ML19325F172

Transcript of 891101 Briefing by C-E on Advanced LWR Sys 80+ in Rockville,Md.Pp 1-42.Supporting Documentation Encl

ML19325F172
Person / Time
Issue date:	11/01/1989
From:	NRC COMMISSION (OCM)
To:
References
REF-10CFR9.7 NUDOCS 8911140379
Download: ML19325F172 (78)

Text

.. _

}

7-s

,, o A.

g.

l r

t UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMIS SION f

i' l

i ibI13 BRIEFING BY COMBUSTION ENGINEERING ON ALWR SYSTEM 80+

l t

1 I

LOCatiOIl ROCKVILLE, MARYLAND i

hdk0 NOVEMBER 1, 1989

.f i

l

?!G6S:

42 PAGES r

i t

i i

t NEALR.GROSSANDC0.,INC, COUit REPORTERS AND TRANSCRIBERS 1323 Rhode Island Avenue, Northwest j

Washington, D.C.

20005 i

(202) 234-4433 1

1101 y,

Foe

l j

DISCLAIMER This is an unofficial. transcript of a meeting of the United States Nuclear Regulatory Commission held on November 1. 1989.

in the Commission's office at One a

\\

White Flint North, Rockville, Maryland.

The meeting was open to public attendance and observation.

This transcript has not been reviewed, corrected or edited, and it may 3

contain inaccuracies.

i The transcript is intended solely for general 1

informational purposes.

As provided by 10 CFR 9.103, it is I

j.

not part of the formal or informal record of decision of I

i the matters discussed.

Expressions of opinion in this transcript do not necessarily reflect final determination i

or beliefs.

No pleading or other paper may be filed with I

I the Commission in any proceeding as the result of, or t

addressed to, any statement or argument cortained herein, t

except as the Commission may authorize.

i r

NEAL R. GROSS COURT Rf#oRTER$ AND TRANSCRIB(R$

1333 kNoet 15 LAND AYtNU(,N W, I

(302) 734 4433 WASHeN0 ton, D.C.

7M05 (202) 232 6600

i

+

1 i

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION I

BRIEFING BY COMBUSTION ENGINEERING ON ALWR SYSTEM 80+

r PUBLIC MEETING r

Nuclear Regulatery Cowrission One White Flint North Rockville, Ma*yland Wednesday, November 1, 1989 i

i The Commission met in open session, pursuant i

to notice, at 1:00 p.m.,

Thomas M.

Roberts, Commissioner f

presiding.

COMMISSIONERS PRESENT:

THOMAS M. ROBERTS, Commissioner RENNETH C. ROGERS, Commissioner JAMES R. CURTISS, Commissioner k

NEAL R. GROSS CoVRT AEPoRTERS AND TRANSCRIBERS 1323 RHoDE ISLAND AVENUE, N W.

902) N WASHINGTON, D C. 20006 (202)232 4000

s g

o.

~'

STAFF AND PRESE!iTERS SEATED AT THE COMMISSIOli TABLE:

SAMUEL J. CHILK, Secretary i

WILLIAM C. PARLER, General Counsel SHELBY BREVER, Prepident. Nuclear Business.

Combuction Engineering ED SCHERER. Director Nuclear Licensing, Combustion Engineering Dr. Regis Mat:1e, Director. Advanced Water Reactor Projects.

Combustion Engineering 5

O 4

NEAL R. GROSS COURT REPORTERS AND TRANSCR$ERS 1323 RHODE ISLAND AVENUE. N W.

(202) 2M4433 WASHINGTON. O C. 20006 2 A024000

c 3

1 P-R-0-C-E-E-D 'I-N-G-S 2

1:02 p.m.

3 CHAIRMAN ROBERTS:

Good afternoon, ladies A

and gentlemen.

The Chairman will not be with us.

He 5

is participating in an exercise on a simulated 6

radiological event at o se of our licensees.

He i

7 regrets he's not here.

He acked me to assure you that 8

his absence in no way indicates any lack of interest t

9 in the subject matter.

His staff is well represented,

}

10 and he will review the transcript, s

11 Does anyone have any opening remarks?

12 COMMISSIONER CURTISS:

Not me, Tom, t

13 CHAIRMAN ROBERTS:

Well, we are here, this I

i 14 is one of a series of meetings today, to hear about i

15 next generation reactors, and now we'll hear from 16 Combustion Engineering, Doctor Brewer.

17 DOCTOR BREWER:

Thank you very much, Mr.

18 Chairman.

19 CHAIRMAN ROBERTS:

I'm not the Chairman.

20 DOCTOR BREWER:

Acting Chairman.

21 CHAIRMAN ROBERTS:

I'm chairing this 22 meeting.

23 DOCTOR BREWER:

I'm Shelby

Brewer, 24 President, Nuclear Power Businesses at Combustion 25 Engineering, Inc., and I'm pleased to be here today to NEAL R. GROSS CoVRT REPORTERS AND TRANSCRIBERS 123 RHODE ISLAND AVENUE, N W.

(202) mg WASHINGTON. O C 20006 (202 4 324200

c a

4 4

1 talk about certification of our System 80 Plus 2

advanced pressurized water reactor plant design.

3 It's been almost two years since we last 4

discussed this subject with the Commissita, and much 5

has been accomplished since then.

6 I have with me today Ed Scherer on my right, 7

our Director of Nuclear Licensing, Doctor Regis Matzie 8

on my left, our Director of Advanced Water Reactor 9

Projects.

In the time that we have this afternoon, we 10 would like to touch on three very important points.

11 The first point is, I would like to share 12 with you my perspective on the direction of the 13 nuclear industry and why I believe that the System 80 14 Plus design will play a very essential and leading 15 role in the industry's future.

16 Second, we want to point out some of the new 17 design features that we have incorporated into System 18

'80 Plus including those specifically directed at 19 meeting EPRI requirements and resolving severe 20 accident concerns.

21 Third, we will review the current status of 22 our design certification application and the progress 23 of the Staff's review toward our goal of design 24 certification in 1992.

25 We would, of course, welcome any questions i

NEAL R. GROSS CoVRT REPORTERS AND TRANSCR$ERS 133 RHoDE ISLAND AVENUE, N W.

(202) N WASHINGTON. D.C. 20006 (2W 2324600

5 1

or comments that you might have during the course of, 2

or after, our presentation.

3 I would like to set the stage for this 4

discussion by sharing with you some of my thoughts on 5

the future of the nuclear industry.

6 Part of my perspective is derived from 7

Combustion Engineering's broad participation in the 8

nuclear market, including the supply of nuclear steam 9

supply systems, fuel and nuclear services.

This is 10 consistent with our support -- company wide -- for all 11 segmeats of the power generating industry.

You can 12 see from this slide, Slide 2 please, that although our 13 domestic construction backlog has nearly been 14.

completed, we are still engaged in a wide range of 15 nuclear system design activities.

16 Development of our System 80 Plus design is 17 geared toward the future domestic market, and is 18 shaped by our perspective of market requirements, both 19 in the near term and the long term.

In addition, it 20 supports our design and construction activities in the 21 Republic of Korea.

The two units to be constructed at 22 Yonggwang are based on our System 80 design and will 23 contain some of the System 80 Plus features.

24 Furthermore, in partnership with Combustion 25 Engineering, the Koreans are embarking on a

NEAL R. GROSS CoVRT REPORTERS AND TRANSCRl8ERS 1323 RHoDE ISLAND AVENUE. N W-902) N WASHINGTON, D C. 20006 (202) 232 4600 3

n 6

)

1 standardization program, and we fully expect that I

2 System 80 Plus will serve as the model for the next

{

3 light water reactors to be built in Korea.

4 The certification of our System 80 Plus 5

design under the new licensing format, 10 CFR 52, is 6

our top priority in terms of preparing for a nuclear 7

future.

8 We are also engaged in design of certain 9

more advanced designs, together with Rolls Royce, 10 Stone and Webster, and the U.K.

Atomic Energy 11 Authority, we are developing a smaller reactor that l

12 emphasizes passive safety features:

the SIR design.

13 Plans are being developed for construction of this 14.

reactor in the United Kingdom in the mid-1990's.

15 In the development of the commercial modular 16 HTGR, we hold a prime contract from DOE as well as two 17 subcontracts for substantial parts of the design.

And l

18 we are heavily involved in activities leading to 19 construction of two new production reactors for the L

20 Department of Energy:

a gas-cooled reactor and a l

21 heavy water reactor, t

22 So, as you can see, Combustion Engineering t

23 is involved in all of the major reactor technologies, 24 and I believe that each of them, in time, can satisfy 25 particular demands and fit into a unique niches in the l

l NEAL R. GROSS CoVRT REPORTERS AND TRANSCRIBERS 1323 RHoDE ISLAND AVENUE, N W (202) 234 4433 WASHINGTON. D C. 20005 (202) 232 4600

7 I

1 future market.

2 My perspective of the industry's future is 3

also colored by observing first hand the nuclear 4

recession in the mid-1970's.

That recession ended the 5

first nuclear era.

t 6

That recession, Slide 3 please, did not 7

result from any inherent deficiency in the technology, 8

but instead resulted from a

labyrinth of 9

institutional, political, regulatory, economic and 10 financial forces.

This particular litany of problems 11 is well known and I will not dwell on them here at 12 this session.

Nonetheless, the experiences of the 13 1970's and 80's reinforce my belief that it is the 14.

institutional problems that we must solve if we are to 15 see a resurgence of nuclear orders.

Technological 16 improvement alone will not sufiice, and a completely 17 new reactor type is neither neccesary nor sufficient 18 to bring about further deployment of nuclear power in 19 the United States.

20 I do not believe that a utility will 21 consider ordering a nuclear power plant unless it is a 22 standardized design, based on proven technology, and 23 is pre-licensed by the Nuclear Regulatory Commission.

24 The evolutionary ALWR -- like System 80 Plus -- is the 25 only reactor species that can meet these requirements NEAL R. GROSS CoVRT REPORTERS AND TRANSCRIBERS 1323 RHoDE ISLAND AVENUE, N W (202) 234 4433 WASHINGTON. D.C. 20006 (202) 232-6000

m 8

1 in the near term, and these are plain realities of the 2

marketplace.

3 System 80 Plus is responsie to these market 4

realities.

5 The design emphasis, Slide 4 please, on 6

evolutionary improvements to proven technology will 7

provide the confidence in the constructability and 8

operability of the plant that utilities will demand.

9 Its large power rating will make the most of 10 increasingly scarce siting opportunities and take i

11 advantage of economies of scale.

We must also keep in 12 mind that the Nuclear Regulatory Commission 13 certification requires that detailed design work be 14,

completed.

Because System 80 Plus is an evolutionary 15 change from previous designs, most of the detailed 16 design information necessary to support the 17 certification application is already available.

t 18 System 80 Plus can be certified by the 19 commission and be available for widespread deployment 20 in the early 1990s.

21 Next slide please.

Design certification of 22 System 80 Plus is,

foremost, a demonstration that 23 institutional obstacles can be overcome and that the 24 new licensing process can be made to work.

This I

l 25 institutional demonstrr. ion can proceed on System 80 NEAL R. GROSS i

COURT REPORTERS AND TRANSCRIBERS 1323 RHoDE ISLAND AVENUE, N W.

(202) m WASHINGTON. O C. 20006 (202) 232 0800

1 y

3 9_,

i 4

1 Plus, without the complications of technical novelties i

O that might lead the Nuclear Regulatory Commission to 3

require -- or, for that matter, utilities to demand--

4 construction and operation of a lead unit.

i S

Let me emphasize that I am totally committed y

6 to the certification process.

I intend, with the 7

support of the Department of Energy, to carry it 8

through to completion.

I believe that it is an 9

essential element in preserving the nuclear option in 10 this country.

Our expenditures at Combustion i

11 Engineering for the development of design information 12 supporting the System 80 Plus application is in excess

/

13 of $200 million.

Support from the Department of 14.

Energy for certification of this design is over $10 15 million.

Certainly we would not be pursuing this path 16 if we did not believe that it will meet the demands of 17 the marketplace and meet the demands of the 18 marketplace in the 1990's.

19 I would like now to ask Ed Scherer for some 20 remarks on NRC's review of advanced reactors.

21 Ed?

22 MR. SCHERER:

Good afternoon.

My name is Ed 23 Scherer and I am combustion Engineering's Director of 24 Nuclear Licensing.

I 25 The reactor designs being developed today by NEAL R. GROSS CoVAT REPORTERS AND TRANSCRIBERS 1323 RHoDE ISLAND AVENUE, N W.

(202) N WASHINGTON. D C 20006 (202)232 4800

j L

10 l [J 1

1 1

Combustion Engineering and others fall into three i

I 2

generel categories:

b!

3 Slide 6 please.

yhe evolutionary ALWR's, 4

such as our System 60 Plus; the smaller, passive 5

ALWR's, such as our Safw Integral Reactor; and the 6

non-water reactors such as the 1:TGR and the LMR.

j 7

It seems to me that the Commission is 8

correct in approaching the review of these.three 9

categories of designs in a roughly sequential fashion.

10 In the first category the evolutionary 11 ALWR's -- the Commission and the Staff will be dealing 12 with technology that is well known.

There is i

13 essentially only one issue that must be dealt with, 14-ant, that is "What is the appropriate level of safety 15 for future reactors?"

If you will, how safe is safe 16 enough and how do we approach the regime cf severo 17 accident phenomenon?

I think it is wise to grapple 18 with these questions first.

19 In what I see or have been calling a second 20 phase the review of the passive reactors the 21 Commission will not only have to deal with the first 22 set of questions, but with some additional fundamental 1'

23 issues.

For example, what are the appropriate trade-24 offs between reliance on " passive" safety features and 25 the traditional emphasis that has heretofore been NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHoDE IP' AND AViNUE, N.W.

(g) 234 4433 WASHINGTON, D.C. 20006 (M) 2324600

 ;

Meeting with The Nuclear Regulatory Commission November 1,1989 Combustion Engineering, Inc.

.n. -.. _. - ~ -..., --

--.~.--.~~.~...aa.

..~.unn. r.a a._2 h

l I

I i

I i

i; k

W b

i 9

9 5

C 9

• =

6 E

C 3

.e2

>q s,,

i 8,

>g9 l

JR g

3 h

O jIL0.

j e

-m s

G O

O t

3 Z

1 I

L I

i,r----

~

- - - ~,.,,,.,..,, -.. ~ -,,, _,

-+,,,--c--,.

,_,w--,,

,,,-.m...

i, v

., a i

t l

l Overview of Combustion Engineering Nuclear Systema Design Activities r

(

l l

= System 80 Plus" Standardized l

Nuclear Power Plant i

1 i

a The Safe Integral Reactor (SIR) i a Commacial HTGR i

t l

m New Production Reactors I

• HTGR

• Heavy Water Reactor i

~

l

[

5 i

1

)

.__._____._-_.__.._____.__j

i i

I Nuclear Recession of the 70's l

Institutional, Not Technological i

i I

i l

l t

1

y

.,-4

--M.a.

l i

l 6

l e

i 9

i E

3 mg Zi i

"E e

a f

i 25 e

=

E

<R n.t!

a 3e E

t 3

g k

=U 3

s,

)

- gh y

a 4

l

~

v) 2 E

g

.9 li e L

j c a e

E 2s 1 ]m 8

5s

<3 i

na m

t a

g a

a a

a a

E j

l A

1 i

+

1 i

i I*

1 i

.i i

System 80 Plus l;

Design Certification i

l 1

l

= Desnonstrates that Institutional l

Obstacles Can Be Overcome i

a No Lead (or Demonstration) Unit l

Required 1

.I I

n C-E is Committed to the Process l

i i

-l 1

o i

1 t

i t

a t

t f

I e

9 a-i e

i a Ag g

I V3 C

E 8a i

f sem a

i W

.h t

O

='

l 4

3 3

I b

i e

i t

I 1

i l

l l

l l

l 1' -..

-. -... -... - ~

,l ii t

il.le i!t

!l

!'!l:

t!

i

!i h ! I !.i 1

1 l

1 l

e i

s e

a s

e h

a s

h a

P h

P P

s w

r oe t i cv ae eR Ry s

e r

3 do R

et k

ca W

s nl L

a u A

R vg de y

W

)r r

e AR a

L dt n

A e a

~

cWs o

e n

or i

t v

at u

i s

vnc lo s

doa v

a ANe E

P (R

.l!

!l i

l

t

' i

./

r l

i i

I i

l I

u Each Reactor Technology Has i

l Merit i

l l

I a Significant Variation in l

Technology Development, Commercial Application, and Regulatory Evaarlence I

r i

i

i

- i

~

..~.__-----....--..-~---.---,.~_.....-.__--.-.-+-_--...-.._.----.__.._.m--._--

,:.j

/

j I

l i

1 Achieve Certification; Available for Deployment l

l Evolutionary ALWR's Early 1990's l

l Passive ALWR's Late 1990's

" Advanced" Beyond 2000 (Non-Water) i l

Reactors l

h

O-U System 80 Plus Design Full Compliance with 10CFR52 j

=

l l

is incorporate EPRI Requirements i

l n

l

= Overwhelm Outstanding Regulatory l

Issues by. Design l

Severe Accidents i

4

• USI's, Gl's, etc.

i 1

i d

l I

i

.j i

i 3

t

.;. -.........-_~

i.

' (.!

iE e 1(.

i 1

s O

n.

e n.

O I

j E

=

d

)

J 8

E D

L I

b O

i I

a i

e L

't3 4

1

?

l

?

\\'

r T

....__,_,_m.,___,,,.

?

Combustion Engineering's l

ALWR Program i

a Start with C-E's System 80 NSSS and l

Duke Power's Cherokee /Perkins BOP u Make SIgnificant 7...

~

r

• Implement EPRI-ALWR Require monts Document :

(

=

Address Severe l,.

~

Accident lasues J

~..

i

-?

a Obtain NRC

~

Certification

+

,l i

~

. System 80 Plus is an Essentially Complete Nuclear Power Plant s Reactor Systems i

l l

a Safeguards Systems i

u Steam and Power Conversion l

Systems l

a Turbine Generator Systems l

s Waste Management Systems 1

4 1

k i

i I

l\\l

))ll,j !l!!t lI l!lt!; i1; iI 9

y l t s

n e

la a r

i u

t l nP d

t er n

c se a

u s

r s

e t

Ew) mr m

S o

u e

d nP d e

t t

a e

t c

s n

r u s

u s y

s s

a y

r g

sa n

S tmS mn s

ei i

J Se g

r e

t slcn e

t t e

t d

n i

r n s t

s u uo w

ey a

y u

l i

^

d i

lPNC o

mS WS B

u l

i 0e(

P nt g

r l

t r

B 8t io n

o o

e e

a r

r t

tp i

p t

e mlp s

np o

p n

h i

l em n

ou o

u o

t O

CS C

S C

O tso yC

=

a u

a u

a S

.~

,i

.i1' il li(!!l!,.ll' llIl1 1liIii!

3 a

1 i

~

System 80 Plus:

Conceptual Design Only i

Site-Specific Features, e.g.:

m Offsite Power (Switchyard) l m Training Facilities 1

a Ultimate Heat Sink i

i i

l m Warehouses i

= Normal Heat Sink & Intakes i

a Security System l

l l

l l

l

l D

l I

l l

t l

1 I

v

\\

l k.

v.

t.

I M

v O

g l

0 l

~

y l

4 I

g 8

g

~

O

~

'O g

en S

4 n

g

$m g

(

L 5'

i s

I

.f s.,

• d) k.

2

Improved Reactor Coolant System & Safeguards e increased inventories o increased Margins Improved Materials 4 Train ECCS

=

4 Train EFWS

^

~

2 In-Containment

~

~

~

RWT Safety Depres-Y

,c l

~~

surization System

~-

a Alternate

. ~77 J L

i 4

Emergency

..... - o- --

I Power Supplies l

h

- m m

9

)

~

l Large, Steel Spherical Containment n Dual Containment a 200 Ft. Diameter Increased Space

~

for Maintenance and Access

~.

t

- Designed to

^

Mitigate Severe s

Core Damage

- Subsphere Space Houses Safeguard Systems

.f-s s.erassaaa_---.--

e

-m-4 J

W da A

6 e

e 4

0 n

J 1

iii

}

}riji%dl.11 l mg

p

'i >

X

?

l>

l1 3

t

.w

,3 sj.9

').'M.

.10i

Jl.

..ik oc

': j,- 's

.?)h)

!bNT [A* '

[E yyjk'e Mg-N ft gig g

.4>,

4 I

i i

1 i

i i

Advanced Control Rdom 1

i i

j u Large Display Screen i

2 i

j u Touch-Sensitive CRT & Plasma Displays I

j u Microprocessors Reduce Operator Burden l

^4} r; :,.y

.,,_7 g.g.. :?p.

..,ry 4iC i,4.i:~C) 7' * -.

%2% M=

a y

u Hierarchy of 3

Information 46 a Prioritized _ Alarms 4

.,i N

a Multiplexing ogg's

. n n,hYkJ7:jl, a Off-The-Shelf s

,w"ETM,g44.g ?!MWW}NI"~

kNN hie

~

n.

, ~-,

Equipment

&pgl 7g:% - :,

m:

www a ~a aa ~

u Self-Testing Features

o 6-4 e

, _s WF&qTe$ gym. ;{iG

.yd ~ TVf. p.,y,, '

.,I

,$l}

!Lm.. f.i g g l w$g ; g d ;p u g g %j]"., 1:l r

@g% ]s;>g A,p w,1,c3 m,f. 4 gy

,s:

M, 1

,4

'f

.<f

%typys et Q.ps....Qv Q u :

g

'[

s

M

-

sa 7

xx R?f%c:

gg r

fe%jp%e;

$a,;g>w@u%ghm;n+&c.

mr$g,t am wa / Qgn '

d>%ga;lf%fgdgrQi p

dr7 4

• y 4

4

Q% n,bi--

7dU h

xedte m e;w

}

a.sh -

m.%fp;g,my,... -

yk;'-::s.s y44

.. my.;.g#Hp[. $,',msa..x..2j[1! ' '"

f3 w..

4a

'm

&ggggyi%g.

\\

Jl[g;[@$

h;}

M

• c usg p;p aM;Ma%gb.'

hnfk%?.il^f... '

ppg f

! js '

gd),e$g

• %MP}ggfj:R 7

e@j&%

.s l

,h_mdomgipywigg q

~&, NJ)

A N

ukTl;gav T. syynw hab

~b$$I,w_hb,h.s+A...id.,

&?dy ~

N r s W h w. A wiWL n w

teed x?pnand"ak!w' q' n

>4tcNG q.; I:

i!h W '9[ N[*h W e' i

%:-Q%'.. c;f!t. i.:.;W;%

+4 a

b#$[b O

p>

Y g

1. kh[ 7 Nhiii$zun

y..

NS

• j4%@@$y k

u.

kWP 3Ch3

$MO$

.,w s"

Yz$31 MFJiG 6; c.4

'1$%phs!.n/p?YjAns{0A$lf+M5 N?fkW

.I

$hyQ!*

s $1 W

hr e

r

• ??

u[N$f

.N.5E E sw bNI m - d MiQ

,e

,1A,

.M,NM#il w.w

.f s

h 4

~ e.qrn

/

,T 92!:9..;

l kdh+ 7 x -

-n...

j

. # n.. =f.f{. ;,

2N

3 i

u i

1

)

L l

l l

f f

MM'

l l

Dominant Contributors to l

Severe Accident Risk (Core Damage Frequency, laternal Events) 3.--

?

'N

% ~' j. :

y e

31.1 %

20.3%

48.4%

2dL8%

2.2%

11.6 %

11.2 %

46.4%

~

LOOP /SDO

&,LOCA

TM

eoea e--

e

&e4Ai-a-<-aA.,a 2 ----+

=e"4

• • • 44 s

A A-

• • A O"4"M&&M-4-"--'

4 N54AAm

+ a er44+M-W^^M-4*-Aa-41%A-

-o=-mm4-n5~.

6 4

9 5

g

-'e i

.1 l

i

)

i

' l 1

l b#

O g

C

.C l

C w

E

,@w o a31 3w w

w3m R&l 9

-0

=

4 3z w

s I

l l

l l

l 1

i l

Design Certification j

e First Submittal:

November,1987 A

- Formal Application

~

for Certification Under Part 52

.~

~

~

-~

March,1989 E'

P '2 y

~

Licensing Review

~.

• a Basis Document Still Under Staff Review

j.

l i

CESSAR-DC l

[

Submittals Completed i

l Date Major items November 1987 - General Description l

- Power Conversion System April 1988

- Reactor Core & Coolant System l

- Chemical & Volume Control System

- Process Sampling System i

June 1988

- Shutdown Cooling System

- Safety injection System

- Emergency Feedwater System h

1

... ~.

y_

1 CESSAR-DC Submittals Completed Date Major items September 1988

- Site Envelope

- Safety Depressurization System l

- I&C Systems

{

- Human Factors Engineering l

March 1989

- Leak-Before-Break Analysis l

- Balance of Plant Descriptions

- Electrical Power Distribution

- Reactor Protection System

- Fuel Handling System

- Radwaste Systems

- Building and Site Arrangements j

- Containment Systems

- Sabotage Protection Program I

i

[..

l l

l CESSAR-DC Planned Submittals I

Date Major items December 1989

- Resolutions to 60 USis/GSIs

- PRA Methodology l

i March 1990

- Remaining USI/GSI Resciutions (60) l

- Equipment Qualification Envelopes

- Additional System Information f

l 1

f t

1 i

t l

f r

1 s

i 4

s

~

,; a I

j i

i CESSAR-DC 1

Planned Submittals a

3 i

Date Major Items Juus1990

- Safety Anaysis l

- PRA & Severe Accident Results

- Seismic Methods

- Building Layouts j

I September 1990

- Seismic Results

- Technical Specifications

- Inspections, Tests, Maintenance &

j Reliabilty Guidelines l

i i

f

,,.a-,c 4

s I

+-

s.

Lg:p m;

f 2p'

-l

. g, e$ $ ast

~-

e l

(

h"$l:.

1

~

.. ?

1 611 -

+

.e.

a N

' h' i

,9 11

.t::

y

~

y g

9-1 O

f.f_

Q e.

+

p<

o lgs 4 7 1

i.f,

[

CO l': s.

L^

~

e n. L i.

1 y u,

i..n,s! }.,,{()

1 8 j. I B -

i 4

en y

f

,t ! !

!ti i!

l.!l!

3*,.

o g

y l

l a

e c

r v

i i

t o s

at n

mc o

s n

d a

'7 a e p

s D R s

e a

r 12 e

r c

9 9 yr ad Rs g

it 9 9 a

e o

s 1

m sc sd r

i 1

in P

l i

'E n

m s a s a a

u uv um n

e An l

l R

Do i

i 1

S P d Pe w

s a

Ft A

D e

c 0

0 e

i

l t

i 8d 8e v

eb f

i e

e u a t

l i

mv mk R

d e-e r

v r

eo ea ei C

t r tM C

hh sp s

ym y

R cc o

Si St N

SA u

u u

m i:

!+l!

i'll!

ll

!lll!ll.!

l i

l;

66d6 twikWW6Wd%%W6f%dtWJ&gtsdf gggg TP.ANSMITTA1. TO:

_d Document Control Desk 016 Phillips j )

1 ADVANCED COPY TO:

The Public Document Room

/// ~7 Of DATE:

r f:

FROM:

SECY Correspondence & Records Branch l

Attached are copies of a Commission meeting transcript and related meeting document (s). They are being forwarded for entry on the Daily Accession 1.ist and t

l -

placement in the Public Document Room. No other distribution is requested or required.

Meeting

Title:

Mk l !

m L ld

[0 +

h Meeting Date:

//// /f9 Open M

Closed i k

[

5 Item Description *:

Copies Advanced DCS

': t to POR

Copy, j

'8 U i

1. TR.1NSCRIPT 1

1 6

ainda r w l1:

i h

e'W h A i I I

g t

ul l l

[

2.

li

!::[

l J-t l

3-3; 3.

g; 3;

3;a-3:

3:

4 33;

$I

"'~

jj 5.

3:

i 3:

3:

L

_fi 6._

L

$i h

3:

• POR is advanceo one copy of each Aeument, two of each SECY paper.

gfo l-gi C&R Branch files the original transcript, with attachments, without SECY

,f g 3;

papers.

3:

2:

_;LJAe I.

lhke o

_