ML17261A124

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Forwards Supplemental Info to Re Systematic Evaluation Program Seismic Review.Oversided Drawings Available in Central Files
ML17261A124
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/22/1979
From: White L
ROCHESTER GAS & ELECTRIC CORP.
To: Ziemann D
Office of Nuclear Reactor Regulation
References
TASK-02-04, TASK-03-06, TASK-RR NUDOCS 7905300474
Download: ML17261A124 (102)


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REGULATORY INFORMATION OISTRISUTIOTOTEM (RIOR)

ACCESSION NBR;7905300474 DOC,DATE; 79/05/22 NOTARIZED:

NO DOCKET FACIL 50 244 ROBERT EMMET GINNA NUCLEAR PLANT>> UNIT 1(

ROCHESTER G

05000244 AUTH'AME AUTHOR AFfILIATION WHITE>> L>> D>>

ROCHESTER GAS 8

ELECTRIC CORP'EC IP, NAME RECIPIENT AFFILIATION ZIEMANN>>D>>L>>

OPERATING REACTORS BRANCH 2

SUBJECT:

fORNARDS SUPPL INFO TO 790507 LTR RE SYSTEMATIC EVALUATION PROGRAM SEISM'IC REVIEN,OVERSIZE ORANINGS ENCL@

DISTRIBUTION CODEe AO 1S C PI S

RECEIVEDoLTR g ENCL Q SIZEe TITLE: GENERAL DISTRIBUTION FOR AfTER ISSUANCE Of OPERATING LIC QLL-45ES r4

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2 14 TA/EDO 15 CORE PERP BH 1

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UNITEDSTATES NUCLEAR REGULATORY COMMISS ON WASHINGTON, D. C. 20555 MEMORANDUM FOR:

TERA Corp.

FROM:

SUBJECT-US NRC/TIDC/Distribution Services Branch Special Document Handling Requirements 1.

Please use the following special distribution list for the attached document. P~ ~ 5 Q'oo(,.~

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S9 EAST AVEMUE, ROCHESTER, M.Y. 14649 LEON D. WHITE. JR.

VICC PRCSIDCNT

'TCLCP5IONC ARCh COOC 75a 546-2700 May 22, 1979 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis L. Ziemann, Chief Operat,ing Reactors Branch No.

2 U.S. Nuclear Regulatory Commission Hashington, D.C.

20555

Subject:

Systematic Evaluation Program Seismic Review R.E.

Ginna Nuclear Power Plant Docket 'No. 50-244

Dear Mr. niemann:

During the site visit by the NRC Seismic Review Team, members of the Team requested

that, we provide additional information on the design and construction of Ginna Station.

By letter dated May 7, 1979 we provided some of the requested information.

The enclosures to this letter provide additional information.

The items which are addressed and an index to the enclosures is as follows:

b.

c ~

d.

e.f.

go Seismic Anal sis and Desi n Criteria The following information provides responses to functions in item I e Calculations of fundamental frequency of containment internal concrete structure o Dynamic models; design loads (dead load and equipment, loads),

lumped masses, and member stiffness properties for the following structures a.

containment shell and containment.

int,ernal structures control building auxiliary building service building intermediate building turbine building diesel generator building Enclosure Page 11-11B See footnote (1)

I 12-15 I

16-19 See footnote (2)

I 20-26 g 9P5g004 10.

RE('l.Ii

" " "noCKET FJLE t;Opy PISg P<~

g. SAC%

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I ROCHESTER GAS AND ELECTRIC CORP.

May 22, 1979 Mr. Dennis L. Ziemann, Chief SHEET NO.

Enclosure I

II.

Seismic In ut to E ui ment e Typical calculations showing load path through the structure Auxiliary building o Description of Category I structural foundations I

o Summary of design check on column lines F and 3

I Page 27-42 82-83 107-110 84-84 1.

Design of structural masonary walls/

reinforcement details 2.

Design calculations of containment wall and steel liner 3.

Buried service water piping See footnote (3) 61-81 1-3 IV.

Seismic Clarification of Mechanical and e System component support calculations a.

pressurizer b.

accumulator c.

steam generator d.

reactor coolant pump Footnote (1)

Dynamic models are not available for structures from d. through g.

(2)

Submitted to NRC 5/7/77.

(3)

This information is still being assembled.

43-60 As requested by your Staff, eight copies of this letter and the enclosures are being supplied for your use.

If there are any questions regarding this material, please contact us.

Very truly yours, LDW:np Enclosure L. D. Whit, Jr.

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-17a, and -17b.

The shear deformation was not considered in the original frequency determination calculation of the internal concrete structure.

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corresponding period of 0.0607 sec.

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period originally calculated.

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GILBERT ASSOCIATES, INC. ENGINEERS AND CONSULTANTS READING, PA. SUBJECT SEISIY3IC. R VALI a r IOm PROJECT NAME ~+i~+ JvJ 8 5 I A1'ION W.O. NUMBER PAGE O I-98~LI-CIa~ 3g 0 R IG INAT0 R BATE l I 30179 OKPARTMKNT NAME DEPT. NO. FILING COOK ~T~cyurZAc E~Ci I AJ Fr-+I~ O~l l "I 'r3RLC I~C~ 25 C '7 'j<<Ivy'g=y>>, g<<v,'>> I. Q C<, RLC 5 3o Co 5< G3 l I I I l l I' I l i " 7F~ BATE ~ ~ 7 7 v 0 .0 0 ~~kh.v'uIJ g - QiIK ~ II I lI I ~I w '3 0 A --" Sl-Tao r--- AIIauabli l blgv'.~ Z. (AllolAJRS<<I ( 59<<4 j "lDI5'1S,3 '24,4 '~l ~) I II I h ...P~z.. I,,Sx3 p(,~!I4. 8,=.2,.l i~ 0 r lRLL = POR.., m eV Z,q '7, o c Sk~~" vs~a vv<<5 ~ 00 I 0mr Cl PROPRIETARY INFORMATION OF GILBERT ASSOCIATES, INC. FOR INTERNAL USE ONLY GAI 350 REV. 3 77

GILBERT ASSOCIATES, INC. ENGfNEERS AND CONSULTANTS READING, PA. SUBJECT 3 Kl&ITIIC. El!'AL~ 8 YlDID DEPARTMENT NAME SIP.MCTufZAI Euei~er=mi~mCi PROJKCT NAME Cf)n ne Sl-eT-f~~ DEPT. NO. FII ING CODE ))") <:za'I IN.O. NUMBER PAGE Oz/ Q8-"<) ceo ORIGINATOR Ia~n... ~wps cz 4q - 19 2 I I' RFI "t 1 9OIW i<<i<<~>'>' <<<<0N z cadiz.x.,x.t t'4 Lx==q.<<SI iL zxxitI. 5iIZ,.. f:g = I 5' r ~I'-I-L ,kS L .Q rn'i~ x ~ t I'I

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GILBERT ASSOCIATES, INC. EHGINEERS AND CONSULTANTS READING, PA. SUBJECT 5 015ynIC. QVQL,mA < JC>n.5 OKPARTMENT NAME 9TaWC T>I aC EuC >~r IZImC, PROJECT NAME ~7IAJ~A SV)3-,IOM OKPT. NO.- FILING COOK 01tH I >C I IN.O. NUMBKR PAGE u~ A@2.LI ~a <O ORIGINATOR b > 'HIS~> PII>FW:WAWC OA,. II....Lw,e In.C9 4 I 4 I 1 I V I FI WWAW4 ~~~+' -g'>4 4+4 144 Wjug' C4 ~IA 5YP.u I I I 4 I I )=i I I ) I I I t ~ 4 I I t "0 N I 4 4 I ~ ~ l' Scg) ZI 1. S.,)- W t9, I)<' I "0*44 WW >'.AWA 4' F)>IRC>> (ei~) I~) ....'ST f4&r P C Albania.bl~ ) blAwi. Z= AIIO~~'cI. ) Q,alZ~ (gi ro>>J>>bI>' gI r)g ( s~.~<3 ,2I ( 29,e.') St>'I It f I ~C,") I>. AI PJ (zn.s (OR,C 4 + 2',) ~ ~ ~ (~o.~ "j C') I.c-" .>>'s) ( n)."~' m.9" 4 w.:,I w>A),"II-MWI>'~4 WI ~ ' 4 POa Ql~., ~ ~1 L 5'y, P X 1/C 8= 2 'l>n" \\ MA(gg.+4 Q >0QP'Zd X L 7 P I,~+ ~I>~ A 1>L '1!>4, Per /frat 0 L) 9cx z~ g Il4 rI,',= )>Io 4 I... (t").=I ) (IZ) .I.qS...F' 4.8). les,' P: C~ >ii;)(.z",,; ),- g.-,j ul'-'4, g" '~,) 2V,S Culth 0O )a -7 3= > 8 IC a If O m o r 0m & C) PROPRIETARY INFORMATION OF GILBERT ASSOCIATES, INC. FOR INTERNALUSE ONLY GAI 350 REV. 3 77

DEPT. NO. FILING CODE I:>(. I W.O. NUMBER PAGE 0't ZIZZ ) OeZ-3 DEPARTMENT NAME STgVC'T 0L E&<~IM6E-lZIIC3C> GILBERT ASSOCIATES, INC. ENGINEERS AND CONSULTANTS PROJECT NAME C7lhPn79 QT ATIo~ READING, PA 0 R IG INAT0 R Ll I~)ISS, DATK 3 C) / cI 0 SUBJECT 0 E IEFFiiC EV ALONG.AT I 0 f4 PGI. Cv I'2 g ZQ OATK I i COI i',~ q g 'I en.eI p t',= G."I'e, GC I'I ~ 'Z, in-l, e GI",UeeeI S /Z. In ': <NE= 'I.C,~- P= r, = S,oq I /gag I I I I I I I ~ 4'- Mxlz.' 16'6 Ie e5Z '~>;.I~.l s 'd IIlt= (5'Io)8 ~) /bD.'?..ka.i bb== I'%Z in-L IG.SI lcc e >'I Ze'n e (GV'3 a nlrb C~ aC ,4 Fb "'P = co.qp-Iz,g = g'7, .4= b.. (I 5a=<L Fb~ i 5a G (I.53.-.'<- 'I 85'.=. VZI..< I G: P = 5 CG,'Ziclc bGl 65e) I'ec GGG 1'=,'335-t2,8= Cc ..) 4 5 'i&..CI<c id'. JO,8'7 q,zs)s, 'P= Zs,s~ h m 0or min c O~PII=TARY IIIFOPMA IOII OF Git.<IcQT ASSOI-IATIcS, INC. FOR INTERNAL USK ONLY GAI 3SO REV. 3 77

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Filing Code 1:36.l Page 60 Steam Generator and Reactor Coolant Pum Su orts Support structures of the above major components were designed for loads resulting from ruptures of the primary coolant piping and main steam piping. Equivalent static seismic forces equal to the components weight, accelerated by the peak response of the applicable seismic response

spectra, applied through the component's center of gravity, were evaluated against the corresponding pipe rupture loads.

For both the steam generators and reactor coolant pumps, the resulting seismic forces were smaller than the pipe rupture loads, therefore, supports were designed for pipe rupture loads.

Filing Code 1:36.1 Page 61 Consideration of the Liner in Structural Anal sis and Desi n The liner is included in the structural analysis of the containment shell. Xts inclusion would appear in the calculation of k. Xz and P on FSRR page 5.1.2-46b. The liner is taken to participate with the hoop reinforcement steel in arriving at the hoop rebar stresses in the cylinder and dome tabulated on FSAR page 5.1.2 51h. The meridional rebar stresses in the dome also reflect inclusion of the liner. The concrete and meridional reinforcement stresses tabulated for the wall on FSAR page 5.1.2-5lh were calculated without including the liner because the liner was located on the compression face of the section. Bucklin Evaluation Justification for including the liner in the analysis and in the cracked section stress evaluation, relies on whether or not the liner is buckled. This condition is evaluated below for the liner stresses and buckling strengths appearing in the FSAR. Cylinder 0 eration Condition The maximum compressive liner stress appearing on FSAR page 5.1.2-46e is 14.3 ksi compression in the meridional direction and is accompanied by a 2.6 ksi compressive hoop stress. The theoretical buckling capacity in the meridional direction is 16.6 ksi for no accompanying hoop stress,

Filing Code 1:36.1 Page 62 as shown on FSAR page 5.1.2-51f. Since the actual tested buckling capacity may be less than its theoretical

value, the absence of meridional buckling cannot be assured in the cylindrical wall.

The small compressive hoop stress precludes buckling in the hoop direction. Accident. Condition The insulation of the liner for accident temperature prevents an increase of the 14.3 ksi compressive stress. As shown on FSAR page 5.1,2-46e, the meridional compressive stress is actually reduced to -2.9 ksi, due to the accident pressure while accompanied. by 27.0 ksi hoop tension. This tensile stress would allow for a meridional buckling strength even greater than the 38,1 ksi shown in the FSAR page 5.1.2-5lf table. Dome 0 eration Condition Since the dome i's not prestressed, only a small compressive liner stress of -2.4 ksi exists, due mainly to the operation temperature. Consequently the liner is not stressed high enough for buckling to be a concern. Accident Condition Even though the liner is not insulated, practically all of the thermal stress is relieved as the dome expands under the accident pressure, As a result, the net liner stresses are actually tensile and are less than 10 ksi (equal biaxial).

Filing Code 1:36.1 Page 63 Incidentally, the equal biaxial buckling strength is 26.4 ksi compression as noted on FSAR page 5.1.2-51d. Results Liner buckling in the cylindrical wall due to meridional operation stresses cannot be ruled out, Buckling of the liner in the hoop direction in the wall and in both directions in the dome is not. predicted to occur. As discussed

above, the liner was not considered in the cracked section investigation of the concrete and rebar stresses in the meridional direction of the cylindrical wall.

However, the structural analysis did include the liner. Effect of Liner in Structural Anal sis In the structural analysis, the effect of the liner in the meridional direction is thru Iz and P ,.which are defined on FSAR page 5.1.2-46b (factor of 4 is missing in the denominator under the radical)., A comparison of these parameters is given 't below for the original design, in which the liner is included, and for the condition of no liner.

Filing Code 1:36.1 Page 64 Ori inal Desi n I

~~

(1) [42 + n(.375)j '1 z 7600 in (used) 4 4 k (Page

5. 1. 2-46c) 4EX 4

116. 5 (4) (4.1. x 10 ) (7600) = 0. 00553/in. (used) Without Liner (42)3 = 6174 in 1 4 z 12 116. 5 4 (4. 1 x 10 ) (6174) This small difference in p would have an insignificant effect on the moment and shear given by the equations on FSAR page 5.1.2-46b. Conclusion The discussion above provides support for inclusion of the liner in the original design structural analysis and section investigations.

Filing Code 1:36,1 Page 65 Tangential shears are discussed in the FSAR as "Longitudinal" ard "Horizontal" shears on pages 5.1.2-44 and-45. Related information appears on FSAR pages 5.1.2-18 and ~51b. These shears are induced due to the restraint on the containment shell at. its base subjected to the horizontal earthquake inertial forces of the shell. Physically, this restraint, would be available (in varying degrees) from (1) the radial tension

rods, (2) the 2'tructural mat plus the 2'loor from El. 231'-8" to El. 235'-8",

and (3) frictional shear resistance that, the Neoprene Pad provides on the wall where net compression exists at this interface. On FSAR page 5.1.2-5lb, a maximum tangential shear value of 67.2k/ft. is given, which is due to 0.2g ground acceleration, This shear value is produced by the conservative 0.46g response acceleration discussed on. FSAR page 5.1.2-17, A more accurate seismic analysis is discussed on FSAR pages 5.1.2-17a and -17b, and the resulting shear force is shown in FSAR Figure 5.1.2-8F. From FSAR Figure 5.1.28F, the maximum value of tangential

shear, due to 0.2g ground acceleration, is V

= 2V: = 2 x 6700 max 'ave 7l X 108.5 ft. 39 3 /ft (Containment Diameter = 108.5 feet)

Filing Code 1:36,1 Page 66 The corresponding tangential shear stress on the gross concrete

section, vu

, is v' Vmax = 39.3 = 78 psi k u 12" x 4>" ~504 in 78 psi (39 3k/ft. ) tangential shear is evaluated (below) for the horizontal and vertical shearing planes of the wall. Horizontal Plane Due to the presence of the vertical prestress, the horizontal plane at B = 90 and 270 (0 180 axis being the direction of earthquake) is under 134 /ft membrane compression for load k combination g41. The 78 psi (39.3k/ft) tangential shear corresponds to 2E in this load combination and it occurs at 8 = 90 and 270o. The ] 34 /ft membrane compression provides more than enough shear friction clamping force to resist the 39.3 /ft shear. Vertical Plane Since 'the containment is not prestressed in the hoop direction, its ability to resist the tangential shear is evaluated using the provisions of CC-3421.5.1 of the ASME Section III, Division 2 Containment Code. These provisions apply to tangential shear on reinforced concrete sections which do not have the benefit of prestress compression.

Filing Code 1:36.1 Page 67 The 3 N18 9 9" hoop bars in the shell wall provide a rein-forcement ratio p , of 0.0317. The corresponding allowable shear stress carried by the concrete, vc,.is its maximum value of 160 psi. Since vc of 160 psi exceedsv'f 78 psi, the concrete can carry this tangential shear provided the three requirements of item (b) in CC-3421.5.1 are met. Item (1) is met because the minimum specified concrete compressive strength is 5000 psi, which is greater than the 3000 psi requirement. Item (2) is met bacause ASTM C131 tests (conducted in 1975) of aggregate from the same geographic area as that used in the containment shell indicate a maximum weight loss of 29% which is less than the 40% maximum requirement. Item (3) is met because the cracked surface is produced by tensile fracturing 'of the concrete due to 1.0 P and, consequently, would be of sufficient roughness.

Filing Code 1:36,1 Page 68 NRC Question XXX.2: GAI calculations Filing Code 1:36.1, pages 69 thru Sl

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File Code 1:36,1 Page 82 The plant buildings are located in a relatively level meadow area with finished grade elevation approximately 270'-.0". The major plant structures are supported on the Queenston Formation bed rock (red. sandstone) or atop natural or compacted granular soils immediately above the bed rock. The Queenston Formation is generally found at a depth of 30 to 40 feet below natural grade. Unsuitable soil removed below foundation level is replaced either with lean concrete or compacted structural fill, Structural backfill where used, has been placed on layers approximately 8" in thickness and each layer is compacted to a density of at leat 95% of the maximum density obtainable by the modified AASHO method (American Association of State Highway Officials). The Containment Building is founded on rock. The bottom of the foundation mat. elevation is 231'-.8" with the deepest foundation around the reactor vessel at elevation 208'-0". The containment cylinder is founded on rock (sandstone) and anchored by means of post-tensioned rock anchors whereby rock acts an an integral part of the containment structure. The containment building is isolated from other buildings, and in areas where it is not surrounded by buildings, a retaining wall spaced 2'-6" clear of the containment wall is provided. This eliminates lateral earth pressure due to backfill on the containment, wall. Rock elevation in the area is approximately at 236'-0". The Auxiliary Building is located south of the Containment Building and founded on rock. The bottom of foundation mat elevation is 233'-8", with the deepest foundation for decay heat removal area at elevation 217'-0" with sump at elevation 214'-0". Rock elevation in this area is approximately at elevation 236'-0". The west end of the superstructure of Auxiliary Building is connected with a portion of the Service Building, and on the northwest with the Intermediate Building.

However, the foundation of the Auxiliary Building is independent of these building foundations.

Intermediate Building is located on the north and west of the Containment Building, and is founded on rock. The west end has a retaining wall where the floor at elevation 253'-6" is supported. The bottom of the retaining wall footing is at elevation 233'-6". Rock elevation in this area is approximately at elevation 239'-0". Foundations for interior columns are on individual column footings and embedded a minimum of 2'-0" in solid rock.

File Code 1:36,1 Page 83 The Service Building is located west of the Intermediate Building and is founded on compacted soil. The bottom of the mat is approximately at elevation 252'-8" with localized thickened mat for column footings, and deepest foundation for sump is at elevation 247'-3". Natural compacted granular soil is approximately at elevation 255'-0" to 260'-0". Mat is supported on the east, side by a retaining wall on col. line 3 with the Intermediate Building. The Turbine Building is located North of the Intermediate Building and is supported by a combination of perimeter grade beams and a structural mat. The mat foundation of the turbine generator is independent of the surrounding turbine building foundations. The Turbine Building foundation is supported on the natural compacted granular material which overlie the natural rock. Rock elevation in this area is approximately at elevation 239'-.0". Bottom of the trubine generator foundation "mat is at elevation 243'-0". Bottom of the perimeter column foundation mat varies from elevation 245'-3" on south side along the Intermediate Building to approximately 246'-9". Circulative water discharge tunnel is supported at elevation 242'-2". Some of the area where Condensate Pumps are

located, the entire area is filled with lean concrete, with bottom elevation 229'-8".

The area between'urbine generator foundation and the permiter column mat foundation is supported on compacted granular material with bottom of mat, elevation approximately 251'-6". The Control Building is located adjacent, to the south-east corner of the Turbine Building and is supported by a mat foundation. Foundation of the Control Building is supported on the natural compacted granular material. The rock elevation in this area is approximately at elevation 240 '0".'ottom elevation of the deepest. portion of foundation mat is at. elevation 245'-4", with a structural slab supported at elevation 250'-.6" with thickened slab for column footing. The Diesel Generator Building is located beyond the north-east, corner of the Turbine Building, and is supported on strip and spread footings at elevation 243'-.0". The Diesel Generators are supported on individual concrete pedestals, at elevation 243'-0". The rock elevation.in this area is at elevation 240'-0". The foundation structures are supported on the natural compacted granular material. Foundation of all the above mentioned structures, except the Containment. Building, are connected into the adjoining building by nominal dowels.

File Code 1:36.1. Page 84 Safety Class 1 equipment and components were analyzed for seismic accelerations by the response spectra approach. The response spectra specified for the Ginna plant are.presented in Figures 5.1.2-7 and 5.1.2-8 of the FSAR. The original design basis considered the seismic response of systems and components to the simultaneous application of an acceleration in the horizontal and vertical plane5 and combined them to maximize the support design load condition. Xnformation pertaining to the qualification and. analysis of individual systems and components is presented in the Tables of RGGE's letter to the NRC dated April 3,

1979, (L. D. White, Jr.

to Dennis L. Ziemann,

Subject:

Systematic Evaluation Program Seismic Reviews).

GILBERT ASSOCIATES, INC. ENGINEERS AND CONSULTANTS READING, PA. DEPARTMENT NAME Q T gli V ( P. I'.I H LD<>>a>I= PROJECT NAME C~IRJAJ4) +T)l7 I c)M DEPT. NO. peal/]t, g W.O. NUMOER Oil hie,Z.~I Fl I.ING CODE /J~~/ PAGE ooo /g7 SUOJECT +I=lsATIC. I-43".It ~I3-rlo& P LI~= Pl AL /QI s. 4 ~ 'i I I: I l I j I 1 I I I rnziTlazyc..s .~ coinP lz'E ss,'ll a~cIIPAc.o h. -.ia LP xcaa> 'o~ I a I THE IliE;ITIQBQ >~TOo 5LEAJ'b Br'. 'To=O+Pe@IcT: I I I i I I QBAC..rI,C~, ~BE~OA'b'm.il.l. R.Cbi V.I3:.Ja~Ta. I I i I I I I I.i I COAT PAESAN.Ii I l,A3CII.EAKIM I Zo.llh3.c, C, AJ 5, i.o '~)' P..GW LA 'T,E.'b, P Q pl.<-t.t.~~ I~ v hJ.r Qb I i: I l l i .. 6> h m Qh:iz.GQ, A~~R.PPRo,.xxTnAa.@; i=AcTo, C P Ir~. ETz. TIcAi...SRAcinD(~ sYGTKTnl ~ HLorv(~ .- l IJhJ&..,~r Rc EVIL,ted% r 'L'b .'.'RO'< -o)!>.T3,.3. Cl GE, ) ~M,."b~$. =..., O'h,. I . (, .,'BIZAc.i~a.. In<n~al=les.. j mE:ne.. N.ss~me+, 'tu .Ge'<.EFFFcTII GoZhI'WEAJS Io~ Sm'b c:,o..~PIZEE,Slo~.< .... H.EP I=-=I YHE,.I. ORIGINATOR ~ i Gl&S DATE 8' 8 l '7'I VERII')ER oAva~li E,L6~ ~ ~r: G.pj ~Q'T)aDC> L I~ I a~=< (SL,. ~ l ~+ RHINE r= ..4,(S ~ 85 I V.BP-'TICP9t I 8I<Ac..I~&~.I~, T..i)< ~3T3. r 'b., T'i. - 6 6'.PP.R C.> i,u.e os~ AM l ~ IQPPI.I~10 HOP OmV' Io 8 E&I $ 7:-J.~C~.~H 6 I I I C.dh) IG ,HAs'. SBBm. '~i T.Can '"-.Loo lz,, C

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ENCLOSURE XX

Response

to Item III.(3) of the NRC Docket No. 50-244, SEP Seismic Review. Buried Service Water Pi@in Size: 16" to 20" nominal I.D. 2. Naterial: Prestressed .concrete cylinder (steel) pipe, class

150, Rubber and Steel
joint, AWWA C301,58 3.

Pipe Bedding: 4. Penetration: All buried service water pipe bedding take either of two forms: (a) con-crete cradle (b) concrete encasement. Typical details of concrete cradle and encasement are shown in Figures 1 and 2. Details of pipe penetration 'through wall is shown in Figure 3. Concrete is poured around pipe monolithically with wall. 5. Thrust Blocks: 6. Subgrade: 7. Backfill: Concrete thrust blocks were provided at various points throughout the entire line.. All subgrade on which concrete bedding were constructed were compacted to at least 95 percent of the maximum density at optimum moisture content as deter-mined in accordance with the modified AASHO Spec. All backfill at, sides and immediately over pipe were compacted uniformly with compacted material in successive layers of 6" or less to at least 95% of the maximum density at optimum moisture content as determined in accordance with modified AASHO spec. I '" o DESIGN ANALYSIS El'L'R NO. PAGE~ of~ REV DATE 42 ~ 60 RfV, t/77

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DESIGN ANALYSIS REV. E'IrR XO. PAGE of~ D-. 42 ~ CO PK'L'. ~

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