ML20090L215

Forwards Ebasco & Harstead Engineering Assoc Npis Wall Hairline Crack Evaluation. Rept Concludes That Cracks Are Drying Shrinkage Cracks & Not Result of Loading Mechanism. Related Correspondence

ML20090L215
Person / Time
Site:	Waterford
Issue date:	05/24/1984
From:	Blake E LOUISIANA POWER & LIGHT CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Johnson W, Kohl C, Wilber H NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
References
NUDOCS 8405250247
Download: ML20090L215 (74)

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(202) 822-1084 Christine N. Kohl W. Reed Johnson Administrative Judge Administative Judge Chairman, Atomic Safety and Atomic Safety and Licensing Appeal Board Licensing Appeal Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Howard A. Wilber Administrative Judge Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of Louisiana Power & Light Company (Waterford Steam Electric Station, Unit 3)

Docket No. 50-382

Dear Chairman Kohl and Judges Johnson and Wilber:

I enclose for the information of the Appeal Board and parties copies of two reports that were recently provided to NRC Staff by Applicant. These two reports deal with vertical surface cracking of concrete at Waterford 3.

Vertical cracking has been evaluated because of its potential relationship to basemat cracking which is the subject j of NRC review and of a pending motion to reopen in this pro-ceeding. Both reports (by Ebasco Services Incorporated and Harstead Engineering Associates) conclude that the hairline cracks observed on vertical surfaces are drying shrinkage 8405250247 840524 PDR ADOCK 05000392 9_ PDR S03

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- ,: SH w, PiTTMAN.'PoTTs & TROWERIDGE A PARTheERSwer Cp pmOFESSecesAL CompomAftO88S Administrative Judges Atomic' Safety and Licensing Appeal Board

.May'24, 1984 Page Two cracks and not the result of any loading mechanism, and that a structural interrelationship cannot be established between cracks on surfaces of wall and basemat.

Sincerely, Y. $& ((<

Ernest L. Blake, Jr., P.C.

Counsel to Applicant Enclosures cc: Service List a

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May 16, 1984 W3P84-1391 3-Al.16.07 Director of Nuclear Reactor Regulation Attention: Mr. G.W. Knighton, Chief fy (_ g D] ,,3

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f Licensing Branch No. 3 f' 's ~p Y

Division of Licensing U.S. Nuc'. ear Regulatory Commission j

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SUBJECT:

Waterford 3 SES Docket No. 50-382 k $,P.P. "

/p Additional Information on NPIS Basemat Cracks "X'/ f I ;G

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Dear Sir:

A technical review meeting was held on March 26, 1984 in Bethesda, Md. to discuss the Nuclear Plant Island Structure Basemat and the hairline cracks observed in the top of the basemat. This meeting was continued on March 27, 1984 at the Waterford 3 site. During the site tour a number of hairline cracks were observed on the vertical surfaces of the ring wall and cooling tower storage pool wall.

LP&L agreed at the meeting to mapping of the vertical cracks and to initiate a review by Ebasco and Harstead Engineering Associates (HEA) to develop conclusions as to the origin of the hairline cracks and their significance to, or interrelationship with, the basemat cracks.

Following the meeting, Ebasco was instructed to prepare maps showing the location of the vertical hairline cracks and to evaluate the significance.

This ceport, Attacht::ent I, was transmitted to HEA for their subsequent review and development of an independent position on the significance of the hairline cracks. The HEA report is included as Attachment II.

l Both Ebasco and HEA have concluded that the hairline cracks on the vertical l surf aces are drying shrinkage cracks and not a result of any loading i

mechanism. The conclusion is "...it is concluded that a structural inter-relationship cannot be established bet. ween cracks on surfaces of wall and basemat."

If you have any questions concerning the attached report, please contact me.

l Yours very truly, K. W. Cook Nuclear Support & Licensing Manager

e s cc: E.L. Blake,'W.M. Stevenson, J.T. Collins, D.M. Crutchfiel'd, J. Wilson G.L. Constable h

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. WATERFORD STEAM ELECTRIC STATION UNIT No.3 1 NPIS WALL HAIRLINE CRACKS EVALUATION PREPARED BY: P C LIU/N HASAN REVIEWED BY: A H WERN APPROVED BY: J L EHASZ APRIL 1984 EBASCO SERVICES INCORPORATED 2 WORLD TRADE CENTER NEW YORK, N.Y. 10048

. 3 LOUISIANA POWER AND LIGHT COMPANY WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 .

NPIS WALL HAIRLINE CRACK EVALUATION TABLE OF CONTENTS PAGE 1.0 PURPOSE 1 2.0 SCOPE 1

3.0 CONCLUSION

S 1

4.0 BACKGROUND

2 5.0 DISCUSSION 3 5.1 CURVATURE OF BASEMAT 3 5.2 HAIRLINE CRACKS IN BASEMAT 4 5.3 HAIRLINE CRACKS IN WALLS OF NPIS S 5.4 INTER-RELATIONSHIP OF HAIRLINE CRACKS 6 REFERENCES 8 FIGURE 1 _BASEMAT PLACEMENT SEQUENCE AND DIFFERENTIAL SETTLEMENT CONTOURS FIGURE 2 BASEMAT CURVATURE FIGURE 3 PLAN OF NPIS MAPPED WALLS j APPENDIX "A" WALL HAIRLINE CRACK MAPPING PROCEDURE I

APPENDIX "B" WALL CRACK MAPS APPENDIX "C" COMPOSITE ISOMETRIC WALL AND MAT CRACK MAPS

- APPENDIX "D" PHOTOGRAPHS G

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LOUISIANA POWER AND LIGHT COMPAlW WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 -

NPIS WALL HAIRLINE CRACKS EVALUATION

1. 0 PURPOSE The purpose of this report is to document the presence cf hairline cracks in the walls of the Nuclear Plant Island Structure (NPIS) of Waterford SES Unit No. 3 and to provide an engineering evaluation related to basemat settlement.

The investigation and mapping of the cracks was performed during the week of April 2, 1984 at the request of NRC staff during their site visit on March 27,1984.

2.0 SCOPE This report covers the investigation and mapping of hairline cracks in the exposed wall surfaces in the areas between Reactor Building ano Wet and Dry Cooling Towers, and between Reactor Building and Reactor Auxiliary Buildings of NPIS. The mapping covers areas f rom top of basemat and extending to ten (10) feet above El. - 35.0 f t. .

All visible hairline c acks are l ocated and identified, areas of wetness or leachate are documented, width and spacing pattern of cracks and possible causes to their formation are reviewed and significance. of these c racks, including inter-relationship with cracks in basemat is evaluated.

3.0 CONCLUSION

S The investigation and mapping of the cracks in the exposed walls of -NP15, from top of basemat to ten (10) feet above El-35.0 ft, leads to the following conclusions:

1. All cracks are extremely fine and ' identified as " hairline cracks",

varying f rom hardly_ visible to .less than 5 mils in width.

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2. The cracks are randomly distributed and mostly oriented in a vertical direction. These cracks are superficial shrinkage cracks, formed during construction, and are considered structurally ins'ignificant.

3. No inter-relationship between the walls and basemat hairline cracks

. appears to exist. In localized areas of the Reactor Building and East and West Cooling Towers some small inter-relationship between these cracks may exist , as a local phenomenon,but the proximity of these cracks could also be coincidental, 4.0 BACKGRN[{D The NPIS, which consists of Reactor Building, Reactor Auxiliary Building, Fuel Handling Building and the Essential Cooling System Structures are erected on a 12-f t. thick, 380 ft. by 276 ft. reinforced concrete foundation mat. The bottom of the mat is located at El.-47.0 f t which is approximately 64 f t. below final grade. The normal ground water level is at El. 8.0 ft.

l l Because of the foundation soils and to minimize the differential settlement between structures a common foundation mat was selected and compensated f oundation principle was utilized in the design of NPIS.

i According to this principle, the net soil pressure under the common mat is n.o greater than.the existing natural soil pressure, ie, the weight of the combined structure applies an effective load to the bearing stratum equivalent to the originally-existing overburden pressure.

The entire common foundation mat was constructed following a checker

~ board sequence consisting of 28 block placementi, over a period of six (6) months. Figure 1 shows the sequence of base.,at block placement with .

dates. l I

During construction, small differential settlements beneath various areas of the mat were expected due to small variations in the underlying soils and small nonuniformities in the loading due to the construction sequence.

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. o Foundation mat settlement was carefully monitored to assume that settlement during construction of the plant was relatively uniform across

, J the entire mat and that no significant relative movement occurred.

5.0 DISCUSSION 5.1 CURVATURE OF BASEMAT The mat curvature resulted from a complex series of events involving the placement of the concrete mat and the scheduling of concrete placement for the superstructure as well as control of dewatering system and monitoring of sub-soil conditions.

The construction of the mat was such that the blocks located beneath the Reactor Building were placed first and then the blocks away from the Reactor Building were placed subsequently. The subsoils beneath the mat in the area which was placed first had started their consolidation process slightly earlier as compared to the areas which were placed later. The lag in the starting of the consolidation introduced part of the differential settlement creating the convex shape.

The convex shape was observed both in E-W and N-S direction, with the curvature being made pronounced in N-S direction. Figure 2 shows a generized curvature of basemat in N-S direction at 3 key construction stages.

t In April 1976, just prior to construction of Reactor Building shield wall the maximum curvature of the basemat in N-S direction was such that the center was 1 inch to 1 1/4 inches higher that the extreme edges of the mat. (At this time portions of the' base mat, ie, block Nos. 15, 16, 17, 18 and 19 were not placed),

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In June 1976, af ter the completion of Reactor Building shield wall and l the remaining mat concrete, there was a slight reduction in the maximum curvature beneath the shield wall area, and resulted in a decrease of L over-all dif ferential settlement.

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I With additional loads added by NPIS concrete and recharging of water table, the settlement process continued, however, the mat maintained its general convex shape with only minor curvature readjustment. . Ihe mat settlement process stabilized with completion of NPIS concrete and ground water table restored to normal condition in mid 1979. Since then, no further significant net or differential settlement has occurred.

5.2 HAIRLINE CRACKS IN BASEMAT The initial detection of hairline cracks in basemat was made in mid-1977 via Non-Conformance Report NCR W3-535, as the concrete surface under the Reactor Building was cleaned up and prepared for concrete fill placement. Then microscopic cracks were identified by weeping of water

. at a rate just enough to moisten the surrounding concrete. Subsequently, a crack map was prepared and the crack widths were observed to be between 2 and 5 mils.

An effort to repair these crachs with an injection of epoxy grout, using a maximum pressure of 180 psi, was unsuccessful, which indicated that these cracks were too small to be grouted.

In May 1963, additional hairline cracks in the basemat of the Reactor Auxiliary Building were also reported via NCR W3-6212. These microscopic cracks, similar to those detected earlier in 1977, were identified chrough presence of moisture.

In September,1983 a detailed mat hairline crack mapping was perforued (Reference 1), the results indicated the crack pattern follows generally the pattern of mat differential settlement. Since the contours of differential settlement show a pronounced greater convexity in the N-S direction than in the E-W, the general crack pattern lies E-W reflecting these convexities.

4

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5.3 HAIRLINE CRACKS IN WALLS OF NPIS 4

Base Ring of Reactor Building Shield Wall -

Surf ace hairline cracks in the base ring wall the Reactor Building were observed and reported in March 1976 (References 2&3).

The base ring wall is 10 f t thick and 17'-2 high, and was constructed in four placements. Surface hairline cracks were found to be vertically oriented and randomly distributed on both the interior and exterior surfaces of the ring wall. The crack width was extremely small and varied f rom hardly visible to less than 5 ails. These cracks were evaluated to be chrinkage cracks, since they existed on the surface and not beyond the reinforcing steel.

Walls in Other Areas

, Surf ace hairline cracks in other walls areas had been noticed during construction. No detailed documentation was made because they were all considered to be shrinkage cracks.

i A detailed mapping of the wall hairline cracks of the NPl$ was performed i

during the week of April 2,1984, in' accordance with a prescribed mapping procedure (Appendix A). The mapping was conducted for all accessible and exposed walls at the interf ace with and up to 10 f t above the top of the basemat El-3 5.0 f t. The results of wall hairline crack maps are presented in Appendix B. A plan of the mapped walls is presented in 1

Figure 3. - For photographs of cracks, see Appendix "D".

Based Don the results of- the mapping, the following observations were made:

1. Crack Width - All: cracks are extremely fine and vary f rom hardly

-visible to less than 5 mils. Their-visibility is enhanced by, and in 'some cases the only witness to their presence is, the: presence pf moisture and/or

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2. Crack Orientation - The cracks are mostly oriented in a vertical direction.

3. Crack Distribution - The cracks are randomly distributed.

4 Crack Wetness - No ' cracks were found to have surface wetness except cracks in Wet Cooling Tower walls.

(Leachate deposits on Reactor Building ring wall were found to be dry)

5. Leachate Deposit - Large leachate deposits are found in two specific areas, Reactor Building ring wall below El.-18.0 f t and walls of Wet Cooling Towers. In both these areas leachate deposit extend to the basemat.

The Reactor Building leachate was found to be dry signifying the source of moisture causing it causing it has been eliminated.

s Leachate accumulations on the ring wall were caused by long term ponding of rain and construction water at the top of ring wall. Seepage of water was also facilitated by open pipe sleeves (El-18.0 f t) which were interconnected with the embedded structural steel system used as temporary support during construction.

l Leachate accumulations on the Wet Cooling Tower walls was apparently caused by seepage of water from the cooling tower basins (water level at - 9.0 f t).

5.4 INTER-RELATIONSHIP OF HAIRLINE CRACKS Composite isometric maps (Appendix C) have been prepared to show the i relative location and orientation of all identified cracks at the basemat/lall interface.

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1. Hairline cracks at the interface are not generally found to be inter-connected or even closely inter-related (spacing less than two feet).

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2. Only three localized areas were found with floor and wall cracks in close proximity:

a) Reactor Building ring wall, north-east quadrant (sheet 1, Appendix C) b) Eaat Wet Cooling Tower walls (Sh 2, Appendix C) c) West Wet Cooling Tower walls (Sh 4&S', Appendix C)

Many leachate deposits on the walls extend further down the wall than the crack due to the originating moisture migrating down the wall. In assessing the inter-relationship, a conservative assumption has been made that hairline cracks are present in all leachate areas.-

Based on the above, it is concluded that a structural inter-relationship cannot be established between cracks on surfaces of walls and basemat.

The mat top surface cracks were caused mainly by flexure and they are closely related to the general convex shape of the basemat. This convex curvature would tend to introduce cracks at the top of combined structural elements (basemat plus walls), and not at the base of walls, which would be a compression zone.

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Since the wall cracks have been identified close to the base and in most areas do not extend to a great height above the top of the mat, they are most likely caused by other than basemat flexure. A likely source is shrinkage,with the mat providing great local restraint to shrinkage movement in the walls. Therefore, some inter-relationship of cracks-in the walls and basemat could exist but would be a local phenomenon, contributed by minor local basemat curvature readjustment.

7 ,

i References

1. Analysis of Cracks and Water Seepage in Foundation Mat, Waterford SES Unit 3, Report No. 8304-1 dated September 19, 1983, by Harstead Engineering Associates Inc.

2. Field Trip Report, Waterford SES Unit 3 March 22,1976 by P C Liu.

3. Memo on ' Ring Wall', WSES Unit 3, March 23,1976 by E L Boyd.

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8 see sheet 8, Appendix B PL AM . AT EL '55.00' cair 44,fe4 WATERFORD SES UNIT NO. 3 Figure 3 PLAN OF NPIS MAPPED WALLS ESASCO SERVICES INCORPORATED ,

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APPENDIA "A" WALL HAIRLINE CRACK MAPPIhG PROCEDURE l

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EBASCO interoffice correspondence DATE 3/30/84 FILE REF. 6Q.p-g TO B Grant OFFICE LOCATION Waterford Site RN E. S. Kowalski/P.C. Liu OFFICE LOCATION SUBJECTWATERFORD SES UNIT NO. 3 NUCLEAR PLANT ISLAND STRUCTURE WALL HAIRLINE CRACK MAPPING PROCECURE This subject procedure is attached for your use in mapping the wall hairline cracks of NPIS.

l ESK/PCL:lh Attach.

cc: J L Ehasz G A Kanakaris l _A B Wern J J Costello Project File 4

RO - March 30, 1984 LOUISIANA POWER AND LIGHT COMPANY WATERFORD SES UNIT NO. 3 i

WALL HAIRLINE CRACK MAPPING PROCEDURE

1. The exposed wall surfaces in the areas between Reactor Building and wet and dry cooling towers, and between Fuel Handling and' Reactor Auxiliary Buildings shall be visually inspected for the presence of cracks.

2. The visual inspection shall cover the areas of wall surfaces up to ten (10) ft. from the top of basemat El. -35.0 ft.

3. Location maps shall be prepared to record the results of the inspection. These maps shall be elevation views of the wall with cracks drawn on them to scale location.

4. Each location map shall include items as follows:

a. Dato

b. Inspector's name

c. Checker's name

d. Crack locations - end points and approximate paths

e. Repair evidence

f. Seepage indication

g. Dimensions of areas cover d by leabhate h.- If the crack is extended down to mat level, the distance to the near-by mat crecks (not more than two (2) ft.). >

j. 5. A. scale composite crack map shall be' developed to show the .

general pattern of cracks on walls and the.basemat..

6. The basemat crack maps which had been developed by Harstead Engineering Associates shall be utilized to l develop the composite crack map.

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7. Those.basemat crack maps utilized shall be-up-dated to include newly observed cracks, if any.

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9. Laitance shall not be removed.

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APPENDIX "B" WALL CRACK MAPS L,_

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-HARSTEAD ENGINEERING ASSOCIATES o INC.

169 KINDERKAMACK ROAD, PARK RIDGE, N.J. 07656

• Phone:(201)3912115 Project No. 8304 April 26, 1984 W3-HE-L?-015 Louisiana Power & Light Co.

Waterford III Nuclear Plant P.O. Box B Killona, LA 70066 Attn: Mr. T. Gerrets

Subject:

Naterford III SES Analysis of Cracks and Water Seepage in Foundation Review of Wall Cracking

References:

(1) HEA Report No. 8304-1 dated 9-13-83 (2) Ebasco Report NPIS Nall Hairline Cracks Evaluation, dated April 1984.

Gentlemen:

1,0 Introduction On Tuesday Acril 17, we received a copv of an Ebasco l Reoort, Reference-2 A memo from J.Costello attached to the subiect Report requested HEA review with subsequent not-ification to Louisiana Power and-Light Company. Dr. A.V.

du Bouchet of our office has reviewed the Ebasco.Raport in conjunction with a site visit (conducted with the assistance of I.Safro of Ebasco) on April 21, 1904.

2.0 Puroose t

The purpose of the site visit was to confirm the validity of the wall crack maps-generated by Ebasco (see Appendix B of the Ebasco Report) . There are a total of 28 pages of crack maps' contained in Appendix B. The location key to each of these pages is provided in Figure 3 of the Report, which details 1the locations of the concrete walls mapped by Ebasco with ' respect to the top of the NPI.C basemat at Elev. -35.00 ft.

4 L -

'$' I' 1 3.0 Site Review The following items were specifically reviewed at the site:

1. Each crack map contained in Appendix B was reviewed qualitatively for accuracy and completeness.

2. A notation was made for any wall crack spaced closer than 2 ft. to a basemat crack at the juncture of the wall and basemat.

3. Additional walls not specifically mapped by Ebasco were also reviewed to confirm the validity of the Ebasco scope of work.

With respect to Item 3, a continuous circuit was established in both the NE and NW quadrants of the basemat to verify the absence of any substantial cracking in walls not mapped by Ebasco.

4.0 Evaluation The following quantitative observations with reference to HEA Report 8304-1,. Reference 1 can be made in order to confirm the validity of the Items extracted from Sections 5.3 and 5.4 of the Ebasco Report:

1. there are a total of 146 cracks mapped by Ebasco, of which 37 are directly observable; the remaining cracks can only be-inferred from the presence of leachate;

2. there are'a total of only 19 instances in which wall and mat cracks fall within a.2:.0 ft.

dimension at the base of the mat and wall;

3. Ebasco mapped a total of approximately 700 linear feet of wall I hese dimensions were scaled directly

. from Ebasco DI wings LOU-1564-G-499 Sol, 2 and 3) ;

4. the average spacing.of observable cracks is therefore (700 ft./87 cracks) or about 8 ft. on center;

5. the average spacing of all cracks counted is therefore (700.ft./146 cracks) or about 4.8 ft. on center; L . .

L . 6.- the percentage of wall cracks interacting with basemat cracks as a function of the total number of wall cracks ?is therefore -(19x100/146) ; about

-13' percent, or aboutil in 8 cracks.

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If wa rastrict ourselves to an ovaluation of the LRatator-Bldg walls alona, wa then note that: ,

1. there are a total of 70 cracks mapped by Ebasco, of which 29 are directly observable; the remaining cracks can only be inferred from the presence of leachate;

2. there are a total of only 5 instances in which wall and mat cracks fall within a 2.0 ft, dimension at the base of the mat and wall; l

3. Ebasco mapped a total of approximately 210 linear ft.aof wall;

4. the average spacing of observable cracks is therefore (210 ft./29 cracks) or about 7.2 ft. on center;

5. the average spacing of all cracks counted is therefore (210 ft./70 cracks) or about 3.0 ft. on center;

6. the percentage of wall cracks interacting with basemat cracks as a function of the total number of wall cracks is therefore. (5x100/70) ; about 7 percent, or about 1 in 14 cracks.

5.0 Conclusions The cracks observed in the top of the foundation mat

' were discussed in detail in HEA Report 8304-1, Reference 1.

We concur with the observation that the wall cracks are drying shrinkage c

acks which form when the wall drys but is restrained from shrinking at the intersection of

~

walls with the foundation mat. In some cases there may have been a predispotion of these wall shrinkage-cracks to emanate from a pre-existing crack in the mat. However, the cracking as observed is not consistent with any possible loading mechunism.

The incidence of wall and mat crack interaction as detailed in Items 6 above'is not considered significant.

enough'to. substantiate a wall-basemat crack interaction hypothesis. We therefore concur with the key Ebasco conclusion contained in Section 5.4-of their Report which notes that: " it is concluded that-a structural inter-i relationship cannot be established between cracks on sur-faces of walls and basemat."

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In summary we concur with the obnorvations and con-clusions described of the Ebasco Report, Reference 2. '

l If we.can provide any additional information or clar-ification with respect to our review of the subject Ebasco Report, please call us.

Very truly yours, HARSTEAD ENGINEERING ASSOC., INC.

Gunnar A. Harstead President cc. J.Costello 4

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L UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION f Before-the Atomic' Safety and Licensing Appeal Board In the Matter of )

)

LOUISIANA POWER & LIGHT COMPANY ) Docket No. 50-382

)

(Waterford, Steam Electric )

l- Station, Unit 3)- )

I SERVICE LIST Christine N.' Kohl Sheldon J. Wolfe Administrative Judge . Administrative Judge Chairman, Atomic Safety and Chairman, Atomic Safety and

Licensing Appeal Board Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D . C .- 20555 t

W. Reed Johnson Harry Foreman

{,

Administrative Judge Administrative Judge Atomic Safety and Licensing Atomic Safety and Licensing j Appeal Board Board U.S. Nuclear Regulatory Commission Director, Center for Population j; Washington, D.C. 20555 Studies Box 395, Mayo Howard A. Wilber University of Minnesota Administrative Judge Minneapolis, MN 55455 Atomic Safety and Licensing-Appeal Board -Walter H. Jordan l U.S. Nuclear Regulatory-Commission Administrative Judge Washington, D.C. 20555 Atomic Safety and Licensing l- Board

Sherwin E. Turk, Esquire 881 West Outer Drive

Office of the Executive Oak Ridge, TN 37830 Legal Director L U.S. Nuclear RegulatoryLCommission Docketing & Service Section (3)

Washington,'D.C.. 20555 . Office of the Secretary i U.S. Nuclear ~ Regulatory Commission I Atomic-Safety and Licensing Washington, D.C. . 20555 i Appeal Board Panel U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C. 20555 Board Panel U.S. Nuclear Regulatory Commission' Washington, D.C. 20555 ,

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t i d LP&L 1 Service List-ASLAB Page Two P

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Mr. Gary Groesch Luke B. Fontana, Esquire 2257 Bayou Road 824 Esplanade Avenue New Orleans, LA 70119 New Orleans, LA 70116 Brian Cassidy, Esquire Spence W. Perry, Esquire Federal Emergency Management Federal Emergency Management Agency Agency Region I Office of the General Counsel 422 J. W. McCormack 500 C Street, S.W., Room 840 Boston, MA 03109 Washington, D.C. 20472 Carole H. Burstein, Esquire 445 Walnut Street New Orleans, LA 70118 l

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