!! h. L:: 'r: 2: 3 =::

p. --

-... _ ~. 7.-... -.- i.... =i!: E u !?,. power stations in operation within the. Soviet Union. They also have done design =H' work for plants exported to 29 other countries. TEP has about 12,000 employees. F" The institute is centralized, with its largest concentration of employees g.3...... located in Moscow. There are 12 other local divisions in various citiey F=- within the Soviet Union. The institute appears to perfonn the overaT1 L.:sE.; design work for power projects and apparent?y has complete.tesponsi-b:ili-ty for~ this (desig~ri., This could ' include transportation, damsi 15;. :... -~ reservoirs 'an'd dv'ed ths des'ign' an'd l'ayout of a town. to house people = in the general area where a facility would be built. TEP does not =. manufacture equipment; e.g., pressure ves.s.els,.and.tu.rhi.nes,. ate. ordered to specifications 'from "dquip~me'nt' ma'n'ufactur.ing pl a~nts.

i... =.

=.. ;;..:. The delegation had lengthy discussions at. TE.P r.egar. ding. design.p.hi.losopfties as~sociated Vith ~rda~c~ tor 's'af st'y. ~ ~ 'e 'new'est 1000-MWe PWPJ desiah' Moyovor'onezh i:E=:. Th Unit.Y)..was used-as a basis' 'for. thdse, di.scussions. '

".['?.'...."

f.Erig:-

• • a;

+y g2._ The design basis accident for the 1000 MW facility is an instantaneous ru'pture pi,. p of the largest pipe anywhere within the. plant. (800. m diameter)l... Three E=== independent. active systems feach sai =: accident' mitigation. : The rationa-le d ttr b.e 100".; capac.ity). !are. Usied:for for.three systems:is; :one.of.th'e. systems

=

may; fail: and' bnet m'ay be: out of ser'vice' 'f'o'r' one reason or another'.. ~ ~~;~ f# ~.~:. The basic design of the ECCS is apparently done by the Kurchatov Institute,.

1. 3' with TEP having responsibility for the design from the pressure boundary I

outward. 3 The general' philosophy appears to be that " active" systems should have IE a redundancy of three, whereas " passive" systems should have a redundancy i::. of two (for example, four 50". capacity accumulator tanks are used since E... ' this is a passive system -- two discharge into the vessel above the fllZ core and two into the downcomer.) The Soviets asserted that the three EI" ~ trains of the accident mitigating system.are completely. independent _includ-EE ing. separate.and independent electrical systems; component cooling; ' F= ~ lube oil, heat sinks, etc. The delegation did not see detailed drawings of.these systems; but for' one area of design where pump and hardware locations have been layed out, questiors were asked regarding the extent to L. which 5quipmsntias ' separate and indepe6 dent;in:rddundant trainsu.J.: Ef._.. The,respohse:was that'dvsry lattsmpt was mide tq1eep thm.trid5pedddat'. - lE ' ~ =..... fi::f':. x==.. r*"::~ l =. :~ .~I?a 4

p ?t was not clear to the delegation that in all cases a truly independent arrangement of systems is in fact achieved. The need for 3 independent systems was discussed in more detail with respect to the assumption that one of the systems f ails. Since separate nozzles are used for providing the ECCS cooling water to the reactor vessel, the failure of one of the lines leading to the vessel can cause an accident of sufficient 3 magnitude. that the ECCS would be required. Thus; a failure of one of the: systems would initiate the accident ~itself. The Soviet-design philosophy of assuminione of the systems to:be out of service for one: reason or inother appears toibe: equivalent to the U.S.. assumption-of a-single-failure, k= Qith the rembinder'of'the system being able to perform the function..

=

Other philosophical approache. used in the U.S., such as a loss of g offsite~ poker coincident with:the: accident,':are also assumed for-the; ; g p; Sovi t' design. p

.n.

e E

E The Soviet approach for the ECCS appears to be quite similar to the approach used by the Germans. Simultaneous top and bottom injection is used. As is the case.in the Gennan designs, the. coolant is.jntro - !=r duced:into' the reactor vessel ~ by direct injection:to the_ vessel..instead E== of-into-the: piping'systemsa Redundancy is'provi.ded.back: through; the 3 ; - 3- - high 'p'ressure' ~ systems,i including: heat-exchangers : diesel s,- etc3. Three high pressure injection systems are provided, primarily for small E= breaks. Thgse do not provide recirculation from the sump,. but fr.om. = th'ree 100 m capacity tanks. Three low pressure injection systems are provided with separate, independent storage tanks and heat exchangers. i These provide for recirculation from the sumps, and provide feedwater to the containment sprays. Three separate containment spray system.s are br'ovided to avoid interconnecting.the ECCS trains. The particular arrange-ment of ECCS was discussed in some detail, but there appear. to _be a number ~ of design features that are not yet resolved. For example, at present there is no cross-conr.ect between the high,)ressure and low pressure ECCS systems, but it was stated that such a connection is being. considered. The arrangement of the containment in the 1000 MW unit has some interest- -ing features. One.is that all of the ECCS equipment (both hi.gh. and, low p'r' essure pumps 'and their. hent exchangers), is located in. rooms immed.i.at:ely. _ ben'eath -th6 tontainment boundary.' T.he bottom of ithe.conta,if)mer)t itsel f is abo'ut ~12-metefs 16bove gradeilevel;; The esupply mf -water-i:s-taken-from sumps which generally are in the rooms immediately above the pump location and about 30 or 40 feet above the elevation of the pump itself. The overall space provided inside containment also seems to be more generous than in the containment designs used in tlie U.S. (See additional .= discussion of containment in Section 7). = i E.E [ N [41

:y

b r 8- [' The subje- . ire protection was explored in considerable detail. ~ The TEP * .aentatives said that as a design basis, the following scenarit assumed: (1) an assumed design basis LOCA, (2) a simul t, s loss of offsite power, and (3) a fire in the control room. , of these events-are considered to occur simultaneously,

.. =1 so P

2. separate. auxiliary control. room must be used to control

[h ' th* rt. The approach is to assume:that a LOCA signal used to: i n' ce actions normally going.through:the control. room and: be 'o.the:ECCS: system: occurs simultaneously with a signalithat:- p' to the.ECCS: equipment itself.. The design is such that:.the : ei- ,5, signal-to actuate the safety trains: takes precedence-- = . overrides any: effects.of. spurious actions.that would come., :

f. rom'a. postulated fire in the control room..No specific.infor -

3 mation was provided on how that design objective is accomplished. It may be that they have not yet worked out the details. The FF1 question was posed as to whether, if there were no LOCA, but simply a fire in the control room, all necessary functions could be.accomolished from the auxiliary control station. The somewhat-confusing response to that: question suggests.that this design.is

t.:

still.in.a.conceptua.l. stage..This subject warrants further. discussion in: future exchanges-to see' how the objective is accomplished;;. - ++ One fire protection criterion is to require the equivalent of a 1.5 hour fire barrier between redundant equipment, without credit for active suppression. The rationale is that one and a half hours would be tufficient. time to bring the fire under control and prevent redundant equipment from being damaged. The emphasis on fire protection is apparently aimed:at fires that can originate as a result of. overheating within cable trays... It:was stated that no combustibles are assumed present in the cable area. It is unclear whether exposure fires are considered. Automatic suppression systems using gas, foam and. water. are used.* p: Other design basis accidents are considered in the design of the 1000 MW facility, e.g., steam line rupture, loss of off-site power, and various transients f rod. withdrawal : etc.).. With regard to-specific requirements'

i::

-:.~i-- +:

3- -

-e-----e-----et--e

e 5 :.

..5- .. :5.e

• During the tour of Novovoronezh Units III and IV the delegation.was r_

permited to see. the. cable. spreading room..The cable. trays apeared. - lightly. loaded,iwith separation of redundant cables about: equivalent to

p

U.Sn practice'.- There

was no> evidence of. fire barriers: between. trays. i se

An automatically actuated foam: system was present (See discussion in Ef Section 10).

F S e -oo-..Ehl y

9-ll u h.. k .g. for environmental qualification of safety equipment, it was indicated that all equipment located within the containment must remain functional for relatively small or minor incidents for which the containment environ-ment might reach 90 C. For major pipe break accidents, the non-safety - 1 related equipment woulo be permitted to fail, but any equipment necesstry = to mitigate the accident is required to have been qualified te function in that environment. No details were available at the time of our visit. The accident radiation environment is assumed to be that corresponding' to a 10 percent core melt. The source term associated with that amount of melt is assumed present for qualification of equipment and is also used as a source terTn for containment leakage dose calculations. It was stated that the main steam line break accident is the limiting =: - accident f or setting the design strength cf containment, but that in the Soviet design the loss-of-coolant accident produces a larger containment tempera ture. The Soviets felt that their use of horizontal steam gener-ators probably accounts for the difference from U.S. calculations in this regard. There is no single document corresponding to the Safety Analysis Report

== in the U.S. Separate volumes (about twenty in number) are prepared to ' describe the different areas of design in detail, and there is one volume 5= that addresses safety matters explicitly. Each of the many (about 401) reviewing agencies receive all the volunes. Each may, if it desires, comment on any subject. The evaluation of each reviewing agency is sent to aR the others. Any changes in design resulting from the.se reviews are sent back to all agenciet The arbitrator of differences between y agencies is the State Committee for Conuruction, or if differences exist p between Ministries, the Council of Minist:ers (in principle, at least). }:::.:. 5. Visit to the Xurchatov Institute in i Moscow - February 7, 1978 [; The NRC dele;ction was w'elcomed to the Kurchatov Mstitute by,Dr. V. M derentoy, Director of the Department of Huclear Reactors. (See Appen-dix A for other conta:ts) furchatov Institute was the first nuclear center established in the USSR. The Institute reports to the State Comittee for Atonic Enercy. It was here, under the direction of u. Dr. Murchatov,that the first ruclear reactor in the USSR was constructed F and coerated in 1946. The Institute now employs about 6,000 people, g Dr. Siderenkov described the role of the Institute in nuclear power as -I being that of " scientific leader." It is involved in the development of initial design philosophy, follows up during the design of projects and a participates in the startup of initial prototypes. (.:.{ l i l l I N. =

..m. r p The institute includes the following departments: Nuclear Physics (which includes solid state and super conductivity), Molecular Physics, Plasma Physics (fusion work), Nuclear Reactors (primarily work on thermal reactor physics), and Test and Experimental, Reactors (including work ort structural .=i.. materi al s). n-' Th.e' Kurchatov Insti.tute. ' participates. ~in.the 'startup'.of all::thereacio,rs. E built.in the'11SSR'. .'It 1sl'apparently ~confs:1 der ~e'd as a ' par.t.of the. star. tup te[st' t.e[am.'. The. iinstit. ufe, has' 3 primaryMr.esponsib'i1ity foh lh'e c'or'e 'd'esign of 'all of the reactors in the USSR, hence' the relationsh'ip' to th'eir startup te_s ti ng rol e i s e.v_i d.ent. Thle inst'itu'te 'h'a's? 'b'e[e.nfr:es'pioIns'ible' f'or[ ~ des [ign of PWR reacto_rs, graphite 2, ~ ~ reactors, high temperature' gas. cool'ed reactors, fast breeder reactors. .. = (both of the liquid metal., type and gas cooled type), and for various experimental. reactors. The institute is, responsible for. the development of calculational m.ethods used' for; core de.si~gn:.: - T,hese, calchi atipng). methods incl ude. the physici;. ' and thermal-hyd' ablic' codes for steady-state and transient' processes. " p' r It is also responsible for the development of calculational procedures to evaluate various kinds of reactivi".y accidents. The institute has several operational computer codes which are used for the purpose of evaluating ECCS performance. Although they apparently do not have the responsibi,lity.for validating.the accuracy and adequacy of'these. ~ codef with research work, they'do have the codes operational at th5 insti-tuti and do run them. With regard to the steady-state calculational pro-cedures, the institute conducts experimental work to verify the correctness of the calculations. The Kurchatov Institute must formally and specifically approve a nuclear reactor facility before i.t is permitted to start up. Its representatives are'present at all _ meetings of;approvidg. organizations, and it plays.the, ro1520f an inspection organization at startups. There is some apparent duality [for each"of-the. reactors.of role,stnceithe institute:is.Hso. responsible for.the design In the development of the' cord design, J each of the important Elements of the design must conform to the various ~ regulatory crit 5ria evolied sithin 'the. Soviet government. The i nsti tdt'e',' ~ iri sddition,' participates in the developnerit'of the standards and s :.. regula. tory cri teria,tha.t,ar,e.used in _the. design. P The institute has the responsibility for evaluating the operating experience of the faciliti,es and factoring that experience back irito 'riew designs. This responsibility appears to be broad in scope and includes evaluating experience with n rmal operations, and ) repair and maintenance operations, as well as f.ilure data. 1 l 5 i.:: 1 1

3,x u _= ~ m i E+ p-easily. There are a large number of control rods for flux shaping around 5 a test position (25 are movable during operation). Twelve fuel channels j can be inserted or removed during operation. The reactor can operate at = loops. The. neutron flux level in the center E 40 MW, plus 10 MW in the tesg n/cm2-sec' and as high as 8 x 10 14 n/cm -sec in P! 2 of, the core is about 3 x 108 flux trap positions. In the present core conficjuration about 30 experi-

=,"

ment loops are in operation. Twelve are loops operating in PWR conditions -(300 C), one is at 800-1500.C. for gas-cooled reactor fuel tests and. .an'other. is being used 'fo'r' low' temperature tests w.ith. liquid. nitrogen,.. coo 1 ant.., ~.. ..... ~. s- .The MR reactor. is used. principally for tests of steady-state fuel per - --- = formance at' nominal ~op'erating conditions, but some transient tests are run .E; in. small loops, e.g.., tests of release of. radioactivity to the coolan.t- =:: -from. intentionally.faile~d' Yue'l ' elements'., Some tests have :been run with 3 ~ fuel irradiated to 80,000 MWD / ton bu'rnup' ~(UO2, zircalloy-clad fuel of the type used in the 440 MW PWR's). It was stated that they have seen no evidence of ' pellet-clad interactions or bambooing of the cladding. The t:1 adding wall thic.kness 1s.0.65 mm.. T w I he' press'ure' ve's'se'l Isteelise'd i~n' t'h'e '440 KJ PWR's is a Chrom'e-' Molybdenum- .-~ ' Vanadium alloy which has high stability at high temperatures. Reference was made to a paper at the last Geneva conference which gave the compo-g! E. sition (Paper #705). The copper content is about 0.23%. They believe that their steel is better than most used elsewhere in the world--better radiation resistance and temperature embrittlement behav.ior. For the L. rlew 1000 MW PWR's a modified steel alloy is being used with nickel added [

and vanadium reduced, for more strength.

The. nickel content worsens - radiation resistance, and they are doing experimental work to optimize ~ the properties. The actual compositions are proprietary. For the 1000 KW vessels there are no welds in the belt-line region. We later I learned at the Izhorsk plaiit that the central ring forging is 3.5 meters high with no longitudinal welds. The expected NDT shift in the belt-line

e region at the end of lif.e is about 60 C with essentially no change in the ij

. upper shelf hardness. (See also the discussions at the Izhorsk plant. E -in.Section 8). jf. p The-cielegation toured 'the MR:re' actor:and.the'first Soviet.readtdr.l The 5 .f rst reactor, a graphite pile reminiscent of CP-1, first'went critical M -in.1946, and is stil.1 operated-as a neutron calibration standard. Several sL ciiti. cal' facilities are;also. operated.in this. complex. .{E 6. Visit to Dzherzhinskiy Institute N.f. in. Moscow - February 7, 1978

T imm

= The Dzherzhinskiy Institute, also known as the All-Union Heat Engineering 8esearch and Development; Institute, reports to. the Ministry of Power and ""- l%. a.

n py:p ' QJ E._... ' i Elei:trification. It has about 2500 employees. Several daughter insti-h tutes are located throughout the Soviet Union. This institute is B: = responsible for a considerable amount. of R&D work on power generation

"

equipment. The institute operates a number of large boilers for the g=' development of conventional boiler designs. The turbine department Ei?= tests and helps to build turbines..There is also a metals research ~:1... department, a' water-chemistry. department (waste treatment.and decontam- [.;.;;: ination),.an1 automation.de - ::.~. fossil and. nuclear plants)partment (instrumentation.and controls for both. ,afuel. department.(fossil: fuel.only),a' ~~" 7 physical-technical. department (gas. dynamics.and heat exchangers).a. is c nuclear powei plant de artment and 'a'nucleaE' physics department (ridiation =~ control'and shielding)p* The work of the institute is directed largely 3=3., at operational problems.and. improvements for power, stations..For example, thsdnstitute.is. responsible for developing ~in-service inspsction.tsch-

== ni. ques Efor ' examining 'all: kinds of: components 'within ' nuclear :plirits. ~ : 2,. ..J.. 7 The. activities 'of' the su;rveillance laboratory 'were 'very impressive. This j lab designed a large~ shielded vessel with viewing windows and manipulators =E that can be. lowered inside a reactor pressure vessel for inspection and '~~ repairs '(0.S meter concrete : wall.with steel shell). This device was

=== 4 apparently developed ' originally for use in the removal of the thermal -55 shield in the Novovoronezh Unit I (See discussion.in.Section.10),.but.. _ ~

?=.._.

= .is'now intended'for use'for in-service ' inspections, and all new reacto'rs will have such a device available. =h ~ The surveillance 1ab is also developing acoustic emission devices for p installation on reactor primary system piping; remotely controlled ni magnetic crawler devices (" caterpillars") that crawl inside steam sep-arator drums and piping for:UT inspections; eddy current probe ' devices; and gama ray devices for internal radiographic inspections of nozzles k: and steam generators (" woodpeckers"). The lab also develops rigs for ?" remote measurement of thermal growth and movement of pipes, and noise analysis equipment. g Therewasabriefdiscussionoftworeactorcontainmentconceptsthal have been patented.in the U.S. by the Soviets [U.S. Patent 4056436].. One p!=i, is 'a conc'ept in 'which the Veactor compartment is vented through a wet M" condenser compartment, and then to an " air-trap" through check valves. It.was.sai.d.to be planned for.use.in several_ power stati_ons..The second concept ?Was a va'riatiorf Af.the ~ ice"coriddnsee desig'n usirig we't 'cbndensers

==3 instead of ice beds; No' details of these designs were discussed. ~ =:. y

• This would seem to infringe on a specific area of responsibility of the

}$[ State Comittee on Atomic Energy and its institutes.

• • This device has been patented in the U.S. by the Soviets.

n

,j !=..i.i b5

tp

• The institute performs resear:h on the transport of radiation within plants and research on criticelity safety to support the Atomic Inspectorate (Gossatomnadhzor).

It compiles documents on all aspects = of nuclear safety. M En ~ ' In a brief discussion of -the sin'gle failure criterfs, ft was st'it'e'd Ehat-single failures.are assumed for ' active ' components, but.thit !ther'e ire 'n'o' ~ finn req'uirement's' for ' passive compon'ents. Some difficult'y with the" inter-E pretation o'f what constitut'es' activi co'mpo'nenti wai 'acknowlid.'ge:d. kith. ~ regard to th'e us.e 4f ;qulintitativ'e reliab'ifity.or.l risk in;ily'se;s in.niakfn'g decisions on. design requirements, the Soviets stated that they do not-yet ~ hav.e sufficient statistical.information to Mevelop quantitative baies. ~ ~ for evaluating any of :th'e eq'uipment.in the. plant. The.designe'rs',..hoWever, l do use quantitative analyses in selecting be' tween various ' optionsin their designs, on a relative, basis.- No ; specific reliability goals.have been se.t G in their standards, but such goals were said to be borne in mind i'n the development of standards and criteria. The institute is collecting ~ I {g statistical information.,.but couldn' t predict when their standards ni ght.become more quantitative. In the discussion of the quantitatiive i appr;oach.to -reactor.safet_y design,' WASH-1400 was specif.fcally m'enti4ned I# ~ and Dr. Siderenkov indicated that it Vas' his personal 'opTnfon, 'althou'gh D:. he did not have quantitative information to back it up, that the actual probability of core melt accidents is lower than the number stated in WASH-1400. The design of the graphite-moderated, pressure tube reactors in the USSR was. discussed at various institutes. (See also Section 9 discussion.at 1.eningrad power station). At the Kurchatov. Institute it was' noted. that the capability for the online refueling, and the capability.to detect failed fuel elements in individual pressure tubes during operation, allows prompt removal of failed fuel without shutdown. Th'e pressure tube design also limits the maximum diameter of a postulated pipe failure. That design also provides a large source of cooling.. water in the feedwater system that can be used for an ECCS source, and the header system-for the pressure-tubes-makes.for a.less complicated situation in assuring reliable, 'distributiod.of emergency coooling -witer. .:... :: :+ :.- 4: ~.'.:: The: Test and: Experimental Reactors Depsrtment of 'ths ' institute his'iF Z program studying the properties of fuel elements for both PWR's'and ~- pressure-tube reactors and of pressure vessel materials. The program uses the MR reactor located at the institute. The MR reactor first went critical in 1964. This very versatile test reactor is a pool-En a type--(9' meter 1epth) with a graphite reflector, beryllium moderator. F blocks and the fuel in channels. Channels are also provided for experiment loops. The core is a one-meter cube. The core fuel ...c! I elements are. concentric plates of U-Al alloy c1ad with Al. Each fuel element generates about 2000 kW. The core array can be rearranged != N ::;;; =.

g. g.. . 7. Visit to the Scientific Research Station (named after S. Ya. Zhuk) of the Cidroproject Institute Tushino District of Moscow - February 8,1978 F The Gidroproject Institute (Hydro-Project) is responsible for the design E of hydro-electric power. stations in the USSR,.an'd.for research.and..... development on ' structures, It also assists TEP.on the design.'a6d'deyel' opment on structurds:for nucidar powef plants, bothithe'pfsssufe t0b..;. designs and :the PWR!s.. The.. Deputy Director.of.the. Station,:Di,. Alsxand6r. P. 'Kirillov,.chairsd the 'disdussions sith 'the ' delegation.' He;5psaks..'-- English. Ths principal subjects of discussion'at Gidr6pfoj5dt were: seismic design,. containment. design and pre-s, tressed : concrete pres'sure vessel.

.['%.,

O development. - ' ' '. '..g 3 The.first Soviet nuclear station built N a:high seismic ar a is.1the_$ : ~ f Afmenian Power Station near~Yerevan (See discussion of visit in Section'll). F~ ~ The seismic design criteria for this station were based on a Grade.IX intensity earthquake (on the MKS scale -. essentially the same as Modified E3 Mercalli). Gidroproject developed the design frequency spectr6m:2.said k to.be a " synthetic.spectr6m". based on-a collsetion of data for the.' region b (msxim0m peak'sdc61erstion vslue.0.8 ; static Asl0 'O.2g).~ ThrEeldime6-F 9 ~ 'sional models were built and tested. The models simulated the masses of i equipment and the rigidity of pipes and reactor components. To account. for scaling factors, the materials of the model were selected, vafying properties such as ductility, volume weight, and modulus of elasticity. The materials selection for proper scaling. was checked by some materials testing at several scales up to full scale. The scale model.of the. Armenian plants 'was tested dynamically, msasuring frequency,' amplitude; sdcelerations and stresses. ~ j At the reactor station on the Kola Peninsula where there is an' operating station similar in design to the Armenian reactors, explosives were set off.in the excavation pit.for.the second unit to simulate earthquaks ground motion. Amplitude displacements, stress levels, and accelerations were measured on components and structures of the;first unit for which con-stpuction was essentially complete.. Th5 res0lts were compared with;dalcula- ~ tio6s and with the results of the scale model tests. The results agreed ~ of ths steam generator supp6rts. ~ ~ '~ k to_within about.15L s.The 1argest. discrepancies concerned;the. response [E. Ths.i6stitute.has a shake. table dapable.of testincj comoonents andlm6dels dp:to :100 tons srid.6;x'6 : miters in siie. The shake table ~is used for f.. tests 'of electrical 'eciuipment and control systems for the calc 61ated F spectrum at their location in the plant. The equipment in a typical nuclear plant is divided into four. seismic categories. The situation seems similar ~ to that in the U.S. for various classifications of teoth safety and non- ~ safety equipment. Category 1, safety-related equipment, is any. equipment needed to control the release of radioactive materials within the plant, g. A dynamic analysis of all such equipment is required. i'i U..... [55h

., = = = = .. =.. - - = - - - -.. g.:: The development of seismic design bases for nuclear facility designs was outlined. The Gidroproject Institute has its own seismology department that conducts geologic investigations to select the intensity grade (MKS) for ~= the facility site and the appropriate spectrum and g-values. The Soviet Academy of Sciences is responsible for evaluating.the seismicity. of al.1 EE=- regions of the country and the co1~1ection of. seismic data.. The Academy );;E', prepares charts and maps..showi.ng earthq'uake intensity prob.abiliti.es. gr - that.are used.by the ins.titute. ...~..- [::. ~ ~ f6r' d'es'ign 'pu'r;iose.s', ;two e'arth'q'uakes ar'e[co[ns'idered, a T in 100. y'ea*r. ;

• 3se earthquake :( apparently.a'nalogous to the 11.5. operating basis " earthquake)....

5:1 and a 1 in 1.0,000 y. ear ear.thquake. for which there should be no failure ~ ~ ~ Z.:.7 of the primary pressur~e boundary a'nd no loss of capability for s'afe' sh'utdown and residual' heat removal (analogous to the U.S, safe shutdown T.;l. g, carthquake).* .g.. Once a site is selected the Gidroproject Institute conducts site investi-f gatf or.s (micro-seismicity, location of faults, etc.) and develops a site-l:. spec'ific design spectrum.1.n consul.tation with the Academy of Sciences.. - The : Academy of Science's.has respo~nsibility for the final approval 'on the adequacy of..th'e.' analysis',' and the'. geologic :investi.gati.ons are conducted in 'conlunction ~ witih personn'el 'from 'th'e Academy 'of Science. The Academy may rely ~on - ~ investigations by the institute or they may conduct completely h=ll'l independent investigations if they choose.

r With regard to proximity to known faults, it was stated that they would.

k not approve construction of a facility on an existing fault, but there did b not appear to be criteria.for specific permissible distances from f.aul.ts. i It was stated that the 'Arhenian Power Station is located between two ~ faults at distances of 2 kilometers and 5 kilometers from the station. (Note discussion of this topic at the Armenian Station in Section 11, which characterizes the faults differently.) Since there is good solid E rock foundation between the faults, surface displacement is not con-j... sidered in the design. [ i4 Wi.th.r.egard to stress criteria, for the smaller (1 in 100 year) earthq'uake, ' b

s. tresses are limited to c. ode.al.lowables ( their codes).

For the.1, i 10.,000. year e.ar.thquake,. pi pes and_ equi.p. ment :shoul d not crack' ~or..los,n. {= ~ e;.:' functionabil.ity, but..may indergo p1'astic deformation. Structures may' crack if the nece'ssary leak-tight integrity is maintained. It is assumed that the plant may be.. unusable after the.lar.ge earthquake..Ea rthquak.e.. ari.a.ccident 31arge's.t p'irie. b.reak);1oads are. combined,. but it was no.t !="- d clear how they are combined.. Gidroproject Institute provides only the ' s seismic loads; others (apparently TEP) take into account the combinations. E: be

• In response to a question, Dr. Kirillov stated that for hydro dams for f<

which a large population may be at risk, the 1 in 10,000 year earthquake [= is also used as a design basis. (( ix lE:"-

~ -. 7-f i l - The first Soviet pre-stressed concrete containment building is being =' built for the 1000 MWe PWR, Novovoronezh Unit V. The dry containment is 45 meters internal diameter and 80 meters high. The cylindrical walls z.. are 1.2 meters thick and the dome is 80 cm thick. There is a steel liner. E. As noted previously, the ground floor of the containment is not within the M.' leak-tight barrier, but consists of.12-meter-high compartments-for pumps M and other* equipment.' The' design basis' accident for the containment is a break.of the: largest pipe. -The design pressure is 4.6 atmospheres ove -r pressure and the design temperature is 150 C. The internal compartments are not pre-stressed. - The)Gidroproject Ihstitute-designed the contsin-E ment structures itsel.f and 'ph'rformedrexperiments'en a 1/5-scale'inodel.i g The subcompartment design is by TEP, but it was stated that.their. design 7" is based on: dynamic' calculations of-pressilre and temperature versus time for: design' basis'eventsu : 'i ~ ? it was noted that, because buttresses in pre-stressed concrete containments 9: introduce high stress concentrations, the Soviet designs use diagonal f cables ( spiraled 180'). Each cable has 1000 ton capacity. This has simplified construction of the containments. Greased cables are- ~ used -- no grouting. Cable. loads are measured periodically. At Novovoronezh-E Unit V, since it is;the: first. of;a~ kind;' frequent measurements will' be taken~ for at least the first year. Strain gages on'the dome and walls will be monitored continuously. = The Gidroproject is developing a pre-stressed concrete pressure vessel for use in the reactor under development for district heating (See also discussion in Section 2). They have studied a Swedish ( ASEA) design for a pre-stressed concrete pressure vessel for a 900 MWe BWR and believe [_ they have improved upon it. The Soviet design employs a specially developed ceramic insulating liner (blocks), which is under full radial compression ~ loading in the pre-stressed design. g In the tour, the NRC team saw the shake table and numerous instrumented concrete models. .u 8. ' Visit.to the Izhorsk Manufacturing ."'...iPl antiNear' Leningrad ' : February '10,1978' ,y-- The' Soviet hosts at the Izhorsk Plant were headed by the kting Director General, Mr..Yuri Sobelev. The Izhorsk Plant was founded in 1721'by-Peter E the Great, as a : shipbuilding ' plant, 'and has always been a statelcsnsd I? i ndu stry. 'It now reports ito the Ministry ~of Power Machinery 'It.hasibeen in I= operation for 257 years, including throughout the Leningrad siege of 'World War II,y at which time the German lines were about 1 km away. Over 5,000 plant workers . :s, were killed during the siege. The plant now manufactures principally

l heavy equipment for power plants; reactor vessels, steam generator shells, 4.. o E

4 8 l y !!E 3)

....y. ,=

.a.

.y m.

. _u l}

ir ~ I i f pressurizers, steam drums, pump casings. It also manufactures hydraulic-rod drive mechanisms. The plant is unusual in that it mills its own steel in the facility and does extensive metallurgical development, as s well as the fabrication of equipment. g F It was stated that the. plant has the capacity to produce 5 to:81000-MWe pressure vessels:per year (both' pressure tube and PWR types). The plant does not have access to waterways-suitable:for shipment of large+ pressure vessels. Thus the size limitations (dimensions; not weight);of. rail... shipments do pose: difficulties. :If. vessels. larger.than-1000-MWe-are to be-built,.other shipping means'will.have to be found. 3 7 The. head of the: Quality' Acceptanch organization atdhe plant is-appointed direct- ~ ly' by.the Ministry 4of Power Machinery. The Deputy Head of the Technical Inspectorate (Gosstekhnadzor) for the northwest region of Russia is resident at this plant. - i-All of the R&D work for the vessel materials is performed at research facilities within the plant. The'. plant isiresponsible'not:only.for the" manufacturing of tpressure yesselij -but also for doing detailed design work on these components. The overall design parameters are established by another institute (TEP) and the final e detailed design is produced at Izhorsk. The one exception where considerable E overall design, as well as fundamental research and testing, is done is that associated with control rod drive mechanisms. These mechanisms are designed, manufactured and tested at this facility. Ei. The reactor vessels currently ~ being designed in the USSR are manufactured-5 so that there are no welds in the belt-line region of the reactor vessel. This is accomplished by forging cylindrical sections for which the largest i section is 3-1/2 nuters long and made from a 180-ton billet. The nozzles in the reactor vessels and pressurizer vessels are pressed out of the billet during forging and no welds are required in the nozzle itself. The facility appears to be well run and of a relatively modern vintage. = The vessel steel is. manufactured on. site using.either an electric arc vacuum furnace or the ' electro-slag technique.9 The plant. has extensive facilities for radiographic inspections (including linear accelerator ~ d betatron), and has large metallurgical R&D f acilities. an ~

t' m

Standards for chemical composition of pressure vessehsteels are: set:by the. Technical Inspectorate.- The copper content for steels that: do not + - pi contain nickel ih the alloy is 0.2%. For the newer steels ( for the 1000-MWe E= PWR) that contain nickel in the alloy, the copper content is held in the

3 range 0.1 to 0.2% -- except that the cylindrical sections in the belt-T, line region of-the reactor vessel are from specially selected batches of

+

steel in which the copper is held to 0.05%. lii] l

== xa - ..-z._._.._. . _r _ r.c y. i ??? 7

i..

g;;:~ : The plant performs a 100% baseline inspection of all vessels after fab- = rication, including 100% UT of base metal, and UT, X-ray, PT and magnetic particle testing of all welds.

..f E.

Control rod drive housings and mechanisms for PWR's are designed ard N fabricated at Izhorsk. They also perform short cold and hot tests.of p=7jgt all drives and life; test all prototypes. The drives,are of the rack and g;... pini6n type'. A:br6chure'was provided. that describes-the' mechanism.: ff' d 1 ~.

=. =::. e g -.y

z

..r::,

D ' ' ' " + ' ~ - 9." Visit to LeningradiPower' Station' i i'i M - ~ " - - - ' F6b~ruary 11,'1978i M 'i' =.=" 5=== 'rhe Leningrad ~ Power Station:it on tthe' Bay:of' Finl&nd about' two: hours" drive' '+: - TjiT from: Leningrad,'near: the' toen of'Sosnovyi Bor:(popularion:about 40;000K ~~ The: station 'has two'1000-MWe graphite-moderated, pressure tube,' direct: I :e': cycis' boiling water reactors. Unit 1 went on line in December 1973, and EM Unit 2 in July 1975. In 1977 the plant generated 12.4 billion kilowatt p hours at a capacity factor of 0.71. 9= ~ +~ E(5:. Each reactor has two turbine generators with common auxiliary ' equipment 2 ih+ a common. hall. ~ Thbre ars 1600 pressore' t0bes:per reactor' and.179 : 2:* :. control channels. The fuel rods are conventional type', uranium-oxide' E enriched to an average of 1.8 percent and clad in zircalloy tubes. The reactor is cooled with'8 circulating water pumps, 6 of which are required : - N to achieve full power. The water is heated to steam in the core and g separated in external steam drums. The steam from the drums is directed to the' turbine generators. The system is ' essentially a once-through sys-h: _ tem in which water is separated in the steam drums, so there is no inter-l= mediate system. 'The graphite moderator is: cooled by nitrogen and hbl.iumi The turbine generator for the facility (3000 rpm) has one high pressure, and four low pressure, stages. There are four separate condensers per turbine. Full flow treatment is used for the return condensate-to the i pl ant ~. The condensers are cooled by sea water. The reactor is operated f ~ at 70 atmospheres steam pressure and 284 C with about a 0.1% carry-over E _ factor; The st~eam"genbrating capacity'is'about 5800 ton's' of'ste~a~ rpbr. hour. E m t 2 g Thbre is. a' total'of~12:MWs diesel;gsnerhting; capacity f6r the: standbya ~ ' poker system','d6' rived'from: 3 diesels',~ 6ach 6f, which is' rited: ati 2p HWe. g;?.'.. d The reactors are refueled on line. Apparently about 2-3 fuel assemblies F pe' ' day hrs re~ Wcedi Ehch: individual ~ press 0re tube can: be:mohitbred.for .=:3 3 - r ~ p fuel failures by a:ghnma: ray scintillation monitor which can be cbnhe ted to

7.~ '

c any of the' pressure tubes at the exit pipe upstream of the steam' drum. The monitoring for the leak detection is not continuous for any tube beca0se there EE..g:,,

==..

^

7-" Wp y _.:Y. e 3h) j

5: 5::. - l E [... - f V::. are only a few counters. Operation is pemitted with 0.1% of the fuel W i assemblies failed (leaking). It was stated that the plant could operate ~' 1 with 1% failed fuel without radiological problems for workers. To date, . since startup of the station _ there have been 35 cases where fuel assemblies i:5 have been removed because one or more fuel rods had leakage. They recently i= =. built a hot-cell at the station and are beginning to examine these 35-

== - assemblies to determine causes of failures. =E7

== The water chemistry for the plant is controlled at a pH of 7.2, with a conduc-tivity 0.1 micromho per centimeter. The chloride content is less than 4 H micrograms / liter, hardness less than 0.5, and the oxygen content is less

=== ; than 5 micrograms / liter. The primary piping is partly stainless steel and T-~i: partly clad with stainless steel. 51. These reactors do not have conventional containment in the U.S. sense. Rather, there are a variety of sub-compartments which are designed to withstand pressures of 4-5 atmospheres. The compartments are connected to a long corridor through check valves, so that if a pipe break occurs in one of the compartments the steam would be exhausted through the check valves into the corridor and thence into a special condensing =E=;.. building next to the reactor building with a spray system. The condensate 7" would be collected and pumped back into the coolant loop. The plant _5 is designed so that the largest pipe break in any one of these compartments i=: is considered the design basis. In the event of a LOCA, the initial cooling would be by natural circulation. Then a compressed gas system drives water from tanks into each of 44 collector intake manifolds (22 on each side of the reactor) each of which serves several pressure tubes. Finally regular cooling water is pumped from a 400 m3 storage tank. It was stated that pipe whip is taken into account in design. Main s [g.i coolant pumps are in individual compartments (8). Each ECC pump is in a separate compartment with independent power sources and separate Cables. "2 During the plant tour the NRC team noted that none of the turbines was shiel ded. It was stated that the contact dose at the high pressure stage =4 q of the turbine casing is about 0.8 prem/sec (about 3 mR/hr) and that the 1 average plant worker exposure is about 0.8R per year. No direct reading ..... 9 or indicating radiation monitors were in evidence. Apparently the shif t E size is fairly high, a minimum of 80 employees per shift for the two-

.;;;; 1 unit station.

===t

[... The condenser tubes are copper-nickel alloy with a 2 rm wall thickness. There have been several tube failures, but overall perfomance was stated 5, to be satisfactory. The tube sheets are carbon steel covered with an

"~.::-,

epoxy. In the event of sea water ingress, it would be handled by the l full-flow treatment. If ingress exceeds the capacity of the treatment

I

l system, power would be reduced by about 50 to 100 MW, the leaking condenser isolated and the tubes plugged. This can be done on-line since there = =, are four condensers per turbine.

1 5:;= l l

== 1

It ' ' u p L

• ~

b p. The team was impressed witji ti.e cleanliness and general evidence of good management of the station. The Soviets stated that Unit 1 had operated continuously for a two-year period without shutdown. 5....

=.. '

.r: p.L_ 10. Visit'to the Novoyoronezh Poser:Stationi ~i i E! L'F +' ~ ~Februari:15,1978 E5 The NovoVoronezh ;PowdF'Ststion-is located'sboQt 40 kilom tiers-from ' : ':M ..e the dity oflVoroneih ( popoldtI6n'920,000);'near2thE'6Ewl c6nstisct6d' town e (pFf 6cipilly for stition;sork6fs)'of Novovoroneih.' T66'ststio6 site sd5

1. i=

seiscted. in 1957 ;bec505e of'its.locati6n 'o6 ?th6 Don :Rivef!with! eff: sand : ~~ ' i6fl and essentialli'6oiigricsiture. It was originally to have been

5).

a fossil-fired station, but later it was decided to build a nuclear =l :;3 s ta t. i. o.6 2. ; ;. ' ' ". _' i l ~~i Vi re ii. ^ [... ~gm p The station has four operating PWR units and a new 1000 MWe fifth E" unit under construction. The basic characteristics of the units are bived:in' Tables 1 ind 2. The co6tainment building'for Unit lV'is i' W up:almost to the dome, and the pressure: vessel is-in place (but littisi alie:of'the primarjisistsm). 'The'Sovieti'expset plint 5tartupii6:~ ti 7iti late 1978 (1). The NRC team did not tour Unit V. ~ Unit'I (210 MWe) was begun'in 1957 and went into operation in 1964. ~ Unit II (365 MWe) started up in 1969. These were the first two demonstration PWR-type reactors in the USSR. Improvements were made i in each successive unit and Units III and IV are apparently the proto-tipes for'the Soviet 440 MWe: product line which'has been built else-where (e.g., Armenian station) and exported to Finland (Louisa station). 1.p Capital costs have decreased with each unit. The cost was 326 rubles is per installed kilowatt for Unit I and is down to an estimated 199.6 ~ rubles per installed kilowatt for Unit V (estimated in 1976). It was noted that the cost of labor has not changed significantly over i.5 t[1e last 15. years.;, ,,, } i _ (;, - f' 1 The: capacity fadt6rsifoF hdh'of the'06iti,ars: posted thP6 ugh 60t th ?'* O p1A6tiiapparenti :to initilliemplopee' interest toid6 whate9bfithe id:' 9 cin' to'iri1pr69e 'th6t6p6rati6g' record?ThE capacitp factor'fof laiti ~ _.J iear,1977, for~ all four 6niti sas said to be 0.79.- It was ~also stated lE ' j that 06it'Il operated for a 3-year period with no shutdown except (E= - for refueling. A typical refueling (remove 1/3 of core and, shuffle = .f611:ls idc6mplished%ithini25/30 days and is'icheduliad hnnuillp"i :- EEE i ThA ~ capacity factor q0otsd includes the varying output of the plant-Er 66ca6se'of: changes in load demand, ev,en though the unit was ivailhbis EE; for most of the timb to generate at full capacity. The operating * - ' Es, experience with' fuel failure at the plant has been'very good, with~ '== 9 no outage resulting because of fuel failure; the coolant activity - s =1 av6raghs About'10W c'0 ries 'per liter for the gross acti91t Eachi6f T:;.' ths fuel ass mblies is checked during a refueling outage (both those +.., ...=; ?..*.

m....

+ 1 1..~. i ' Il I Table 1 U f :.rr ; Basic Characteristics of f Novovoronezh Nuclear Power Units. I-IV r a

c:

I tem Unit I Unit II Units III & IV . =... [fM: liiiiiiiii ~' Initial Operation 1964 '~ ~ 1969' 1971 & 1972 " " = 210: 365.+ e : ' E =. =-- : El ect.ri.c.6utpot,: MW.. :. .n: :- 3:. -.. . each.440

g,

. z. - 74.g.: Thennal o:utput..of ieactdr,~ ;MW. _ t t,-.. .=. 760 .1320. ... each 1375 m.- -..=; ...y.. gt. Numb N 6N tdrbogenerators 3 5 each 2 bi ~ g=.- Turbine plant rating,'MW. 70. 73 ] ' ~ 220

1. }

- +.: +. 1 : m:

+

e

.'5 =

c...

m Saturated steam pressure ~ ~ 29 30 ~ 44 ?=l5... upstream of turbine stop (412.5 psi) (426.7' psi) (625.8 psi) = valves, kgf/cm li:: ~ p Coolant flow through the core, 36,500 48,000 40,000

• F m 3./ h..

g _. .(160,706 gpm) (311,399 gpm), j]76,116 gpm) g{=:' Primary water pressure, bar 100 105 125 [.. (1450 psi) (1523 psi) (1813 psi) B r-Average inlet water temperature. 252 252 267 J J j::. C' (486 F) (486 F) (513 F) sr " b

----=

7 i ::::: :

- di:-

.,,....2.. ,... =..- ....e 2, Averig6 c6olint Sedting~in !!.. ' ~ ' ' 19.'T. : * '  : '.2 5:8 ~ 30 ..'.5 nuclear core, C ~ ' ' (34.4 F)~ (46.4 F) '~..'.(54 F) C

=

~.. - . :. :.:: ~:

• i.-

l'"ll~ I 5 li:~ Maxim 0m.n0c16ar.fdel.edrichment,' %: 2.~ ~3',:. 3.6. t== ....a.. 1:. ~

=

b=. = Average fuel burnup, MW-day /t 13,000 28,000 %40,000

== = E.j .r. Producti6n cost," Koriecs/ksiir. 1 0.'75 ' 0.65 ~ (1.4(/kw-hr) (1.1 & /kw-br) 94 & /kw-br) .(0 = =., .mi Ef ficiency (gross), % 27 28 32

== 1 .==j --=mm

w..ai = ...z... =... :_._:. . =. . =, ...=:. i .i

==:

I!

=.

ll. [i

[EF. -

=:: :r

$f. : Table 2 Mff..:, Basic Characteristics of

1. ff Novoyoronezh Unit Y g+

== Reactor capacity, MW: electric 1000 " ~ ~ ~ ~ thermal 3000

f......

=::.- :.. .Turbogenerators 2 x 500 MW ... = - Main circulating pump 19,000 (83,655 gpm) b-3 capacity, m /h 2E(,_ Steam generator capacity, t/h 1500 Primary Loop Pressure, Atm. 160 (2320 psi) =. Steam Pressure at Stop Valves, Atm. 60 (870 psi) O... Number of circulation loops 4 [" ,f Fuel burnup, MW-day /t 40,000 Production cost, kopecs/kW-hr 0.5 (0.7 f,/kW/hr) L im Efficiency, % 33 [ E Station needs, % 5.3 f5 l =....., [5!.'E }....-. E..I.E O 1y a illl !.iy i:'.: h..k

..a.

{=5 j: 1

• * ~..{

b ' b that are removed and those that remain) for any leakage (dry and wet sipping). It was stated that these inspections are primarily to obtain ~.s statistical data and that only a few instances of leakers have been ci observed, primarily in fuel exposed for three years. J y

• "* :.';.";;.l The fabrication of the reactor vessels for the units differ in l55h detail. Unit I has a stainless steel-lined reactor vessel,

!EE! E whereas Units II, III and IV have no-liner material on the carbon steel which has been exposed fui'Use-past several years. In the

==r unlined vessels some very. minor. pitting.corrosicn was observed early EF in the operation of thd'udif,:hdt]dow'a'll'of the vessels are covered with an oxide film that provides #otsctfon of the carbon steel. ~~. All of the new 1000 MWe units will be designed with a stainless steel- .. s lined. vessel..even.though.no serious corrosion problems have been Mid observdd " .g.l =1 The design baAes for Unit V appear to be similar, in te'rms of safety _;.:= philosophy, redundancy requirements, etc., to large PWRs being built in the U.S. f There.are some specific requirements not yet in final fom 'for 'which compTete information was not available at th'e site.

== For exam would tie.ple, the,NRC team.was unable to learn what leak rate. limit ~E re' quired ifpf. the ' containment. ~ Units I through..IV..do _not.have containments in the U.S. sense. In s: Units 'I and TI, th'e~ pr*imafy 'sy' stem is located within several inner ~ compartments of thick-wall, reinforced concrete. The compartments are designed for 3 atm. overpressure and are interconnecte'd through check valve vents.. A. dome.over the top of the pressure vessel is I=s also designed for 3' a'tm. overpressure.' 'The compartments are lined ha with stainless steel...Their ticJhtness was checked by pulling a vacuum and measuring' in-leakage'.' There seem to be no specific leak =, rate requirements. For Units III and IV, all the primary system is v. within one compartment designed for an overpressure of 2 atm. Ei;; 5 The team did not obtain sp~ecific infomation on the emergency core E:' cooling. systems for Units I to IV. The statement was mado that E early ~desi~gn's 'di'd not consider a large pipe break. For th~e"new' Unit'Y,' i;t was stated that for pipe breaks with break flows

......-=,

of 300 m 3/hr, or less, primary pressure could be maintained. For larger breaks (800 nm is diameter of largest pipe) pressure falls ] and ECCS is needed. There are three 100% capacity low pressure injec- .....g tion systems - separated and independent. The precise meaning of I""" :::l 100% capacity was not clear. The design basis seems to be prevention of overheating of the fuel, but no specific acceptance criteria were 5 stated (although the figure of 1200 C maximun temperature was r':ferred EEEE to in passing). The low pressure ECCS is injected into the tor of ~ the reactor vessel, the bottom (through the downcomer), and into coolant pipes, all through special nozzles. There is apparently no control of the flow split. If the US-USSR exchange agreement is obtained, further detailed discussion of ECCS design, particularly for the 1000 MWe units, would be desirable. h=!" issi C=. : q

.g. ll g, C Some of the Soviet criteria documents seen by the team indicated that ~ two independent reactivity shutdown systems should be provided (preferably of diverse design). After questioning the intent of this criterion, it became apparent that,.in. practice, the.two independent systems r.. _ consist of (1) a rod systsmf which;is capable of shutting',down the [=.. ~ r6 actor under transient:and accident conditions, and (2) a boron iDjection. system. ;in the. older. units, the. boron injection. system

=

app 6ars to.be the31ow-acting. type similar'.to' systems presently;used in thb ' United State 5.. 'A comment.was made.however, that'in.the "... ._== moderh designs.a. " fast.* boron

• injection system". will be used! ' A' '

.. m characterization of the new system was.that.the boron would be. =* capable of shutting.thE. reactor.down'in Meyeral. tens of secohds. " ' i Tiie degree of separation of control and safety circuits in cabling systems was discussed. It was indicated that a separation, of control and safety circuits completely back to the individual sensors was required. While visiting the units the team was permitted G.. to go into the cable. spreading' room for Unit IV. We noticed a very = light 1,oad of cables ~everywhere, which. suggested that, if complete . =.. Independence of conXol:and: safety were required, considerably more "~~ control' cables 5hould be~ evident 16 the cable spreading area. The cable spreading room was clean and free of combustibles, and was.kept locked. There appeared to be about six or seven horizontal trays stacked about 6 inches apart vertically. No fire retardant coatings were noticeable. The room was equipped with an automatically il-actuated foam suppression system. The criterion is that the room should [. fill with foam in ten minutes. There is one distribution ring p for:the foam, fed by three,:1007, capacity pumps. [.: It was stated that all cable tray areas and transformer areas have p:: firs suppression systems. There is a special fire fighting station lE J on the site, and shift crews are trained for fire brigades. (ll. 5 It'was stated that the new Unit V would have a separated control p station.for shutdown arld: residual. heat Temoval..in the everit of ' (= fire, and that such a feature might eventually be retrofit on = the older units. - i ii, -;f. ,i- -is 3.i a: F Et the Novovoronezh ' station, ~s'ignals'from~ radiation monitors 'alilover

E-the station are. fed to.a, central. dosimetry' room.with recorders and

=- al a rms...The r6oni;is.continuodsly. manned. There appear to.'be.few, [.lf[. i f any.,.1ocal Ty. indicating. monitors f ri the pl ant - only alann lights.

E.:"~

tripped from the ' central ' room.

== ?.!i- = 32 y. "= ..n i: 5::. ___ma ::;,

m_. m o -_ e h(. .: ^ g i The water chemistry for each of the units is controlled somewhat I di f ferently. The major difference is that the pH level varies from a value of 7 in the Unit I vessel to values of 8 to 9 in Units II, III

9 and IV, which are unclad steel.

Unit I has no boric acid system. The ii parameters on the water chemistry for 'the secondary, side are.as follows: ' r.... = chlorides.0.01 milligrams.per liter,' salts 0.003 milligrams per:li.ter, -~ oxygen 0.015 mill.igrams per liter, and a pH of.8. =.... a-Durinsi the 'tou6 df the.'shatidrl, the ' team had 'an oppoNu~nity id.'l'ook. at the spent. fuel. rack arrangement.in-the Unit.III spent fuel-pool. The pool:was.origirially designed.to be filled with spent; fuel. Rather 59 thari providing a more densely packe'd fuel rack. arrangement to, increase 55.- capacity, they-have chosen.toibuild a second layer of. storage racks above g-the ' bundles that are already present in the pool. The second layer for fuel f.E;s{ storage h,as not.been.used yet _but is. installed in the pool. .A comment was made,that they.are thinking of the possibility of building. some : dry storage '~ facilties for storage of fuel away from the reactor. The availability of onsite power for each of the units was discussed bVi efly. For Unit,1, three die.sel generators are provided, wi.th - iE: - two ou,t of three bei.ng re, quired f.or accide.n.t si.tuations. vIrt Unit +

== II, four diesel generators are provided, and three out of four

s:

are required for accidents. For Units III and IV, three diesels ~= are located in each of the units, with either one of three er two of E': thr'ee being required for the diesel. ( Answer was not clear). i Units III and IV were said to have three completely independent diesels. The diesels are completely independent from the ac power distribution capability, and..from the de bat.tery supplies for starting the diesels and supplying.dc -battery services elsewhere in th'e f acility. There are no interconnections between the three diesels at each of the units, and no interconnections between the three buses; although apparently, each bus feeds both units. The statement was made that only one of the emergency buses was required .....= a to provide sufficient protection for the facility. ]. In;. Units III and IV., the_73 co.ntrol-rods.( fuel-follower type). are ~ arranged in twelve. groups.:.There are three levels of scram pro-v.14ed in the prp,tection system (a'utomatic and manual). Level 3 ..etg - scrams two rod groups. Level 2 scrams each rod group sequen-tipl.ly (apparently with opportunity for the operator to interrupt E the sequence).. Level.1 scrams all rods. - Because these were lead ~ Z L._ They[ts: pf' the.440; M'We; design,1.arge' shutdown margins were prov.ided fif uni . normally control on boron-concentration with rods fully out except ' El for 'one' 6-rod group. partially in. Unit IV has 1*. excess k, cold with @fl = ik s N .. i

.~..~'"

l..% " '

m.. _m.= _ m. .y i+ . r all rods in at beginning of core life. Cold shutdown requires 12% boron with all rods out. Insertion of sixteen rods is required to reach hot shutdown. It was said that they can achieve cold shutdown without boron addition after two to three months of operation. It was noted that the Armenian station has fewer rods (37) and less shutdown margin. .c .+, ?i m.. The 1000 MWe Unit V will:have twelve nests of control rods - not of the 4-fuel-follower type. The fuel rods will be in cans with no cross-flow. -

=. _

3 t The most 'significant: operating' problem that-has ' occurred at+~ :::', N6vovoronezh was:the failureiof:a' thermal shield in: Unit I in.1969;re- ~= iftsr five'y6ars of' operation.: The shield came' loose-and was "bounciog" du ' to' fl ow. The failure'was discovered by the noise. :The: removal n:,+ of the shield t60k aboutione year. :. The difficulty was that thetsbield ^.3 -

=

was' attached to the~ vessel inside the downcomer region and.could:not : b iremov6d'withost cutting;it'into pieces. The shielded device :-

6 described in Section 6 was built and used for this repair.

The shield ~ was removed and not replaced. Analyses showed it to be unnecessary, and L were thickened). ~ h thermal shields were not.put. in the 1ater units. ( although. the. downcomers ~ = -4

r : - -

.:.r. Once' again' the NRC~ team' was impressed with the cleanliness and general good housekeeping and management of this station. f:: 11. Visit to Armenian Power Station near Yerevan, h Armenia - February 13, 1978 ~ ~ The Armenian Power Station has two 440 MWe PWR units similar in ~ ' design' to the Novo'voronezh Units III and IV. Construction began in 1971, and the first unit achieved criticality in December 1976. The second unit is still under construction and expected to be on-line in 1979. The principal interest of the NRC team in this station 'r~esults from the fact 'that this station is the tnly Soviet nuclear station in a high seismicity area. -The Armenian' power ' grid exp~ orts power to the Europea i part -of-the h[l USSR' thro'u'gh the':Ge'orgia'n 'gr.id...Former1.y.most of.the power in !A'dden'ia' was"obta'indd from hydroel ecri'c -dams.- Shen add 1 tional power E 'was needed, the difficulty of transporting crude oil to this remote l? ' region -( altitude about 1800 ' meters) made nuclear a pr.eferred ' choice. .Un't t 'I 'f.s not :baie' loaded.. It : achieved. full power operation in. : 3-- ' 'No'vember '1977,'liut soms' testing is apparently still going on. Ei=' =1. I 5:.

__=._ -m s. __._..s.. o _ ..If ,, I ) i From the outset it was recognized that the high seismic activity would be a problem in design. The region is characterized by Grade VIII i on the MKS intensity scale. Extensive site investigations were performed, and historical records back to the 5 th Century A.D. wbre: kn.; i studied. The area is rich in history and old structures. A cathedral b iiear the station'( the seati of the Armenian Catholic' Church)- datbsM 7+ [# bac' to the: 3rd Centuiya aid The: Academy; of Engineering ~ : Ssismbi699 - i, k of the Armenian Academy of Sciences, was heavily involved in site = investi~ atibns andin: settin~gl designFparambters.. : The plant.wa,s,,, g designed for a' Gr&de IX MKSiintensity~barthquaks. 'In' contr'a'st to. =.E statements made: at'Gidroproject ( see: section 7), the peoplet at. ~ ; ': ?: the site said th' t'the two features near the: site' we're noti"se'i~smic 4"' a f aul ts"' but Were-su~rfac~e " wrinkles". ' Another; "small; fault I no tF i '- E. seismic" was said~ to be:10 km'away; but they; had not detectsd.any; eviden~ce of movem6nt from' examination: of'100-200' meter. deb'p bore

1. =

holes. No age data seemed to be known to the people we spoke to. h. The basement foundation under the site is basalt which had been covered by volcanic. lava and then another layer of basalt.' The ~ site was ~ excavated down to the second basalt layer ( about -22.5 meters elevation), the lava removed, and replaced with concrete.

== .The lowest point of~ the reactor building ~ foundation (beneath the - = _. reactor vessel) is at elevation of -10 meters resting on the g concrete fill. The center of the reactor core is about -1.8 meters !i (grade level is "0"). There have been three earthquakes in the region since 1977. The most .recent (January 3,1978) had its epicenter in Georgia (Grade VII) and produced Grade IV intensity at the reactor site. The other two, a with epicenters in Turkey and Iran, also produced Grade IV intensity at the site. These earthquakes resulted in no problems with equipment b. at the power station. The facility is equipped with extensive seismic instrumentation and complete records were obtained of the earthquakes that have occurred. 'There are:92 accelerometers ~1ocated on equipment throughout k the plant and a seismograph is located on the site. Some seismic research facilities are also located at the Armenian Power Station. pr'ee' categ~ories. of: systhm's~are.s'pecif1'ed 'in: the design': ? Ca.tbgory 1 - @[: th'e ' primary co~ol~ ant: system and reacto'r building structures;' Cat'egbry 2 - the cranes, auxiliary building and systems; and Category 3 - the E==, turbine plant. iCatbgbry 1. was'designedito the most stringent criteria != and the other categories to less stringent criteria. E==g '~ "iil-: ..] b 1 y .1". khh

Effort was made in plant layout to keep major safety-related components ~ at the lowest possible elevations. All switchgear ( relay cabinets and motor control centers) are located on the ground floor. The Gontrol Room, however, is at the 9.5 meter elevation (above grade). All equipment was said to be. tested for seismic resistance (by ful_l. u.y= scale or model tests);.this. includes control instrumentation, electronic H: controllers, equipment. mounts and connections, pumps, valves, motors, etc.- Some of th6se tests 'were:done at.Gidroproject,' othsis at vafious ~ EE9 manuf.actur.ing.; plants :and institutes. jg.. Te The.resctor vessel. fs r.igidly held in 5 : support system tied to the i!.:. foundation. An agnu.l.ar '.shiel d ' tank 'around.the vessel, water-filled ~Z:.... In other designs,.was _:replac.ed.with a dr_y. shield (material not.speci- ':?i. fied). The reactor internals ars 'said '.to have special restfaint devi.ces to' prevent.v.ertical and rotational movement. The reactor ~ vessel head has special screwjacks to prevent tilting and rotation. 7-Fuel assemblies were tested for seismic loads at the manufacturing plant, but no special. reinforcement was found to be needed. There is ~~ widespread use of hydraul.ic :(oil) snubbers. TN5 i'drizontdl s' teamdendrdtd/sare' suspen'did 'on straps ( witn ' vertical h spring snubbers) and have horizontal snubbers ( two degrees of freedom). ~ The reactor has a s'eismic scram circuit, with some readouts in the' control room. It is apparently set now at about the Grade VIII intensity level,.but may Lc changed as experience is.obtained. The ' subject of seismic design, and particularly the data available from the Armenian site studies, should be an important subject for future, more detailed exchanges. =.: Fl ~ ...k. ~. U:. -t i: - . :.i s ; +.::. i; .33: E ~~

==

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E:

ATTACHENT 1 iG:--:. ~, ~ ~ t: List' of Doc'unien'ts &taine'd on ^ . Visit to USSR. - February 1978 ~ iiii:i: 3.:-. .c

.:.u:

Copies, cf. the fol. lowing documents and brochures are available from 25,. F.. Schroedsr, DSS. ] ~~ . ~ '.' ' ~ ~

1. Brochure entitied. Teol~oelectrooroieht institute.

Describes the

== ~~. activities' of TEP - Written about 1962 - in English. !T' t;. 2. Booklet entitled Works of Gidroproject. A collection of 23 short Y==:, technical. papers, published in 1975 in Russian. 3.. Paper entitled.."Devel.opment of the Nuclear Power Industry in the: USSR," .:)i= by L. M. Voronin, E. P. Karelin, et al. Reprint from Nuclear Power and i: 5+ Its Fuel Cycle, IAEA, Vienna 1977 - in Russian with English abstract. 4. Paper entitled "On the Soviet-American Seminar on Designing and I Construction of Large Dams in Seismic Areas" by A. P. Kirillov. g. Prepared for International Commission oh Large Dams, Salzurg, Austria i= .. _ September 14-16, 1977 - in English. i=- 5. Brochure entitled.Novovoronezh Nuclear Power Station - in English. = =... g 6. Brochure entitled Drive Mechanism of Control and Protection System of ~ Water-Moderated Water-Cooled Power Reactor (440 MWe) - in English.

== 7. " Rules for Nuclear Safety of Atomic Power Station," 1976 ( Appr cved by Gossatomnadzor December 13,1974). Informal translation by J. Le>'in, ORNL. Eu 8. Book entitled Atomic Electric Power Stations by L. M. Voronin, 1977 - E8=" in Russian ( Appears to be a collection of papers). Lu....; 9. Book - History of the Izhorsk P1 ant - in Russian. .1

== 9 EEN -a ~......:. l =iEm

m

?=: R i il

===

=- i ie= H

r

(:: i F/: l = i List of Documents Available from n Joseoh Lewin, ORNL i E"......... ; i .'.5. ~ '~ 1. Pamphlet entitled Electric Power System of Armenian SSR. Illustrated brochure.of. power insta}}ations; and power grid in Armenia. ~ ~'- -- '~

- 2,,;

Book _ entitled Problems of Design and Operation of Atomic Power 1.. $tations'.. Proceedin~ s of the All-Union ~ Heat Engineering ~ ' Institute, =E o g Issue No.11, headed by A. S. Kon'kova, et al. Moscow " Energy"

===' Publishing House,1977. Under translation at ORNL. 3.- Bo'ok' e~nti.tidd.' Problem's4f-Desion and-6p'eration of %t'oitifd-MWer Stations. Proceedings of the All-Union Heat Engineering Institute, E Issue No. 2, Moscow " Energy" Publishing House,1974. Four. articles from 'this book.are being translat,ed.at ORNL.. h.. = ..j =

4.. Book. entitled.The Control and Safety of. Nuclear Power Reactors.,

I. Ya. Emel '.ya'nov. Moscow Atomic Publishing House,1975. ~This.- = is a personal copy belonging to Mr. Lewin. ~ 5. Book entitled The Electrical Sections of Power Stations. Edited by S. V. Usov. Energy Press, Leningrad, 1977. Personal copy

3

. purchased by J. Lewin; available for anyone interested. [. f:::= 6. Brochure entitled The Beloyarsk Atomic Power Station. Published in Moscow 1973. Extensive description of two super heating reactors and one LMFBR in the Ural Mountains. In possession of J. Lewin from previous trip. 7 = ~ . !=P ^ .. =. E.. _ - ; :3-3- n.;. R i

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,.~ . -.. - ~. p l g: - Appendix C =:. PEDTOCOL Ei! 1 ,} on the results of the visit of Anotican specialists hjjj~ t:: :.. on nuclear power station reliability and safety

• j to the U.S.S.E. on Februa.ry 5--18, 1978 43.

In accordAnce with the protocol of the 4th session of

.u.. ;

I the U'.S.-U.S.S.B. Joint Con =ittee en Pe,aceful Uses of Atenic ~ " ' EnerEy that was signed in Terevan in Dece=ber of 1976 and =n. later co=:runications, including the letters from I.ir. Allen 3. Gwenburg of the U.E Enbassy in Eoscow to N.A. Lopatin, Deputy Minister of Power and Electrification (13'E) on October 31, 1977, W and fron L.M. Voronin, Chief Engineer of the Main Ao-ini stration for Atenic. Power Stations of-EFE to Mr. Ernst Volgenau of the k' U.S. Nuclear ReEu1atory Co:inission on December 26, 1977, an b ~ Anerican delegation of specialista visited the Soviet Union during the period frc= 7eb. 3 through 18th 1978. The purpose of the visit was faniliarization with the experience of the U.S.S.R. Lyi. in assuring reliability and safety cf nuclear power staticns E:!' during design, construction and operation, and the holding o. negotiations on the possibilities for z:utually beneficial coope-t1 ration in this area. ,l: Be American delegation was headed by Victor Stello, Direc-E_ ter, Division of Operating Eeactors, and Joseph D. La?leur, Jr., Deputy Director, Office of International Programs, both of IGC, yn and the Soviet delegation was headed by L.1!. Voronin, Chief Engi * [ neer, Glavatonenergo, Ministry of Power and Electrification of E: the U.S.S.E.. Lists of the members of each dele 5ation that took h part in the discusssions are appended. Se itinerary of the ~ visit of the U.S. delegation in the U.S.S.R. is also appended. [... Se 1:erican group of specialists conducted negotiations g... at the l'ini stry of Power and Electrification of the U.S.S.E. [ i j and in the course of their so,1ourn in the U.S.S.E. visited the 8g..;;. 7

= '

• Se to:n " reliability and safety" is used here to include EE:

the followings design philosophy and c:iteria; related safety re-h? searcht engineering calculatiens; quality assurance and control Ef aspects, and construction and operation of equdpsent needed to f,.,;.,. assure safety of nuclear power statiens with respect to the pub-E::... lie health and envirennent. $IE ' r. 7::: e

[ p::. ~2~ ~;.:. I F: Novoveronezh, I,eningrad and. Armenian nuclear power. stations, i.t:: The Institute of Ato=ic Energy naned after I.V.Kurchatov,

• ~

the "Teploelectropreekt"' Institute, thd All-Union,Eeat Engineer-ing Institute naned after P.2.D er-k4 W y, the "Gidropreekt" In-stitute, as well as the I: hora Plant of the t'iM.stry of Power l Machisery;;to-faniliht'ind~thinselves with the organization of wort is reliability and safety of nuclear powei'. stations;at;all stages of 'their creation: and: operation. 21 - :: n - ' ' In the ' course of the d.iscussions the ~ specialists of both sides noted-that probless of reliability and safety ~of ndcledt i power'stStions are of basic significance for the development ' of nuclear power and agreed that cooperation in this field be-tween ' specialists cf the U.S.S.R. and the U.S. A. -is. appropriate [:. l and =r.atually beneficial and nust be crganized*as soon as possible after the-retu:n visit by a delegiv.cn of Soviet specialists to the U.S. A. in L' arch - April 1978. In the opinion of the experts of the two sides, cooperation can be effected in thd following areas:

1. Exchange of te

• 4 cal infernation, including standards and nc:=s that define requirenents for equipnent, nue-

~ lear systens and nuclear power stations with PWR units ~ as' a whole, fren the point of view of ensu:ing reliabi - '~ lity and safety of operatien and environnental prdtection; ~ reviews of basic technical decisiens that dete.~ine reliability and safety of nuclear power stations.

2. Holding of deint seninars and sy=posia on current prob-

~ , lens in reliability and safety of nuclear power stations with p772 units that are cf nutual interest. ~~ ;' '3. -periodic exchanges of -delegatiens of specialists to ':;tudy 2 the achieverients :of toth -oountries in providing for re-it m liabilitylaid sdfety of 'ri:Ic' lear power stations! wit $ - FWR units. - l "" a_erperts of both sides agreed that the topics and final fo:ns of -cooperation-can-be~ finalized with precisica sad'corre-lated after;the return visit to the U.S. A. by the ' delegatich of '- Soviet specialists in L' arch - April 1978. i .=

• r F

Y: i L: i

,g .. :.=.=.a - -

. ::. ~:... -.-

=.= -. = = :. -..; e - - l. . ) _ "... l !:i:. E l S.., i J

=

i i En =, l ~' 'In~tlie course 'of-the: dis ~cussions held it was "secoi;nized l 2 that in each-countryi spec'ially in the area ~of-inspections'ibegg-lations'and standards-and safety research, certain infornation ;'- wEic'h'is inportant t6'-this-c6 operation, is held inither'agedeies

.? E" _

t'han-NRC~and MPE.'Within'tEis cooperation,'each side wil17 assist [, the 'other in obtair.ing -such information fro: these other agencies ~~~ 2 i and wil1 assure that these-other agencies are represented, as appropriate, in the sy=posia, seninars and visits of delegations of~ specialists.' '~ ~ ~ ~ ' - +'; To assist each side in understanding the activities and iG functional concepts of the other side, the U.S. delegation pro-h)',;;. posed that an exchange of -the follori.ng docunents abould occur: E

1. U.S.' Docunents to -be sent to EFS

~ 7(1) -Code of-7dderal Eegulations of NEC (10 CFE) h ~ ~;

• 2

([f. (includes " General Design Criteria") } (2) NEO Regulato.-y Guides fer Reactors (3) Standard Review Plan for Nuclear Pewer Plants (4) A Co.plete Final Safety Ar#1 ais Repor: (?SAE) 7 of a large 758 f (3) Atomic Energy Act of 1934 [;. (6) Energy Eeorganization Act cf 1974 (7) National Envirennental Policy Act of 1969 l (8) Inder cf Light ~ater Reactor Safety Research Activities

3. U.S.S.E. Docunents to be sent to NEO:

~ ~ (1) General Reactor Safety Hegulations k (2) Regulations for fechnical Safety h,p ~ (3) Regulatien for Radiation Safety (SanitarfIsspe[ction' ... Pan @ etsf.,,,,,,, (4) RegulatTdin5 fSi Ec'd-Criticality,, _, ,,,,..~ I Safetf~~ l (3) Design Materials on Safety of 1000 MT3 PWR Unit T ,,,,, '-l(6) ~Governi.ent Decree establishing responsijilit$es] ((.(( ' ~ '. [ ', of NPS jafety inspection agencies ' ' ' _ ' ', ',. ' ~ ~ ' ~(7) Inder cf Light-Water Eeacter Safety Research ~~~ .....=. Activities. .-.....1 5 :~::^ i

=r-

) l =..: ! l N?l ' .::: W

~ u . ~. en Te , E2r ~ fb-p.- ne Soviet side' agreed to consider the above proposals g"e re I." and respond by Earch 15. 1978. ~;

.- B e-U.S.. delegation presented to the U.S.S.Ry side a; revised draft of the " Discussion Points" S ven,ty NRC,durin6sthe Sird i

Meeting. cf-the -U.S.-U.S.S.R. Joint Coccittee on Peaceful Uses,, 3 .=. of itor.ic Energy, in Washington in December 1975. no Soviet, En side.a6:eed.to discuss this draft when the Soviet. delegation.;,. mske their. rets-a visit to the U.S. A. j ji: f ,];, 21s, protocol was irritten on 17 February,1978 in Moscow::.: [~[E in Russian and English, in 2 copies, each of which is fully valid. =:: For the U.S.S.R. dele 5ation For the U.S. dele 6ation = ':5: = = :.. /AN" / k L.M. Voronin ~ V. Ste h Jr.l J.'D.LaFlbur,'dr. ~ Arpendices: 1 - List of members of U.S. dele 6ation 2 - List of nembers of U.S.S.R. delegation 3 - Program of sodourn in the U.S.S.R. of U.S. dele-gation of erperts in the field of safety of nuclea'r power stations j l5:.- =.

• ! ! 2.. *.

e .e ~ h '::=.'. = [][85.:: $L ~~ {b-:. 20'.. ..f5' !5E l. = i 'lL'.'". -Q::., . = =. .--.1L-.-- -

...u..- :-. ... w. ..--...a-.,-e w..-..~ 2. u- = J b II. pent 1x 1 LIST OF n'te OF U S. DEISGATION. r .:...:.. -. e r::::st.; 12.::

c..

1.' Yictor. Ste113 .. Dia ctor... Division. oi Ope ratin g. Be actors, ; NEC li:.i. . 1:. :..:... b.q-i.

2. Joseph D Lafleur,J.::. - Deputy Director,.01fice of ',,ternati,onal

~~~ i p,ng,ag, gga ... : a = w ~. s 3 ;.L.S. Tong : ;. ..~.insistant Director for. Later Esiactor. Safety Research, SEC ~ p:. .4. 3o;rce H.Grier - Director, SEC I=spection an.d Er.forcement, t.;. ~ Re gion.1

5. Pr.u* Seleoedr:r

- OePet7

• inctor. Divisio2r c f Hea: tor Systens Safety, SEC 6; Joseph Iewir.

- Oak Riv!4;e I:ational' Laborator;', Nuclear .~ ._In_ri__n_e. r. re 7.nt_e Rre.t.e_r - '7 1.S ' G:wnbe tt; .- Scient;e Cour t elor, 'U.S.Enbass),' Moscow ~, f...

8. Jack L.G:nnell

- S:iet;e Officer, U.S. E= bassy, Moscow t e 1 4 4 4.,.. i

t. :

f5. -l I . y: r:.. i lu. i h 5' l':.' [" j J ?'.. p.

f a

==::: i 5_.. " [" Appendix 2 LIST CF EMSER3 OF U.S.S.R. DELEGATION [T = =..

===

Leader, Chief En6 neer, %in 144 ni stration E""'

1. L.M.Voronin 1

for Euclear Power Stations, Ministry of Power and Elect:-ification

i=...

~: :--- Eieci'tive hecret'a'ry.; Sost'et'Pii-tf of"tW U.3.s

2. V.N. Milt'e'ev--

U.S.S.R. Joint Com=ittee on EnerEy ..-. - ~ - "... '.: ; r + r -'. : ~.. = = - j 3:. E.P.Iarel'in.., -- *:. Chief. Specialist,1.'ain Adninistration for

.E.T..:

7 '.] Nuclear Power Stations i I

4. V.E.Troahin 7

Senior Consultant, Portign Relations-Dpt.;,-

=.

Einistry of Power and ElectTification g'].. -: = =

5. _V.'A.Sido;ynto Director, NPS Division,.In chttor: Institute

!!EE of Nuclear Energy ]"[ ~ ~ ~

6. V.3.Doroshchuk Director, D:er-H W Eeat En61reerin6.

Institute

7. A.M.Bukrinsky Chief of Laboratory, D:e:-Huky Eeat I:si-neerirs Institute.

t m-f ..-f , ~. :-. - r Chief 1*gineer, Institute "Teploelektro-pi:E==

8. V.N.Chhotin proekt" t

=n :-- Dy. Chief >4eer, "Teploelektreproekt" =E

9. V.P.Tatmikov Directer, Research Division, Institute

10. A.P.Zirillov "Hydropro j e ct"

.,, ;;=- y ".:=::

11. Y.I.Eononov Dy. Chief, HPS Safety Inspection Dpt.,

Go s go rte chnadsor,U. S.S.R. ,Q;{,. i r x-- Chief, Eis Safety Inspectien, Gossannadsor, inn-

12. Y.D.Tarovnky U.S.S.R.

Interpreter

13. V.N.Mingkov r.,.

t::. ::=:: il:{

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- 6.02 78. .10 00 Discussions.at the Ministry af Power.and... [:6 ' 'Mdnday " - ~, Eleetrificatio:i of.th.e.;U.SSH" =. [ 15 00 Visit to the Institute "Teploelektroproekt"

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7.02 78 10 00 Visit to 'the Zurchatov Institute iof Tuclear [:ih =. . Tu_esday,, '15 00 Visit to the D:er-Waky Institute for Heat " [', Energy v = eri=g I is.. 8.02 78 10.00 Visit to the Institute "r~.ydroproject" ( 23 55 14 ave for Ie***r ad != =. Wednesday ...e, . r. -. [ v frrive in' Leningrad ~ " ~ - " 'I! 9 02 78- ~ ~~~B.25 h da7 14.'00 Sightseeing E i -L.* }i:

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--~~.*z 10.02 78 10.00 Visit to the Izhora Factory p day h .- -15 00 Free tine 11.02.78 8'.00 Leave for the Leningrad Nuclear Power Station ~ SahW 12.00 Visit to the Leningrad Ruclear Power Station 12.02 78 11 45 Leave fo'r Terevan 8"2d87 16.00 Arrive in Terevan '13 02 78-.. 11.00 Visit to the Ir:enian Nuclear Power Ststi6n-M*nday ...17 05 Leave for Moscow, flight 898 19 45 Arrive in Moscow 14 02 78 14.00 Discussions at the Ministry of Power and ~ Tuesday Electrificatien of the USSR 22 40 Leave for the Novevorone:h Nuclear Power Station. [ 15.02 78 9.08 Arrive in Novoverone:h E Wednesday 10.20 Arrive at the Novovorone:h Nuclear Power Station li v:: 11.00 Visit to the Novovorone:h Euclear Power Station r 22.17 Leave for Moscow, train No.15 ff 16 02.78 9 00 Arrive in Moscow h sday 14.00 Meeting at the 1"M stry of Power and Electri-52 fication. Discussion of the draft protocol =. 17'.02l 78 16.00 Final discussions. Sig=ing of the protocol. E Priday

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18.02.78 14.00 Leave for the USA Saturday l55."~ = t =n s"q:: .?.

p --.m._- m._. .l 'l l j IIPOTOKDE. gg.. o pe.'syaraTaz,snanTa a CCCP. Iezeranan enesa:EcTom Ci:IA no sanez-i:9 ~ II ASC a nepson c 5 no'I8 fe's~pa n 1978 r. fj:} accTa a desonacsocTn l....'* p.:-: u

-3.c~oorserenza e upoToxcaos 4-ro sacenasan ConMecTao2 coser-cxo-axepaxancaon xoxacezz no unpsexy menossownm aTouson asep-ran?'riodxcanHuM s Epe'saHe"B 'AeKadpe 1976.~r.!'E IanHetme2.nepe.

Al ~l nucxon, sxxovarae2 nacsua.Es HoconeTsa C2A.s Mocuse oT.r-x'a An.

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sena J.Tpnadepra na nun. H. A.IonaTnHa - sauecTzTen MazacTpa esep-refEKHE 3MeKTp2@HEa@H CCCP (Musasepro CCCP), oT 3I exTndpn. I977 r., a Tane or r:assoro nEzeHepa TZasH0ro ynpas3enE noEaToM- ~ = HEM saerpocTamanM Masanepro CCCP 2.M.BoponHa r-sy SpacTy. Boareso as Kouncenn no snepsouy perymposaEnn C2A oT. 26 sexadpa [? 1977 r., Aezeracan auepzzaserar enesanacros a nepnon c 5.02 no I8.02.I978 r. noceTzza CoseTexaft Cora c nenD.o3EaRoMenK.'C. oG-Tou CCCP 'no odecnevenio.aaseznoen a desonnenocTE A3C 3 uponec. ~ ce npoeKTEposaHER, cTpoETenena E. SKeniyaTana E.nposeRes2K.ne- .g. perosopos o sosuozsocTEI saanunnre:noro ccTpyAEn50cna a BTo2 . odancTm. AMepzxasexyn Ieneranno scarcas:ssa Eznop CTeuo - Inpenop.. ouera exenayaTapyexuz peanopos EPC, a Azose@ A. Iscrep' ma:=n2 - aaueenTen sapexTopa onena'sez ynapomrA nporpas EPC, coser-cxyo 'neseranno - r.ip.M nazesep TzasaTexanepro Masanepro CCCP I.M.BopoEnH. CEcKE UBBoB odenI neMernm#, upnEE2CnX yRacTZe 3 decerax, npzzaranics. UpzzaraeTcs Tane nporpaMMa npeduzanna Aeaeranz a CCCP. Reseranas cuenaa::2cTos CIA nposera neperosopu a Maassepro CCCP's so speus nuanTa noceTzza Hososoposezczyo,.IennHrpaacxyn. ~ ' ' ' a Apuxsexyn A30, HacTzTyT aTouno2.aseprnz EM..H.B.KypsaTosa, za-cTzTyTu."Tenzoarenponpoen",, BeecomM Ten:oTeIHzseen2 EEcTZ-I ' fyT:.zu.:01.9.Asepznnenoroc "TanpoupoexT", a Tarze HzopcKn2 sasos.,;. Manaseprena a e nenm ossarouseEEE C opraH23ane2,'padot -no.-odeC=., - ne9tHED HaAezHocTE E de3onacHocTs A30 na scez cTanaxx az coana ' [.:."... HER E. 3. RCn.VBTanaB. 1B Ione nposereEEuz dece; cuenaaracTu od.eEI cTopoE _oTMeTn.:;2_, ?!E~~ s I) Tep.:2H "sanezaocn E'de30'nacHocn " 32Ecs sEZU9ae5~cEe'ZfD*: lee: 15[.. Ronnennnn n KpnTepna no npoexTzposaHzm; coorseTonym ae zc-R czenosanns no desonacsocTz; EEZeHepse pacWE"'u; sonpocU odec-neseHER E RoETpoAR RavecTsa. 8 Tane E3roTonIBEZR 2 BKennyat-Tanna odopynosang, ocecneusao::lero desonacacen A3C I:s ox-r=r - pyran::a2. cpe u a naceaenza. .=:. i f.':.: 7 p'::. ..._y I (:9 l'.:.. t

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3. Hepzornsecxze saamatus oduenH ABAeranZEMZ cuen2aIEcTos.

21: no E3yveEED noenEeHEE odeEX.CTpa5 B odaaen odecne9eEHR sa eX-mcTa a.de3cnacuocn. A30 c.peaxTopaMs ESSP.. Snc., pTu odeux cTpas cor:acnucs,.sro TeMarzra z oxon9aTes- { Hue CopMs.corpy;::Ezseena MoryT dETs yTosseEE.2.corJ;acosasH noc -.. ~ se.onersoro snazTa.s CEA Aeaeranz2 coseTexnx cuenzanzcTos s Map-Te-anpere 17/8 rena.. g;; E xose cocTossnaxcn deces dsno.npassaso, sTo.s.Kazso2 cTpa. l::. He, ~ocodesso e odAacTE EsenennE2,. cTasAapToB, npasEA E.EccZe;osa-nz2 no desonacsoon, onpenezesnas zu@opMaczs,. r=m-?sca sazso2r [ Iru xassoro 'corpynsa9ecTsa. saionaTes.s seness.a;gnx 6praszsa - _.~~ ~ nn2, a se s HPC:allanaseproTCCCPJ. . ? :- ~ -:13 'paurax Iassoro coryy.aaseeTsa. Kassag 'cToposa dyneT:'oxass-r san conegenae Apyron cTopose.s neaysenna. Taxon ns@opuanan 23 Apyraz oprezzsann2 a spa Heod:c:EMocn odecness; ysacne npen- 'f." cTasnTeze2~aTaz.opraE28 W 2 a cEMnoBEyMaI, oeMasapaI E sB3 eta % seneranna enenaazacToz,. E-7 T u oxasan s core 2c nns n r o2 cToposa a noEEMaE2 AeRTen - E soon a tysxaa2 Apyroa cToposu auepanasexas Iezeranas npe::oza-EE.;;.;;; iE,_==.. =:.. 8

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== (5) 3axosona enzz2 an no aroMEo2 aseprernze or'I954 r' E I l (6) 3axososaiens2 an o peopraszsanza asepreraxa oT l 1974 r.. (7) Scrososaienm2 an o sa:mosanson neanxe' no sa:::a:e 'cipp.ac:ae2 cpei;u"or.1969 r... (8.). yxasaren nesTensoon no accsenosanne desona' socia e zeraosoEEWC peaxTopos. ~ .h

3. Ioxyuescu CCCP': s nepe:asz aMepnxasexo2 cropose:

(I) Od::::e nosozenza no desonacsocia 130. !.i (2) Upanzza Texsrsecnon desonacsocin. 'f .(3) Upazzza parzanzoason desonacsoc a (3ponrpa I'occassan,- sopa).. ~ (4) Upasnaa a:epson d'eionacsoen. .(5) Upoensue xaTepnazu no deaonacsoc a d oxa E33P-.I000 !Ce, (32.) (6) SaxosoAaTensE2 an od o se:cisensoc:a coorse:cisyaf.x oprasos sassopa sa desonacs6cnn arouser asexTpocinett. (7) yxasaren nes:ensoen no acczenosaEERM d63onacsocTE

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- Cose cxas croposaecorzacnraes paccuorpe n yxasasEHe npe;- mox5E$lIl-Hak.Ess i esoE~o95e ~x I5 dyia 15WN A-l Axepzzasexas Ieneranas nepesara cose cxo2 cropose yrosses-h5,i ~ -IE'H2' nepe95Hi'"BonpocoB,f.As odcyZ2eHas", nepsH2.s p2in Ebhoporo. [$$ ;. ~~dsinepenas -EPC so'speiur upossieans ~ pinen 'ceocia Coseidisaxe-kh. - pHEascEo2 CosMecTNo2 KoMaccIE no coTpy;EZsecTBy a odIac:2 MZp- [ ~ g: I.

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2. Axoiie@ A.IQAsp', w:7

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6. Exose@ Renas

- nepeso ux, Exzenep-anept::tz, Oyx-Pzzz-cza5 EEH2cEanHaR ZadopaTopEn.

7. A.C.I'pundepr

- ooseTEzx no sayxe.a Te m xe HocozL-c za C.:A a Mocxse... (..:

8. Ex.I.Tosaea

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5. Cuopesso B. A.

- Izpex;op c seneEns. A3C HucTnTyra I=: j , aronso2 aseprza.mu. Kypsarosa. 4

6. Iopo::;yn B.E.

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8. -OzoTan B.H.

- rmm n razesep EseTzT7Ta "TBUZoaZex- . Tpoupoex:'.'. -

9. Tarapazxos B.H.

- sau.rzassoro zszesepa userary a " Ten- . ?' f zoarenpoupoexT". 1

10. Kapzzros A.H.

- EasanEHz oTIeZes2R sa7Eo-HCcIe;osa- . Tesexzz pado: EscTzTy a "It.:;poupoex;". II. Kososos B.L - sau.savas saxa Tupassesna.no Texsa.,. seczo2 de3onacsocT2 A3C ToeropTeIs2A-sopa CCCP... I2. Typosexat'B.I. - sasa.usza o:seaa no sa sopy sa arou-b5 EEMB. sae xTpo cTasEEMZ To ccassB%3opa CCCP... I3 Marros B.L - nepesonux. " ;n J .k5bb l {ll t lll2. -- = ..,..y....

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SUMMARY

VISIT OF U.S. LIGHT VATER REACTOR SAFETY DELEGATION TO LENINGRAD POVER STATION DELAYED.' HEN MINIS

= sY FOREIG N AFFAIRS (MFA) DELAYED APPROVING GREEl'* VRG, SCICOUNS, AMEMEASSY MOSCOV, MEMBER OF U.S. DELEG ATION, o 1 geoic TO VISIT ST AT ION. U.S. DELIG ATIO N, C^ IN LENINGRAD, DECIDED TO DELAY VISIT PENDING SOVIET RESOLUTION OF THIS ERRORI -t 0 0. AND FULL DELEG ATION HAS !!OV RECEIVED APPROVAL FOR VISIT ,0N FEBRUARY a, p,

11. AFTER VHICH TRIP VILL EE EACX ON KIEV

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2. JUST BEFORE C.O.B. FEERUARY B, SCICOUNS GREENPURG RECEIVED CALL FROM MFA' SAYING HE HAD NOT BEEN APPROVED CR0 TO VISIT LENINGRAD STATION: ALTHOUGH ALL OTHERS ON DELEG ATION HAD BEEN APPROVED. GREEl:EURG NAME HAS BEEN SUEMITTED AS TEAM MEMEER ON JANUARY 23. ON WIGHT OF FEERUARY 8, GREENBURG ACCOMPA NIED DELEG ATION EY TRAIN FROM CHtCN /

MOSCOV 70 LENINGRADANYVAY. EARLY FEERUARY 9 CONGEN 'W // LENINGRAD RECEIVED CONFIRMATION FROM MFA THAT GREEK 3URG i P WAS DISAPPPOVED. DELEG AT101: ASKED SOVIETS OF MINPOWER "Y. (ACCOMPANYIN3 DELEG ATION) AND MTA, TO TRY TO GET .'I APPROVAL. SINCE APPROVAL OF GREENBURGHAD NOT COME AT 10:45 A.M., TIME OF SCHEDULED DEPARTURE FOR l SIATION, AND SINCE THIS SEEMED LIKE DELIEER ATE MISCHIEF i EY USSR, ?ELEGATION ADVISED MINTCUER RE*REEENT;.TIVES IN LENINGR AD THAT IT VOULD VAIT FOR THE APFROPAL EEFORE COING 70 THE ST AT IO N. MIt:?OVER REPRESENTATIVES SCHEDULED

• L SI*HTSEEING DURING REMAINDER OF FEERUARY 9 2.. AT MIDAFTER N00N, FEERUARY 9, DELEG ATION VAS ADVISED THRDUOH MINPOVER THAT ENTIRE DELEG ATION COULD VISIT

j ST ATION SATURDAY, FEBRUARY j

EEEN SCHEDULED FOR SIGHTSEEING!!, VRICH DATE HAD F% EVIOUSLY r IN LENINGRAD. L .g

4. DELF.G ATIO N SCHEDULED TO LEAVE, O N SCHEDULE, FOR I'

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.s ,,.j,,.- . - - = = - 7- .7 .,d' g s. APPENDIX E ...== . T*. t.?. E ..w LWR SAFETY:RESEARCH: PROJECTS -- ~ " . y,. - =.. *.... n .n.,.. J. ..j.,, - - - . -. -...,. -+ r P. 7.~-- . 3.. .e

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e Appendix E p. The " reactor safety research" specialties of Russian national institutes are listed as follows: Teoloelektroproyekt Institute (Moscow) 1. Reactor accident analysis and ECCS design ..g Xurchatov Institute (Moscow) E 1. Fuel irradiation effect and failure tests i.: 2. Irradiation embrittlement of reactor vessel and weld materials [. 3. Method of reactor transient analysis Fl. 4. Core design and reactivity effects analyses y Dzherzhinskiy Institute (Moscow) E.:.i =- 1. Non-destructive inspection techniques 2. Reactor vessel inside inspection by inserting a shielded cage I 3. Operational experience of water chemistry in PWR and steam generator Li:. Gidroproyekt Institute (Moscow) - Scientific research station named after S. Ya. Zhuk. 1. On site seismic response tests ~ 2. Shake table tests 3. Structural modeling analyses Izhorsk Plant (Koloino-south of Leninarad) ~ ~ 1. Acoustic emission inspection of stainless steel lining in reactor vessel 2. X-ray inspection of reactor vessel wall I IE ~ .:= 5: { [I s , me a e o a. .-}}