ML19242D604
| ML19242D604 | |
| Person / Time | |
|---|---|
| Site: | Allens Creek File:Houston Lighting and Power Company icon.png |
| Issue date: | 07/16/1979 |
| From: | Froclich R, Moon C Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUDOCS 7908150501 | |
| Download: ML19242D604 (15) | |
Text
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- M h' +'4-UtlITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION G
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BEFORE THE ATO'4TC SAFETY AND LICENSING BOARD ff ro Ll g
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HOUSTON LIGHTING & POWER COMPANY
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Docket No. 50-466
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Ya i Gk (Allens Creek Nuclear Generating
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NRC STAFF'S RESPONSES TO JOHN F. DOHERTY'S THIRD SET OF INTERR0GATORIES The NRC Staff responds as follows to " John F. Doherty's Third Set of Inter-rogatories" filed on Juoe 6,1979 in the captioned proceeding:
Interrogatory No. 1 In the event Applicant is granted a permit to construct two permanent box culverts and a temporary low water crossing approximately 3 miles northeast from Wallis, Texas, by the U.S. Army Corps of Engineers, will the money ex-pended on the project he credited toward the cost-benefit when the final siting detemination is made?
Response
Insufficient information is provided to permit the Staff to answer the interrogatory.
The Staff would at a minimum need to know the purpose of the pennanent box culverts and temporary low water crossing and the relationship of this construction to the Allens Creek site and the proposed Allcns Creek Nuclear Generating Station.
NOG 33*
7008150 9 /
Interrogatory No. 2 On Page 11-11 of the Supp. to the SER, what is BTP-ETSB 11-1, and what is BTP-ETSB 11-1 (Revision 1)?
Response
BTP-ETSB 11-1 is " Branch Technical Position - Effluent Treatment System Branch - Number 11-1."
The title as stated on page 11-7 of Supplement No. 2 to the Safety Evaluation Report is:
" Design Guidance for Radioactive Waste Management Systems In-stalled in Light Water Cooled Nuclear Power Plants."
Revision 1 dated November 24, 1975 was issued as a part of, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Pcwer Plants," NUREG-75/087, dated September 1975.
NUREG-75/087 can be ordered from the National Technical Information Service, Springfield, Virginia, 22161 as an individual item or a standing order basis.
BTP-ETSB 11-1 was the original version used for guidance of Staff reviewers prior to publication of NUREG-75/087. A copy of Revision 1, which was used for the Allens Creek review, is enclosed for your convenience.
G u Gt:tJ S 9 J nterroga to_ry fio. 3 On Page 4-4 of the Supp. #2 to SER, in section 2.4.2, it says the need for a " pron.pt relief trip system" will be eliminated by the modifications of the fast scram system.
Does this mean Applicant will not be required to provide a recirculation pump trip feature to mitigate the effects of ATW?
Response
No. As noted in Section 15.2 of Supplement fio. 2 to the Safety Evaluation Report one of the piant modifications d'iscussed in fiUREG-0460 is an anticipated transients without scram recirculation pump trip.
If included in the ATWS generic resolution this feature will be required for Allens Creek, As noted in Section 4.2.2 of Supplement flo. 2 to the Safety Evaluation Report, the fast scram system will insert reactivity at a much higher rate than the unmodified scram system and at a rate ccmparable to the combined negative reactivity insertion rates of the unmodified scram system and the prompt relief trip system which was proposed before the fast scram system was proposed.
Both prompt relief trip and fast scram are means of increasing the rate of negative reactivity insertion near the end of core life when the control rods have to travel an increased distance to effect scram.
Interrogatory No. 4 Has Applicant provided any proof that, "the minimum suppression pool volume, without upper pool dump, provides adequate heat sink capability for any combination and sequence of blowdown energy and decay heat energy?"
306333
Response
The Applicant in Section 6.2.1.3 of the PSAR has provided extensive discussions regarding the short term capability of the minimum suppression pool volume to limit containment pressures and suppression pool temperatures for a variety of combinations and sequence of blowdown energy and decay heat energy. A3 stated in Section 6.2.1 (1) of Supplement tio. 2 to the Safety Evaluation Report we (the flRC Staff) find the Applicant's comnitments for further analytical modeling to be acceptable.
In the long term after blowdown an active heat remeval system is required to remove decay heat from the suppres-sion pool, i.e., the residual heat removal system.
The Applicant's provisions for long term responses are described and found acceptable in Section 6.2.1 (2) of Supplement flo. 2 to the Safety Evaluation Report.
Upper pool dump replaces water withdrawn from the suppression pool and retained within the drywell.
Interroga tnry flo. 5 If "yes" to #4 (above) please provide the document (s) or state their identi-fication number so they may be provided by Applicant.
Response
PSAR and SER, including Supplements 1 and 2.
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i BRANCH TECid! CAL FOSITION - ETSB NO.11-1 (Rev. 1) g Design Guidance for Radioactive Waste Managtsent Sy s t er +s d
6 Installed in Light-Water-Cooled Nuclear Fower Reactor Plants
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p_ackground An aspect of nuclear power plant operation is the control and management of liquid, gaseous
.W and solid radioactive waste generated as a byproduct of nuclear power. We have established C
acceptable design guidance, seismic and quality group classificatiens, and quality assurance provisions for radioactive waste management systems including stean gcnerator blowdown
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systems. For the purpose of this position papor, the radioactise waste management systems
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are considered to tegin at the interface valves (s) in each 'line frun ether systems provided for collecting ustes that may contain radioactive materials and to terminate at the point a
J of controlled discharge to the environrent, at the point of recycle back to storage for reuse
.(*d in the reactor, er at the point of storage of packaged solid' wastes prior to shipment offsite to a licensed burial grcund. The steam generator blo.s h n systen tegins at, but does not include, the cuttrcost containnent isolation valve on the blcado.vn line and termi-
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nates at the point of contrulled discharge to the envircranent, at the point of interface
~ ~l with other liquid waste systers, or at the point of recycle bach to the secondary systen.
Except as noted below the positions set forth in this, paper do not apply to the reactor n
coolant cleanup system, the ccndensate cleanup system, the ctemical and volume control systen, surps and floor drains provided for collecting liquid wastes, the boron recovery system, building ventilation systcms (heating, ventilating and air conditioning) and chemical fuae hood exhaust systems. Positions set forth in this paper regarding provisions to control releases of radioactive materials in liquids due to tank ovcrflows apply to all plant systems,
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outside reactor containment, Laving the potential to incur such releases.
The design and construction of radioactive waste managerent ar.d steam gener ator blowdown systems should provide assurar ce that radiation exposures to operating personnel and to the general public are maintained at low and acceptable levels, by assuring that these systems are designed to quality stand 1rds conducive to increasing system reliability, operability, and availability. In develcprent of this design guidance, the NRC staff has reviewed a number of designs and conce,;ts sutanitted in license applications and cperating systen his-a tories. The NRC staf f has Leen guided by current industry practices and the cost of design
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features, taking in accout,t the potential impact on the health and safety of operating per-sonnel and the general public.
64 The design guidance given in this position paper provides reasonable assurance that equip-ment and cooponents used in the radioactive waste management and bio;down systems are designed, constructed, installed and tested on a level comensurate witn the health and NRedioactive waste used in this gm de means liquid, gaseous, or solids containing radioactive
+aterial resultinq f rom cperation of a LWR which by design or operating practice may be or e 'j d
> 11 te processed prior to final disposition.
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safety of the public ard plant eterating personnel. Instrurtntation and controls associated with the waste rianagv ent ard bloaduwn systera stolid te designed to a cuality cccrensurate with their intended function.
This position paper sets f orth niniurli t, ranch requirrents ard is nnt intendtd to prohibit the inpler(ntation of other (r;uivalent design codes, standards, or quality assurarce reasures N
than those indicated herein.
5 In addition to the de'.1',n gaidirce givcn for radwaste systems, reccm endations are given for provisions to preclude tne inadverter.t r elease of radioactive materials in liquids due to spills or overficws frcm Loth raJwaste and non-radwaste systo tanks located inside or outside of plant structures.
==
B.
[ ranch Technical Positicn.
I.
Systems Handling Pidioictive Materials in Liquids r
a.
1le liquid rad..aste treatcent system, including the stcan generator blowdown system downstream of tu second containment isolation valve shculd reet the following criteria:
(1) The systas sFeuld be designed and tested in accorcance with the codes and standards listcd in Table I, to include the provisions in (2) telow and in Section IV of this position paper.
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(2) Materials f or pressure retaining cor ponents should conforn to the requiremcnts of one of the specifications for raterials listed in Section II of the ASME Boller and Pressure Vessel Cede, except that malleable, wrought, cr cast-iron mterials and plastic pipe should not t>e used. Manufacturer's material certificates of conferrance with r.aterial specifications may te provided in lieu of certified mater.ials test reports.
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(3) Foundaticns and adjacent walls of structures that house the liquid radaaste g
system shculd be designed to the seismic criteria described in Secticr V A.,' '
to a height suf ficient to contain the liquid inventory in the building.
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(4) Equipment and cor ponents used to collect, process, and store liquid radio-L-.
active waste need not be designed to the seismic :riteria given in Section V.
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b.
All tanks located cutside reactor containment and centaining radioactive rraterials h
in liquids should be designed to prevent uncontrolltj releases of radioactive raterials
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due to spillage in tuildings or from outdoor storage tarks. The following design n'
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features should be ir.cluded for tank! that may contair radioactive materials:
1.
(1) All tanks, both inside and outside the plant including the condensate storage tank (s) should have provisions to rnonitor liquid levels and to alarn potential y
overflow conditiens.
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l (2) All tanks should have ove: flows, drains, and sample lines should be routed
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to the liquid radwaste treatment system.N mari b --
(3) Indoor tanks should have curbs or elevated thresholds with floor drains routed to the liquid ra w ste treatment system.1/
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(4) Outdoor tanks should have a dike or retention pond capable of preventing run-
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off in the event of a tank overflow and have provisions for sanpling collected a.,
a liquids and routing them to the liquid radwaste treatment system.
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Gaseous Radioactive Waste (Radwaste) System
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The gaseous rad <aste treatment system, including systems provided for treatment
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of normal of f gas releases f rom the main condenser vacuum system f or a EWR and p['*i
.A for the treatment uf gases stripped from the primary coolant for a PWR should meet the following criteria:
'*h e4 (1) The systers should be designed and tested in accordance with the codes and standards listed in Table 1, to include the provisions in (2) below and in s- !.
M Section lv cf this position paper.
(2) Materials for pressure retaining conponents should CGnform to the require-ments of one of the specifications for traterials listed in Section II of the ASME Coiler and Pressure Vessel Ccde except that malleable, wrought, Or I
cast iron reattrials and plastic ripe should not be used. Manufacturer's d
material certificates of conforr.ance with material specifications may be provided in lieu of certified materials ttst reports.
c.e n'A (3) Those portions of the gaseous rcdwaste treat:.ient system which by design are i
intended to store or delay the release of gaseous radioactive waste, including fortions of structures housing these systems si,culd Le designed to the seismic desigt criteria given in Section V of this pcsition paper, for systems that normally operate at pressure ato.e 1.5 atmospheres (absolute),
this should it.clude isolation valves, equipmer.t, interconnecting piping, and 4*
components located between the upstream and dow.cstream valves used to isolate s
these compor.ents from the rest of the system (e.g., waste gas storage tanks in a WR). Fur systems that operate near an.bicnt pressure and retain gases on charcoal adsorbers, only the tank elements and the building housing the tanks are tu.luded (e.g., charcoal delay tanks in a EWR).
III.
Solid Radioactive Waste (Radwaste) System n
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a.
De solid rad aste system consists nf slurry waste collection and settling tanks, spent resin storage tanks, phase separators, and tanks, equipment, and components Retention by an intermediate su.p or drain tank, designed for handling radioactive materials j
and eaving provisions for routing to the liquid radwaste systea, is accer table.
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used to solidify wastes prior to offsite rhipment. The solid radwaste hardling and treatnent systm should r:cet the following criteria:
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..y (1) !te system shculd Le designed and tr%ted in actorJ nce with the codes and standaids listrJ in Table I to include the provisions in (2) belos and in Section IV of this paper.
t (2) Materials for pr essure retaining cor ronents should conf ra to the requirce.ents of one of the srecifications for r:atrrials listed in Section II of the ASME Boiler and fressure Vessel Code except that malleable, wrought, or cast iron materials and plastic pipe should not te used. r'anufac turer's rna terial certificates of confortance with traterial specifications may be provided in lieu of certifico materials test reports.
v.
. :e (3) Foundations and adjacent walls of structures that house the solid radwaste f, l.,.
system should be designed to the seismic criteria given in Section V of this l
position paper to a height sufficient to contain the liquid inventory in the building.
(4) Equipmcnt and ccmponents used to collect, process or store solid radioactive waste need not t:e designed to seismic criteria referenced above.
IV.
Additional Design, Construct.on, and Testing Criteria b
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In addition to tre requitteents inherent in the codes and standards li ted in Table 1, k.
r the following criteria, as minimum, should be implemented for conponents end systems T
considered in this guide.
i-a.
The Quality Assurance provisions descrited in VI of LMS guide should be applied.
b.
Pressure retaining cu ponents of process systems should utilize welded construction to the maximum practicable extent. Process piping systens include the first root r
valve on sarple instrument lines. Flanged joints or suitable rapid disconnect
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fittings shoult
. sed only where mintenance or o[erationa' requirerents clearly
$7 5Lb indicate that t.ch construction is preferable. Scrcwed connections in which threads p? c.
s provide the only seal should not te used except for instrumentation connections
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where welded connections are not suitable. Process lires should not te less than 3/4-inch. Screwed connections Lacned up by seal welding, socket welding or rechanical 7 '.
Y joints may t e used on lines 3/4-inch or greater, but less than 21/2-inch, ncminal r.
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size. For lines 21/2-inch nominal size and above, pt;e welds should te of the L*
butt-joint type. Backing rings should not be used in lines carrying resins or 7.'
other particulate material. All welding constitutirg the pressure boundary of pressure retainirg cor ponents should be performed in accordance with ASME Pressure L.
- and Vessel Code Section IX.
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Completed process systems should be pressure tested to the c.axinum practicable a
extent. Piping systems should be hydrostatically tested in their entirety except '
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at stnospheric tank ccnnections where no isolation valves exist. Testing of piping systems should be performed in accordance with applicable ASME or ANSI codes, a
yaS but in nc :ase less than 75 psig. The test pressure should be held for a minimum of 30 minutes with no leakage indicated. Testing provisions should be incorporated J
to enable periodic evaluition of the operability and required functional aerformance of active conponents of the system.
- -j V.
Seismic Design Requirements for Radioactive Waste Management Systems and Structures
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Housing Radioactive Waste Management Systems
.. q, Seismic Design Requirements Gaseous Radioactive Waste Management Systemsb, y
a.
' 'j (1) for the evaluation of rupport elements in the gaseous waste system, a M
simplified seiwiic analysis procedure to detemine seismic loads may be used.
t The sireplified proccdure consists of consideration of the system as a single degree of freedua systen and picking up a seismic response value from applicable i
floor response s;ectra, once the fundamental frequency of the system is j's$
determined. The floor response spectra should be cbta umd analytically (Section V.b) from the application of Regulatory Guide 1.60 design response gb spectra normalized to OEE level maximum ground acceleration at the foundation q
of the building housing the gaseous radw3ste system.
d (2) The allowable stresses to be used for the system support elements should be a
those given in the AISC Manual of Steel Construction, 7th edition 1970, including the one-third allowable stress increase provision for load combina-w
. j tions involving tarthquake loads. For design of concrete foundations of the system, where applicable, use of the ACI 318-71 code with one-third increase in allowable stress for seismic loads is acceptable.
(3) The construction and inspection requirements for the suppcrt elements should comply with thcse stipulated in AISC or ACI Codes as appropriate.
1
.Q, b.
Seismic Design Requircments for Buildings Housing Radwaste Systems
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..m (1) Define input motion at the foundation of the building housing the radwaste systems. The muticn should be defired by normalizing the Regulatory Guide 1.60 spectra to the lit maximum grcund acceleration selected for the plant.
U or which seismic capabilities are required in Section II(3).
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A simplified analysis should be pu formed to determine appropriate seismic 6
loads and floor response spectra pertinent to the location of the systcms; 3
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i.e., an analysis of the t;uilding t y a "several degrces of freedom" mathe-matical mcdel and the use of an an roxiute "ethod to generate the floor response spectra for radwaste systems and the seismic loads for the buildings.
h No tine history or dynamic analysis is required.
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(2) The sir;)l'ified method for deten-ination of seis*ic loads for the building consists of (a) calculation of first several i cdal frequencies and participation factors for the building (b) determination of rodal seismic loads by item (1) input spectra, and (c) c'rbination of rodal seismic loads by the square root of the sum of squares (SRSS) rule.
(3) With regard to generation of floor response spectra for radwaste syst('s, snethods such as the Biggs or other equivalent procedures which give
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approximate floor response spectra without need for performing a tin e history analysis ray be used.
(4) The load factors and load con 1binations to be used for the building should be those given in the ACI-318-71 Code. The allcaable stresses for steel components should be those given in the AISC Manual of Steel Construction, 7th edition, m
1970.
- i.1 v.
(5) The construction and inspection require ents for the building elenents should comply with those stipulated in the AISC or ACI Code as appropriate.
b*
- r (6) The foundation media of structures housing the radwaste systems should-not liquify during the Operating Casis Earthquake.
t c.
In lieu of the requirements and procedures defined above, optional shield structures j
constructed around and supporting the radwaste systm s may be erected to protect I'
the raduaste systems fron effects of housing structural failure. If this option r
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is adopted, the procedures described in Section V.b only need to be applied to N'"
the shield structures while treating the rest of the housing structures as non-i' seismic Category I.
V s v-y, VI.
Quality Assurance for Radioactive Waste Management Systers F^
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b;-
A quality assurance frcgram should be established that is sufficient to assure that the
't-design, construction, and testing requirements are met. The quality assurance program h'
U should include the following:
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Design and Procurcrent Document Control - Measures should be estaS ished to insure a.
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that the requirements of this position paper are specified and included in design and
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procurement documents and that deviations therefrom are controlled.
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Control of Purchased Paterial, Equipcent and Services - Measures snould be g
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established to assure that purchased material, equipment and construction services conform to the procurer..ent documents.
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c.
Inspectian - A program for inspecticn of activities affecting quality should be j
established and executed by, or for, the organization performing the activity
'l to verify conformance with the documented instructions, procedures, and drawings
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for accor.plishing the activity.
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d.
llandling, Storage, and Shipping - M asures should be established to ccntrol the
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handling, storage, shipping, cleaning and preservation of material and equipment in accord 5nce with work and inspection instructions to prevent damage or
'. e deterioration.
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Inspection Test and Operating Status - Measures should be established to provide for the identification of itens which have satisfactorily passed required
- 1 inspections anJ tests.
J f.
Corrective Action - Measur(s should te established to assure tha t conditions adverse to qc 'ity, such 35 failures, malfunctions, dpficiencies, deviations, defective raterial and eaaigracnt and nonconfonr.ances are pruT ptly ider.tified and corrected.
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EQUIEMENT C00ES
.g EQUIPMENT CODES
- e Welder Qualifications Inspection Design and g
Fabrication Materials and Procedure And Tostina Pressure Vessels ASME Code A5ME Code ASME Code ASME Coie Secticn VIII. Div. 1 Secticn II Section IX Section '.'III, Di v.
1 IN IN ASME Code (3)
ASME Code AS"E Code ASME Ccde E
Atmospheric or O
0-15 psig tanksSection III, Section II section IX section III, P
Class 3, or API 620 &
Class 3 or API 620; 653 Ar.!A D-lC0 Q
650, AVJA D-10C
,L, qg Heat Exchanger ASME Code ASME Code ASME Code ASME Code Section VIII, Div. 1 Section III Section IX Secticn VIII, Div.~1
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and TEMA m
Piping and Valves ANSI 31.1 ASTM or ASME Code ANSI B 31.1 AS"E Code Section IX Section II I3)
II)
AS"E Code ASME Code ASME Pumps Manu f actu re r's Standards Section !! or Section IX Section III Manufacturer's (as required)
Class 3; or Standard Hydrealic Institute Notes:
(1) Manufacturer's standard for the intended service. Hydrotesting should be 1.5 times the design pressure.
(2) Material Manufacturer's certified test reports should be obtained whenever possible.
(3) ASME Code Stamp and naterial traceability,not required.
(4) Fiberglass reinforced plastic tanks may be used in accordance with Part M. Section 10, ASME Boiler and Pressure Vessel Code, for applications at ambient temperature.
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UNITED STATES OF AMERICA NUCLEAR REGULATORY C0i4MISSI0tl BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
HOUSTON LIGHTING & POWER COMPANY
)
Docket No. 50-466
)
(Allens Creek Nuclear Generating
)
Station, Unit 1)
)
AFFIDAVITS OF P,ICHARD W. FROELICH AND CALVIN W. M000N Richard W. Froelich and Calvin W. Moon depose and say under oath:
1.
I, Richard W. Froelich, am the NRC Staff's Environmental Project Manager assigned to the application for a construction permit for the Allens Creek Nuclear Generating Station, Unit 1.
~
2.
I, Calvin W. Moon, am the NRC Staff's Licensing Project Manager for the above application.
3.
The foregoing NRC Staff responses to interrogatories propounded by John F. Doherty were prepared by us or under our direct supervision.
We certify that the answers given are true and correct to the best of our know-lec'ge, information and belief.
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Richard W. Froelich bdt.A.-
N ov' Calvin W. Moon
. Subscribed and sworn to before me this /6t'- day of' %,1979.
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Notary Publ,ic' My Commission expires: _h /~
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSI0ft BEFORE THE ATOMIC SAFETY AND LICENSIf!G BOARD In the Matter of
)
)
HOUSTON LIGHTIfiG & POWER COMPANY
)
Docket No.
50-466
)
(Allens Creek Nuclear Generating
)
Station, Unit 1)
)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF'S RESPONSES TO JOHN F. DOHERTY'S THIRD SET OF INTERROGATORIES" in.the above-captioned proceeding have been served on the following by deposit in the United States mail, first class, or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Commission's internal mail system, this 16th day of July, 1979:
Sheldon J. Wolfe, Esq., Chairman
- Jack Newman, Esq.
Atomic Safety and Licensing Lowenstein, Reis, flewman & Axelrad~
Board Panel 1025 Connecticut Avenue, fl.W.
U.S. fluclear Reaulatory Connission Washington, D. C.
20037 Washington, D. C.
20555 Richard Lowerre, Esq.
Dr. E. Leonard Cheatun Asst. Attorney General for the Route 3, Box 350A State of Texas Watkinsville, Georgia 30677 P. O. Box 12548 Capitol Station Mr. Gustave A. Linenberger Austin, Texas 78711 Atomic Safety and Licensing Board Panel Hon. Jerry Sliva, Mayor U.S. fluclear Regulatory Commission City of Wallis, Texas 77485 Washington, D. C.
20555 Hon. John R. flikeska R. Gordon Gooch, Esq.
Austin County Judge Baker & Botts P. O. Box 310 1701 Pennsylvania Avenue, fl.W.
Bellville, Texas 77418 Washington, D. C.
20006 Atomic Safety and Licensing J. Gregory Copeland, Esq.
Appeal Board
- Baker & Botts U.S. fiuclear Requiatory Commission One Shell Plaza Washington, D. C.
20555 Houston, Texas 77002 1
56C346
. Atomic Safety and Licensing Carro Hinderstein 8739 Link Terrace Board Panel
- U.S. Nuclear Regulatory Coanission Houston, Texas 77025 Washington, DC 20555 Docketing and Service Section
- Texas Public Interest Office of the Secretary Research Group, Inc.
U.S. Nuclear Regulatory Commission c/o James Scott, Jr., Esq.
Washington, DC 20555 8302 Albacore Houston, Texas 77074 Mr. John F. Doherty 4438 1/2 Leeland Avenue Brenda A. McCorkle Houston, Texas 77023 6140 Darnell Houston, Texas 77074 Mr. and Mrs. Robert S. Framson Mr. Wayne Rentfro 4822 Waynesboro Drive Houston, Texas 77035 P.O. Box 1335 Rosenberg, Texas 77471 Mr. F. H. Potthoff, III 1814 Pine Village Ms. Kathryn Hooker Houston, Texas 77080 1424 Kipling Houston, Texas 77006 D. Marrack 420 Mulberry Lane National Lawyers Guild Bellaire, Texas 77401 Houston Chapter 4803 Montrose Blvd.
Mr. Jean-Claude De Bremaecker Suite 11 2128 Addison Houston, Texas 77006 Houston, Texas 77030 Mrs. Karen L. Stade Jonathan Kamras P.O. Box 395 1901 S. Voss Rd., #7 Guy, Texas 77444 Houston, Texas 77057 Jon D. Pittman, Sr.
Gayle De Gregori 2311 Bamore 2327 Goldsmith Rosenberg, Texas 77471 Houston, Texas 77030 Mrs. W. S. Cleaves 8141 Joplin Street Houston, Texas 77017 Vesta Eidman 1117 River Bend Drive 1
Houston, Texas 77063 J'J_ '~
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