ML20027C886

Summary of ACRS Grand Gulf Subcommittee 820811 Meeting in Washington,Dc Re OL Review

ML20027C886
Person / Time
Site:	Grand Gulf
Issue date:	09/09/1982
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2018, NUDOCS 8210270380
Download: ML20027C886 (16)

Text

_ _ _.

A23 Mf L,

N l

ULHiltiLD COPY 2

E E

b DATE ISSUED:. SEPT. 9, 1982 MINUTES OF THE AUGUST 11, 1982 ACRS GRAND GULF SUBCOMMITTEE MEETING 1717 H STREET, N.W., WASHINGTON, D.C.

The ACRS Grand Gulf Subcommittee met on August 11, 1982, in Room 1046, at 1717 H Street, N.W., Washington, D.C.

The purpose of the meeting was to con-tinue the operating license review for Grand Gulf Nuclear Station, Unit 1.

Notice of this meeting was published in the Federal Register on July 22, 1982.

The Federal Register Notice is Attachment A.

A copy of the schedule of pre-sentations is shown in Attachment B.

The ' attendee list is Attachment. C.

A complete set of presentation slides and meeting handout material is on file in the ACRS office.

Attachment D is a list of meeting slides and handouts.

Herman Alderman was the Designated Federal Employee for this meeting.

The entire meeting was open to the public.

~

Introductioni Dr. D. Okrent opened the meeting by noting that its purpose was to discuss the Mississippi Power and Light Company's request for an operating license. He stated that there were no requests for oral statements or written statements from members of the public.

Status of the Review - D. Houston, NRC Mr. D. Houston discussed the status of the review.

He noted that the Second Supplement to the Safety Evaluation Report presented the structural and containment resolution for the LOCA loads on the HCU floor and also the present resolution with a few license conditions of the management concerns.

The Third-Supplement to the SER presented resolution for equipment on LOCA l

loads and a resolution for hydrogen control.

/

8210270300 820909 PDR ACRS 2010 PDH

4 Grand Gulf Mtg 2

August 11, 1982 Mr. Houston mentioned that, at present, there are approximately 20 issues which have been justified for low-power licensing which still need to be cleared before full power.

Among the items to be resolved are:

. Seismic qualification of thermocouples.

This is supposed to be carried out July 23.

. Qualification of the MSIVs and the RHR heat exchangers.

These are to be qualified by August 31.

. Qualification of dry well and containment isolation valves.

The Staff has received the information and it is under review.

. Hydrogen control.

The license condition is based upon the comprehensive qualification test program to demonstrate 'that the system remains func-tional in a post-accident environment.

Report of the ACRS Fluid Dynamics Subcommittee - M. Plesset, ACRS Dr. M. Plesset noted that the question of hydrodynamic loads on the HCU floor had been resolved.

The structural analysis has been completed and the Staff is satisfied with the results.

In regard to Mr. Humphrey's concerns, Dr. Plesset

~

remarked that they appear to be of "second order," and "not of the kind that would ordinarily come to be considered by us or even by the staff." The concerns relate to the interface problems between what the nuclear island designer has as a requirement and the architect engineer.

Dr. Plesset said that the concerns are generic in nature so that they don't have to be restricted to Grand Gulf.

Dr. Plesset remarked that he polled his subcommittee and consultants after the meeting, and the unanimous response was that Mr. Humphrey's concerns should not preclude the possibility of giving Grand Gulf a 100 per-cent power license.

w

/

T,-

I Grand Gulf Mtg 3

August 11, 1982 Mr. Ebersole noted that a matter he is concerned about, more than the Humphrey concerns, is what does a large LOCA do to the supply and exhaust tubes of the hydraulic control units.

The scenario that Mr. Ebersole postulates is that less than a second before the complete rod insertion, the jet forces strike the control units and a number of control rods cannot be completely inserted.

The end result is a reactor that cannot be made subcritical, and continues to generate a heat load that is larger than decay heat.

This issue was treated on a generic basis *and a memo was sent to NRC's Executive Director of Operations requesting the Staff to address this issue in the future before an ACRS Subcommittee.

Hydrogen Control, S. Hobbs, MP&L Mr. S. Hobbs, MP&L, discussed the Hydrogen Control System.

MP&L has evaluated two base cases for sensitivity studies.

The cases used were a stuck-open relief valve and a small-break LOCA in the dry well.

Mr. Hobbs presented data from the study to the Committee.

Mr. Hobbs noted that the spray shield above the igniters in the wet well region have been removed.

Mr. Hobbs noted that MP&L has 90 igniters in the drywell, wetwell and the con-tainment.

The separation criteria for igniters is 30 feet, or up to 60 feet if only one train is in place. The minimum glow plug surface temperature is 1700 degrees.

The igniter assemblies are qualified for seismic and hydrodynamic events and safety relief valve actuation. There is a testing program for the hydrogen control system.

The only tests to be conducted are the actual burn environmental tests.

/

L

t Grand Gulf Mtg 4

August 11, 1982 Management Structure and Technical Capability - N. Stampley, MP&L Mr. N. Stampley was the lead speaker on management structure and technical capability. He remarked that MP&L always tried to obtain the best qualified esployees for whatever jobs they have. He noted that the Manager of Quality Assurance reports directly to him.

Mr. F. Lewis, Middle South Utility System Mr. F. Lewis remarked that he would talk about the Middle South Utility System, about the efforts under way to enhance peer review and sharing of resources, and resources to improve the flow of information within the Middle South System.

Mr. Lewis emphasized the management intent to complete the construction of Unit 2 of the Grand Gulf Nuclear Station.

Middle South Utilities is composed of: Arkansas Power & Light Co.; Mississippi Power & Light Co.; Louisiana Power & Light Co.; New Orleans Public Service, Inc.;

Middle South Energy, Inc.; Middle South Services, Inc.; and System Fuels, Inc.

Middle South Services provides technical and other services to the operating companies. System fuels is a fuel procurement subsidiary of the operating copanies and is involved with nuclear fuel procurement.

j Mr. Lewis discussed a new entity called the System Nuclear Oversight Committee.

This Committee will conduct an overview and appraisal of nuclear activities I

of the whole system to develop standards for performance. The Consnittee will be composed of the highest-level corporate official, from each corporate entity, with a professional nuclear background.

l

/

l

Grand Gulf Mtg 5

August 11, 1982 Plant Safety Review Committee - K. McCoy,-MP&L The Plant Safety Review Committee reviews safety evaluations, proposed changes which nay involve an unreviewed safety question, and other topics which nay involve plant safety. The Committee is composed of seven members, chaired by the Assistant Plant Manager and the 1.uclear Support Manager is the Vice Chairman.

Other members are the Operations Superintendent, the Technical Support Superin-tendent, the Quality Superintendent, the Chemistry and Radiation Protection Superintendent, and the Maintenance Superintendent.

Mr. McCoy noted that the specifications called for monthly meetings. During the startup period, meetings have been several times a week.

Safety Review Committee - L. Dale, MP&L Mr. L. Dale noted that the Safety Review Committee was organized and had its first meeting in June 1981. The meeting frequency has been approximately monthly. The committee has expanded from the initial 7 to 11 members since its initial organization. The committee reports to the Senior Vice-President, l

Nuclear.

Mr. Dale pointed out that currently the Safety Review Committee functions according to the technical specification.

He noted that they are planning to expand the charter and the areas of review in conjunction with the Nuclear Oversight Cons mittee of the Middle South Utilities.

In response to a question from a ACRS Member, Mr. K. McCoy discussed the recent resignation of the Assistant Plant Manager. This resignation was of some concern l

l

[

D Grand Gulf Mtg 6

August 11, 1982

-~

to the Staff because the Assistant Plant Manager had considerable BWR experience.

The current Assistant Plant Manager has had eight years of BWR experience at the General Electric Company. Mr. McCoy mentioned additional personnel with BWR experience that have been hired to enhance their staff. Mr. McCoy also dis-cussed an advisor with considerable BWR experience who spends about 80 per cent of his time at the plant site.

Quality Assurance - R. Lewis, I&E, NRC and A. Wagner, I&E, NRC Mr. R. Lewis mentioned that early in the program they were concerned about the limited number of people at the facility with recent BWR experience.

He roted that MP&L has obtained BWR-experienced personne1' and, with the addition of the advisor to the plant manager with BWR experience, the I&E staff is satisfied that the BWR experience is there now.

Mr. Lewis also noted an initial concern regarding MP&L adherence to procedures.

This concern was addressed by having the Corporate Safety Review Connittee conduct audits of the initial operations which would check adherence to procedures.

During fuel loading and the ascent to power, I&E specialists will check the safety review team performance and the history of adherence to procedures.

Mr. Lewis pointed out that he believes that the mechanism is in place to satis-factorily resolve the procecure adherence problem.

Mr. A. Wagner noted that during low-power startup all the operating staff will have an opportunity to do the evolutions that are one of a kind or evolutions that are not done very frequently in the startup of BWR. He stated that this will give some experience to all of the operating shif ts.

/

~.

V Grand Gulf Htg 7

August 11, 1982 Do Sensor Systems Meet Single Failure Criteria? - E. Rossi, NRC Mr. E. Rossi noted that the basic answer to the question posed is that the NRC intends that they do not meet single failure criteria. The Staff performs an audit review. The Staff reviews manifolded nr. common sensing lines. They consider a transient initiated by a break or a leak of the sensing line.

Then an additional random single electrical failure is considered. Then the Staff has to convince itself that there is no safety problem with the assump-tions.

Regarding Grand Gulf, the Staff has not reviewed in detail all the sensing lines used for protection systems

..d Gulf. Mr. Rossi cited the level measuring system at Grand Gulf as one that had been carefully reviewed.

G. Caesare, MP&L Mr. G. Caesare noted that they take a design basis event, the accident. They take the consequential failures that result from that event, and then impose an addi-tional single random failure. The end results are the safety systems required to mitigate the consequences of the design basis events or the accident..

Mr. Caesare cited one of his slides which stated:

... protection systems are designed to be separate from control systems to the extent that failure of any comon element will leave a protection system, at least one system, to the extent that you satisfy this intent by having reliability, redundancy or diversity or independence."

r

t i

e 4

i 4

Grand Gulf Mtg 8

August 11, 1982

_ Schedule for Full ACRS Meeting on Grand GQ1f - D. Okrent Dr. D. Okrent discussed the proposed schedule for the Full Comittee review of the Grand Gulf Nuclear Station, Unit 1.

t The Meeting was adjourned at 7:32 p.m.

Future Meetings 1

Full ACRS Committee review of Grand Gulf Nuclear Station, Unit 1, August 12, 1982.

g,.

=

4 4

I

+

0

'l e

s

/

Federal Register / V 1. 47. NL 141 / Thursd:y, July 22, 1982 / N;ticcs

~

31782<

NEPA.)The purpose cf this Policy the cognizan't Designated Federal Statement is to furnish that guidance for NUCLEAR MECULATORY n Employee,Mr. Herman Alderman

- (telephone 202/634-1413) between 8:15 NRC staffs own NEPA analyses, for COMMISSION Advisory Committes on Reactor a.m. and 5 00 p.m. e.d.t.

proceedings in which NEPA Safeguards, Subcommittee on Grand' I have determined,in accordance with psychological stresa contentions have Gulf Nuclear Station Unita 1 and 2; Subsection 10(d)of theFederal

. been or may be raised and for any Advisory Committee Act, that it may be petitions which may be submitted under Meeting necessary to close some portions of this 10 CFR 2.200 requesting relief on the The ACRS Subcommittee on Crand meeting to protect p prietary and basis of NEPA psychological stress Gulf Nuclear Station Units 1 and 2 will Industrial Security ormation.He issues.

hold a meeting on August 11,1982 Room authonty for such closm is Exemption ne court's opInlon states that the issue of first impression" which it 1046,1717 H Street. NW, Washington, (4) to the Sunshine Act,5 U.S.C l " addresses is "the cognizab[li of post.

DC.ne Subcommittee will continue the 552b(c)H).

discussion of the Mississ plPower and traumatic psychologica! hes! effects Detedduly te61962.

under NEPA." Slip op. p.13. Elsewhere,

!)ght Company'e request or an John C. Hoyle, the court stat, s its holding that whue operating license.

e In accordance with the procedures Advisory Comm/ttee Management Officer.

NEPA"does not encompass mere outilned in the Federal Register or.

ps on. an.i e ru.o.auen nes ]

diasatisfactions arising from social September 30,1982 [46 FR 47903), oral emisso coot rees.ew opinions, economic concerns, or political or written statements may be presented disagreements with agency policies," the L.-

by members of the public, recordings Conalderation of PsychologicalStress statute "does apply to post traumatic j

anxieties, accompanied by physical will be permitted only during those losues; Policy Statement efrects and caused by fears of recurring portions of the meeting when a tr:nscript is being kept, and questions AotNcr. Nuclear Regulatory catastrophe." Slip op. pp.16-17. The may be asked only by members of the Commission, court underlines this point with a Subcommittee, its consultants, and Staff. Acnoec Statement of policy.

reference to the " unique and traumatic nuclear accident" which gave rise to the Persons desiring to make oral sowuAmr. On May 4,1982, the United fears alleged by PANE. Slip op. p.16.

st:tements should notify the Cognizant Fcderal Employee as far la advance as States Court of Appeals for the District ne court also stated:

of Columbia Circuit issued its opinion in pr:cticable so that appropriate arrcngements can be made to allow the People AgainstNuclearEnergy(PAATl We need not attempt to draw a bdsht line n:cessary time during the meeting for v.NRC, No. 01-1131. By a divided vote, in this case.Thru Mile Island is, at least so the court ruled that the National far.the only event ofits kind in the American such statements.

Environmental Policy Act requires the expedence.We cannot betim that the

%e entire meeting willbe open to psychological aftermath of the March 1979 Commission to evaluate the effects on accident falle outside the broad scope of the public attendance to except for thosesesalons dudng which the Subcommittee psycholo ca! bealth of National Environmental Policy Act. Slip oS finds it necessary to discuss propdetary

%ree e Island Unit 1 cility,ne P'

and Industrial Security information. One Commission is directed to determine

%e majodty opinion'thus stands for

• or more closed sessions may be whether "significant new circumstances the proposition that an evaluationbf necessary to discun such information.

or infermation have arisen with respect environmentalimpacts under NEPA (Sunshine Act Exemption 4).To the to the potential psychological health includes evaluation of " post. traumatic cxtent practicable, these closed sessions effects of operatig the %D-1 facility," anxieties, accompanied by physical will be held so as to mintmf=

and ifit answers tnat question effects and caused by fears of recurring.

inconvenience to members of the public affirmatively, to prepare a catastrophe." As the Commission reads

" supplemental environmental impact

%e agenda for subject meeting abaB statement which considers not only the opinion, the cognizability of In ettendance.

be as follows: Wednesday. August II.

effects on psychological health but also psychological stress impacts under IG82, 230 p.m. until the cortclusion of effects on the well-being of the NEPA thus hinges on three elements, communities surrounding Three Mlle First, the impacts must consist of " post-During the initial portion of the Island."

traumatic anxieties", as distinguished business.

%e time within which the from mere dissatisfaction with agency l

m:eting, the Subcommittee, along with Commission may seek further review of proposals or policies. Second the cny ofits consultants who may be the court's decision by a petition to the impacts must be accompanied by present, will exchange preliminary Supreme Court for a writ of certioruri physical effects.%hd, the " post-vi ws regarding matters to be considered during the balance of the

. has not yet expired.Irres ve ofits traumatic anxieties" must have been plans with respect to f er judicial caused by " fears of recurring ne Subcommittee will then hear review of the decision,however,it is catastrophe".nis third element means meeting.

preser.tations by and hold discussions necessary for the Commission to that some kind of nuclear accident must with representatives of the Mississippi provide guidance on the applicability of already have occurred at the site in the decision to NEpA issues raised in question, since the majority's holding Power and Light Company, NRC Staff.

proceedings other than the %ree Mile was directed to " post-traumatic" th fr consultants, and other laterebted Island Unit 2 restart proceeding, since anxieties and by fears of a " recurring" persons regarding this review.

the court did not provide explicit catastrophe. Moreover, the majority Further information regarding topics la be discussed, whether the meeting

, instructions to the Commission on that clearly had only serious accidents in has been cancelled or rescheduled. the issue. (Indeed, the court stated expressly mind.because of the use of the word Chairman's ruling on requests for the that it saw no need to attempt in its

" catastrophe" and its references to the decision to " drew a bright line" between " unique" %ree Mile Island Unit 2 cpportunity to present oral statements

• cognizable and non-cognizable accident in the opinion. In the and the time allotted therefor can be Commission's view, the only nuclear obtained by a prepaid telephone call to psychological stress effects under I

ATTACHMENT A E

3

TENTATIVE SCHE 00LE ACRS GRAND GULF SUBCOMMITTEE AUGUST 11, 1982, ROOM 1046 1717 H STREET, N.W., WASHINGTON, D.C.

2:30 P.M.

2:30 p.m.

Opening Remarks D. Okrent 2:35 p.m.

Status of Review NRC 3:00 p.m.

Report of ACRS Fluid Dynamics Subcommittee M. Plesset (1) Hydrodynamic LOCA Loads (2) Humphrey Concerns 3:45 p.m.

BREAK Outstanding Issues 4:00 p.m.

Hydrogen Control MP&L 5:00 p.m.

Management Structure & Technical Capability MP&L Mr. Humphrey's Containment Concerns MP&L 5:30 p.m.

BREAK 5:45 Plant Safety Committee MPAL Seismic Qualification of Equipment MP&L MP&L Containment Purge 6:00 p.m.

Do Sensor Systems Meet Single Failure NRC and MP&L l

Criteria?

6:20 p.m.

Quality Assurance and Quality Control I&E, NRC 6:40 p.m.

Other 7:00 p.m.

Adjourn e

e ATTACHi4ENT B

/

H. ALDERMAN.

MEETING ROOM:

• *s

.U)VISORY COMMITTEE ON REACTOR SAFEGUARDS MEETI GRAND ULF 1717 H St. NW., Washington, D.C.'

PLEASE mtsotts ettist sic: ittov l

3RlNT

. BADCt NO.

AFFILIATIO?:

l 1 O/73

]

,deedh/

Neft l

1.

// f /o e e a A i n 1 W. 772ichric

} Oc24 /

}

decAfe/

~

d.. /. fe-ce

'I o M.r l

Accorn l wr i K ic 3.

l A 4M J.#Lru n-er lS.//M./leceM

}

ci 8 /

}

/3 & r/ v E t j

o p 36 l

(bchhJ J 3 D, Rov +h l

O///

l r3eckfel

1. E &l4/ff/ eld B. J S,nele m',Ii J o ao E l

hMe F ~

l bel et.

J c.co m JK j 0 24-4 lo. 5 - t $ h l

Ol9f l

OctAF4(

n. m sAvi8 l con 1

naw

n. & 6 A4 I oz4r I

semrsc 9A %N,

}'O YR7 i_ G S.'

1.'N'11//Md 1 0 /A 2-I GA f

)S. 4 T n,. J, e w o

[o t 7 (

1 Ca s

-nve n.

it. N ee O wn j o/tG l 6;.. ; O 4 4 & '_

11, A-Q G/+7/Yh

_$ O/0 Y l

GG/U GL ECT-lA

/ I M/r//Alfd&M l

OMD-S }

bd h

0I$ /

_h G ku Et E C r

.M.

bff LAVE

]

oz2 9 ) GV Jb. K.f_. M as.

.R d&h& A/SW

{

O.1lD h, CA Mics ~ &L-.

j OG8 l

.k M C.

3, k09e,- T. 63 i l O nacMEvTC

. e;.:: t. c.:;.m.... S,....

c, ;+a.,,,.,.;,... s.....,,,,,;,.,,,,.,,,,,.,y,,,,,,,,,,.

> ; c :

.',s... ;;:

H. ALDERMAN AUGUST ll,1982

, HEETING DATE:

$UBC0!NITTEEMEETING:

GRAND GULF LOCATION: _ ROOM 1046,1717 H St. NW., Washington, D..C.

ATTENDANCE LIST PLEASE TRI N T l@E I

AF F ILI AH ON f* Wob FMrs Mio/xe Siv>rst D71x/7/as r A4L ErnWAe7 Ahs kivsk C //avr /?n TD Q,

),',

} s s fh, s'> $ ~ "

+ e k A'f C.

3,

. ). V ' h c Q,b ha s fe u r f,9~ G a

2 % oesh e en e

+

s.

6.

$hl]

mb NP Y -

L F DA

~

/W +L 1.

mar Aw none

33. hac,

e. l'.7M9(11 Mfcl 10.

R.

- Nt.wm GE M.TT l4iWF GEG

,11.

2--

s RicuAxosea y

,ac est e

N.P.dasns n.

61), /?1. Dn v5 GE

,s.

A/ J A//M rr-wszen W A3swrrL 15.

YM7c SA P.

we?

16 cK b b.

E.N It -

17.

hM.1 J. s. sonde.ma i is.

bc Me-l V,d.

' Areas

. as.

A.T.

vie.; n

&ct+eR

, ro.

21.

3>H Askton

.Bukk{

N25, O A )hdib x e C tTrcL S D buO G e c.hh.)

23.

g u

m

~

[._.

H. ALDERMAN

~

~

l MEETING ROOM:

AD ISORY COMMITTEE REACTOR SAFEGUARDS MEETING GRAND GULF 1717 H St. NW., Washington, D.C.'

ATTENDEES Pl. EASE SIC': B Eto'.'

kkT AFFILIATION

(

BADCE 50.

NefE

/, hy. b. t > kt f f kes h.//ise c3 k kbw af_l 1

(., $. OxlFN' M C l 6 O'd'7 l M

l

~

$ H HoOg k E-o tst l M V k l-l lG.OEY2-l S e.ek'fe !

l A bfl hShk l e o I is l i2eJLrd 1

/.T. nen ui l m -oi 70 - l 8edd/

\\t 10.lW ecn

,. 'y.s. n -s le - o to s l cxx

<3 b b

[M-4-EL:LM l 6 - 6 /~7 4 l

f L L, P w e..C o -

b.

/1 A.

1. Ndd lP 6/Cc *

'l 4,ae

>bwT:-lEhtWrs 18.

n /, ~ Tr/EFE L.

l 6-D7./9 l'Jr<e E d6Socs n. D W A n s t,a l r o it l A129L z

l u.As h L

n. a k. 52-I tr-oau h1"r'Ma&v l coziz l AffML n L k kle l 5 e2z7 l_/1A4L.

1s rr mn >

D& w2 l ant.

l E - Diol l MM 'LW oh% rs 1L. Flodld.L nu it,T 9 BP (?aub l E-sso l wtt

18. N, L. SrAl$

8/

l E ~ bll1 l M/4L

~

Y1. Q Y - (L lads ~

lt -oo1f l

/ M (91 L r

g h4 cm.%u l E o 2.o s:-

.I mht 1.

&. W P'O lh l cn1 & 5

$ (W OfD' at E

LGG j o -zo / >

l g ec AtcJ2

~

~

l

/-

l 1

H. ALDERMAN.

MEETING ROOM:

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MEETING ON -

GRAND GULF 1717 H St. NW., Washington, D.C.'

PLE"ASE ATTENDEES PLEASE SIC': BELO'4

~

7RlRT AFFII.IATION l 12?v 6f HalW D ei7 c j Miss: Po !W/_i9 W BADCE NO.

NAME x 9(ohn e:Mo natt f~ n iva 1

EcoNd 11 1

x I

I i

A I

J s.

1 l

L I

I 1.

I 1

~

s.

h.

1 I

l I

,m 1

J l

n. -

J 1

~

n. -

l' I

l n_T I

1

=

- a.

is J

J la.

DJ J

1 1

_i 1

f n.

,h J

l et I

I

=

n.

Y 1

2 R

1

~

at a4

m.::.

.., i.. k L.. a.......... a n.~ :....,...... ~....... ~. ~......

~

H. ALDERMAN NEIINGDATE:

AUGUST 11, 1982 SliBCOMMITTEE MEETING:

GRAND GULF 1

LOCATION:. ROOM 1046,1717 H St. NW., Washington, D..C.

ATTENDANCE LIST PLEASE TRI N T AFFILIAliUN I4AME

i.. /)m,% 4-

1. 1. < - la.o1

!,. 4. %%en PEc./DL

^/12 C l S N' T' 3.

A. W e c sc(L t) k / F 4 /c h s/&//ST/4WI a

' 5.

6.

7.

B.

o 10.

11.

llt.

.l3.

114.

15.

'16.

l17.

.18.

19.

20.

.21.

??.

6 -s,,

v.

. u:s". 4.:;.c ~.. :s r u r i M c *> & * * * ' ' : "~ ' ' ' v--

u " '

^'" ';"** * ~ ~ ' ~ ~

"# """ ~ -

., + :.....; ;;1 H. ALDERMAN AUGUST 11, 1982 HEETING DATE:

GRAND GULF s'UBC0!HITTEE MEETING: _

ROOM 1046,1717 H St. NW., Washington, D..C.

LOCATION: _

ATTENDANCE LIST PLEASE TRI N T N

1. 'E I

AFFILIAllON

, '. N/LEsH cHokrHI nt;7p /cE,uggg r GHw f

7&&

xiejz. /Ds //Ga N R R' /3sI / RSS 3.JoLn LoM BOL P/.a I Aa's / psr'/ cSe a

Ls. At w 4 % % n4<esen

1. 9 b l D R r / c3 k A/Afd /PGI/CSB

$//A2/CC 7[A/KtA;e-6 A.)

/ 9 6 D / C 6,9; 7.

A4%ED

. $ M A f M f tf

'.D VERilE LL i URL / 7% Z s.

A/NfNL y

~ S C.be-wsS o_

10.

50, CAAlRA / /

11.

12.

13.

14.

15.

16.

.17.

18.

.19.

70.

0#h

_21.

25.

_23, l