ML20070J660

Forwards Draft FSAR Revisions for Section 3.8 Re ASME Code Required Insp to Be Discussed at 821026 Meeting

ML20070J660
Person / Time
Site:	Clinton
Issue date:	10/21/1982
From:	Launi C SARGENT & LUNDY, INC.
To:	Williams H Office of Nuclear Reactor Regulation
Shared Package
ML20070J658	List: ML20070J660
References
SLLI-746, NUDOCS 8212280489
Download: ML20070J660 (32)

Text

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SARGEFT 4 LUNDY, '.,

ENGINEERS c

rouworoessi r

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e s E A s v M o+t m o r,s T R r,CT' pd i

t CHICAGO, lLL 1, Nots eosos, j,.

(stal see anco

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i SLLI-746

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October 21, 1982

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Project No. 4536-02 11

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Illinois Power Company

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Clinton Power Station - Unit 1

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+-

.x Draft FSAR Changes Explaining the;Use of ASME Codes on Structural Design i

Mr. Herb Williams

/ '

/.

Licensing Project Manager

/

-' 5 Standardization and Special Projects Branch

/'

f-i Division of Licensing

- ;, ( ;.,

Office of Nuclear Regulation f/

Room 340

/"

7920 Norfolk Avenue

/'

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I.,

Bethesda, Maryland

,,/,,

1

Dear Mr. Williams:

,As requested by Illinois Power Company', I am sending you a copy

,v of the draft FSAR revisions for Section 3.8.

These draf t revisio.ns -

will be discussed at the meeting scheduled for October 26, 1982 between NRC and Illinois Power Company.

j Yours very truly, I

~

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//' ' l' 3,

l ',i/G,

C. MichaelLauni/

CML:aab.

Licensing Engipeer l

Attachment Copies:

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.H. Livermore (1/1) d ~~

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D, Geier (1/l)

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S.

Spencer (1/l)

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E. Wuller (1/l)

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B'.

Erler (1/1)

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R. C. Heider (1/1)

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R. A. Witt (1/1)

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P.

K. Agrawal (1/l) j g;2 NSLD File:

1C-10a File:

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CPS-FSAR O

p,/ I b

7 l

~P a.

pedestal cavity area:

6 feet 0 ir ch;

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1

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b'.

sump floor area:

9 feet 0 inch; a a

'~ ~,,

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stippressio'n pool area:

3 feet 0 inch.

c.

q Leak test. channels'are provided at the liner' seams in the sup-pression;' pool area and in the containment wall up to elevation 757 feet 0 inch.

The containment liner in the wet areas of the suppression. pool is of stainless' steel to' minimize corros, ion

?

'a problems.

3.8.1.1 5 Polar Crane Girder Brackets The' polar crane g'irder is located jus't below the spring line of the containment and is supported by brackets that are spaced 150 apart and embedded into the containment wall.

Figure 3.8-16

' shows the embedment details for the crane girder brackets.

3.8.1.2 Applicable Co?cs, Standards, and Specifications This cection lists codes, specifications, standards of practice, Regulatory Guides, and other accepted industry guidelines which are adopted to the extent applicable, in t;he design and construc-tion of the containment.

The codes, standards and specifications' are listed and discussed in Table 3.8-4 and are given with a

(, ' ' 'sp'ecification reference number.

The reference numbers for. 2 containment are

/throughf;~7dyb9 a.

59 b.

11 through Ji"; 2" th mvh Ol 1/fl7 lf 5 *,2 3

y j j

c.,. 2 3', 25, k X, 35, 36,'38 through 41; and 47_

d.

43, 44, 46, And 48 j

.~~4 S o 4

the provi) ions of Article,the design of/

A1]

,.Div. 2{ are followed in CC 3000 of ASME B&PV Codg, Sec.

t e containm nt q

II]

str ucture 'exce.t for the.t'angdntial shear' criteria.

d'"

\\

j

- isions f thel1971 ASME Boilpland Pr Code,f The pr sur Vesse H 7(4 i

fon eneteation sleeves, the per,mme( of 1973 a e 'da are a{dopted l

Se.c ti n H I, Div.isi,ci) 1, with sb gg^

so'nnel air lock and equipment j l

h'atth.

\\'

3.,8.1. 3 Loads and Loadino Combinations I

TheEcontainment' structure is designed using the loads, load combinations, and' load factors listed in Tab;1e3.8-1.1.

y L3 ads-and load combinations listed in Table 3.8-1.1 are used for t.he design of the steel liner and liner anchors, but the load

" factor-for all load cases is 1.0.

3 3.8-6

.N.

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

4

.IPS-FSAR The desig ndanalyshsproceduregareJdfu1compliace h

th th re,quir ments,of Article CC-30 r'th'e ASME..B&VP Co,de, Se t)<*>n I I,* Dpsionl 2.,/

U Throughout't$eanalysYsfspecialattentionisgiventothefol-lowing:

a.

the intersection between the base slab and the cylinder; b.

the intersection between the cylinder and the-dome; c.

the area around the large penetrations; d.

Ioading on the base slab 'from the underlying foundation material; e.

stresses due to transient temperature; f.

penetrations and points of concentrated loads; and _

g.

embedment of polar crane brackets,in the containment wall.

3.8.1.4.2 *Shell and Base Slab Analvsis

~

0';'

.The method of anai ysis used is a thin-shell of revolution finite element procedure using the computer program DYNAX.

The complete containment with its basemat is modeled with shell elements.

The loads applied to the shell model are centerline loads.

Consideration.is given to the shift of the load from the actual place of application to the centerline of the shell.

Ov,erall effects of non-axisymmetric loads such as a pipe break load are analyzed using a series of Fourier harmonics, the summation of which represents the distribution of the load on the structure.

Results of the analysis, except for pool dynamic loads, are pre-sented in Figure 3.8-17.

Analysis resdits and design assessment of critical cross sections are presented in Attachment B3.8.

The base clab of the containment building is analyzed by a plate finite-element program PLFEM-II.

The stiffening contributed by

,7 the walls is also included in the finite-element model.

Foundation soil is represented by equivalent springs at the nodal points of the basemat elements.

A range of soil properties is used to allow for the short-term and long-term. characteristics of the soil.

~ '

The base r. lab is also analyzed using the c6mputer progra'm'CSEF-III to con:irm the results from the finite-element analysis.

3.8-8

CPS-FSAR -

AMENDMENT 8 OCTOBER 1981 Except for the allowable tangential shear stresses listed in Subsection 3.8.1.5.1.1, all reinforced concrete 9 e in accordance 1

with Article CC 3400 of ASME B&PV Code, Sec. III, Div. 2.

3.8.1.5.1.1 Tangential Shear M

The containment is designed for the peak tangential shear.

The tangential shear stress capacity of concrete ve is limited to 40 3

psi and 60 psi respectively for the, service' a,nd f,actored load combinations defined in Table 3.8-1.1.

The excess shear is designed to be carried by inclined reinforcement.

3.8.1.5.2 Steel Liner The allowable stresses and strains for the liner plate are limited to values as specified in Article CC 3000 of ASME B&PV Code Sec. III, Div. 2.

When subject to SRV discharge loads, the. liner plates are designed in accordance with Subsection NE,Section III of the ASME B&PV Code.

3.8.1.5.3 Steel Pressure-Retaining Components Portions of the containment boundary that are of steel and'not backed by concrete, such as the equipment hatch, personnel locks, and Code Class MC' penetration assemblies, are desig.cd in accordance with Subsection NE,Section III of the ASME B&PV Code.

These components are designed for the load combinations shown in Tables A3.9-6 and A3.9-7.

The allowable stresses for these load combinations are summarized in th following list of figures from Section III D'iv. 1 of ASME B&PV Code:

a.

design. conditions, Figure NE-3221-1; b.

normal and upset conditions, Figure NB-3222-3; c.

emergency conditions, Figure NB-3224-1; d.

faulted conditions, Table F-1322; and e.

test conditions, Paragraph NE-3226.

3:8.1.5.4 Head Fittina Desian All head fittings (cover plates of flued head 3),-whi'ch'hri clas-sified as Seismic Category I components, meet all stress require-ments associated with the applicable design, operati~ng, and testing conditions, as stated in the following. paragraphs.

. stress values, as The allowable (temperature-dependent) applicable to items a, b, c, d, and e, are taken from Tables I-1.1 through I-2.2 of the ASME Code,Section III, Div. 1.

S 3.8-11

'< CPS-FSAR AMENDMENT 8,'

OCTOBER 1981 g

l 3.8.3.2 Aeolicable Codes, Standards, and Soecifications This subsection lists codes, standards of practice, regulatory guides, and other accepted industry guidelines that are adopted, to the extent applicable, in the design and construction of the structures internal to the containment.

To' eliminate repetitious listing of the codes and standards for each structure, the codes l

and standards are listed and discussed in Table 3.8-4 and given a reference number.

For each structure internal to the L

containment, the reference numbers are listed in Subsecti~ons 3.8. 3.2.1 through 3.8.3.2.4.

r T5Lf.t G F-q g e p2is sf AWA *W v= ci-J w

QMy, J A,' p s 'm,.~~t m '

g-Y W AM JM MW%G=,

qf W">s r%

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uw n,A w w.-

,A

'~W /%

yd&

y(

W

e. %

ww,

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I e

eue e.

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O

m CPS-FSAR AMENDMENT 8, OCTOBER 1981

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3.8.3.2.1 Reactor Shield Wall and Pedestal The reference numbers are as follows:

25bnd 20 ' or reactor pedestal; A

a.

f b.

21 and 23 for reactor shield wal'1; and 28, M 41', 43, A3',' and 47 for both reactor c.

pedestal and reactor shield wall.

. Item: 25 and 25-crc...I er,11-mLie Ida iyua shir 10 wall. - <-M 3.8.3.2.2 Drywell Structure

~

The reference numbers are as follows:

1 through [; 7 M 9 j a.

lL4 b.

11 through.Bs; 16, l'7 17, 2 0 ;

j

.c.

21, 23, 25 /1 % 28; and

~

3 d.

3+, 3 5, 3 8, 41, 4 3, 4 4, 4 6, 4 7, 4 8, and 4 9.

3.8.3.2.3 Miscellaneous Platforms and Galleries, Refueling

,j Floor, Ecuipment Rcoms, Sucoress:.on Pcol Weir Wall, Process Pice Tunnel, anc Structural Support 8

System for Recirculation Pumps The reference numbers are as follows:

S*

a.

1 through 7; 7 9'

j 14 b.

11 through,M; Id l'7, ! &j C j 7

i c.

21, 23, 28, 31, M, 35; and d.

37, 38, 41, 43, 4 6, 4 7, and 4 8.

3.8.3.2.4 containment Pool The reference numbers are as follows:

I 5

1 through y; 7,9,9 *

~a.

~*~ ~ " ~ ~.

\\

i, su b.

11 through M; 16,&7 if 2 D j.

KGc g s'tL

{

j j

21, 23,y G&, 28, M, 35; and c.

i.

d.

37, 38, 41, 43, 44, 46, 47, and 48.

m N

1 I

l 3.8-23

G CPS-FSAR A11ENDMENT ' 8 OCTOBER 1981 3.8.3.4.3 Reactor Pedestal and Sucoression Pool Weir Wall The reactor support pedestal and the suppression pool weir wall are designed as axisymmetric cylindrical shells fixed at their base.

Loads from the reactor pressure vessel and the reactor shield wall are applied at the top o.f the pedestal.

Two Sargent & Lundy shell-of-revolution programs, SOR-III and DYNAX, i

i i

are used for analysis.- The seismic and pipe rupture forces

~

k transmitted to the pedestal are included in the design as shears jr and overturning moments.

The effects of concentrated pipe break load on the weir wall are analyzed using a series of Fourier harmonics, the summation of which represents the distribution of the load on the structure.

The capacity of the section under combined loads is checked using the program TEMCO.

Thermal analysis is performed as discussed in

• Subsection 3.8.3.4.2.4.

The weir wall thickness and reinforcement are se proportioned that the pressure suppression efficiency is not impaired by the deflection of the Weir wall under design loads.

I 3.8.3.4.4 Refueling Floor, Miscellaneous Platforms und Galleries,

,and Support System For Recirculation Pumps The platforms, galleries, and structural supports for the recir-culation pumps are designed using conventional elastic design I

a l.

methods.

j 3.8.3.5 Structural Acceotar.'e Criteria 3.8.3.5.1 Reinforced Concrete Deformations of the drywell structure, containment pools,' and l

equipment rooms under factored load conditions are limited by

)

specifying a maximum allowable concrete strain of 0.002 in./in.

Yielding of the reinforcing steel in tension is allowed only i

j when the effects of thermal gradients are considered.

t i

i For section analysis, the strain in the reinforcing steel and 5

concrete'is assumed to'be directly proportional to the distance

~

from the neutral axis.

The concrete stress-strain relationship is defined by a half parabola whose apex is the point where the

.7 strain is 0.002 in./in. and the stress is 0.85 f',

where f' is t'he specified concrete compressive strength.

The tensile.,

strength of the concrete is neglected.

f.

g o. n. n m g f, g,g l

j Except for the allowable tangential shear stresses listed in

~

Subsection 3.8.3.5.1.1, all reinforced concrete'.is in accordance with ASME B&PV Code,Section III, Div.

2.

The stresses and strains in all other reinforced concrete internal structures are limited to those specified in ACI.

l 318-1971.

Servicability checks are made in accordance with ACI 318-1971 to assure crack contro) and to keep deflections below the limits prescribed in ACI 319-1971 or to the manufacturer's 3.E-23

-.~_.

.n..

~

CPS-FSAR l

for each unit are in their cwn missile-protected cubicles, hach cubicle has its own cooling unit which is electrically segregated from the others.

Each cubicle is flood protected by bulkhead

. doors.

No single failure of the equipment associated with one cubicle will have a detrimental effect on' the rest of the system.

+

The CWSH is constructed with two inlet channels for providing water to the shutdown service water pumps.

)

3.8.4.2 Applicable Codes, Standards and Scecificationd The codes, standards a'nd specifications applicable to the design, fabrication, construction, testing and in-service inspection of safety-related structures outside the containment are listed in Table 3.8-4 and include the following specification numbers:

a '.

1 through Mr; 7, 9 l Il -iQ I4j'l G, 8 7, lt j, 5

25 b.

21, 23,.25 c b&, and 28; j

31,HE&r 35, 37, 38;gand

~c.

h 3, 44 a~ J. 4 C

~.

41 thro, ugh 48.

d.

3.8.4.3 Loads and Loadino Combinations es

' The list of loads and their definitions and the loading ccabina-tions applicable to the design of Seismic Category I structures me.

.outside the containment are given in Table 3.8-1.2 and 3.8-2.

The list of load categories where the types of loads are defined.

is also given in these tables.

In addition to their own dead loads including the weight of' equipment, piping, cable pans, etc., floors are designed for con-servative live loads resulting from the movement of the largest piece of equipment.

The roofs are designed for a uniform live load of 25 psf in addition to snow loads and loads from probable maximum precipitation.

The roofs a.re also designed.to withstand suction pressure induced by 'the design vind and tornadic wind as discussed in Section 3.3.

pattern live loads are applied to determine maximum moments and shears in each slab.

All slabs are designed for the effects of internal missiles, thermal gra'dients,

.and pipe rupture loads, wherever applicable.

Floors and roofs

. are checked for their ability to transfer shea,t through-diaphragm action.

The walls, interacting with the floor slabs, 'are designed to withstand the effects of seismic induced shears and moments.

All walls are designed' for external and internal missiles,' ' transient thermal gradients, tornado-induced pressure, lateral soil and hydrostatic pressure and pipe rupture loads, wherever applicable, in addition to their own weicht and associated loads from slabs' and beams framing into the wills.

For the desian of subarade walls a surcharge load of 500 psf or AASHO E-20'rheel loading is considered.

A

-_.~..,.

..___-.________-__--m

a.

a e.

d s'

CPS-FSAR AAggggggy 3 OCTostR 1981

. TABLE 3.0-4 LTST OF SPECff! CATIONS. C00ES'AND STANDA705 SPECI-SPECIFICATION FICATION OR RITERENCE STA::DARD NUM e t R DESTC?:ATTON T!Ttt EDITION REKARKE ACI 318-71"I77 u11 ding sade pequirements for

'4444=

Appendix *A* adopted 1

b

. Supplement 1974 Reinforced concrete Jg 7f af 7,7 for seismic design 6' 2 ACI 301-72 Specifications for Structural 1973 Revision 1973 Concrete for su11 dings V3 ACI 347-68 Recomeae'nded' Practice for Con-

/

1968 ANSI A145.1-1968 crete.rorr rk 4

ACI 305-M1 Reco..nended Practive Mr Lr c 4 M T"* N U b ANSI A170.1-1972 Weather Concreting 5

ACI 211.1-J Recommended Practice for a4444-M 'l 3 f2T: ?. ; ; 7. ;- M+t* Selecting Proportions foi Normal Height Concrete

,a 6

- "f : f;i-is n r. w--u... ;

.......i.r-

!!?

!M::u ' ;

-? _2:. '.w e...

7 ACI 315-74 Manual of Standard Practic 1974 for Detailing Reinforced Concrete Structures 8

ACI 306-66 Reconnended Practice for Cs?d ISI Heather Concreting 9

ACI 309-72 Recommended Practico for 1972 Consolidation of Concrete f!e.

m.'*16

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..".....r, c...

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---

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• • 5" 1 *.^": ;.... v....,;....

2"

11 ACI 208-71 Recommended Practice for 1971 Curing concrete title 69-1 12 ACI 212 Cuide for Use of Admixtures in ACI Journal Concrete Sept, 1971

-Title 64-56 13 ACI 214-65 Recommended Practice for Evalu-1965 ANSI A146.1-1968 ation of Compression Test Results of Field. concrete 14 ACI 311-64 Recommended Practice for 1964'

• Concrete Inspection 15

.-5C:

?-

..r

_se.m car.em..

16 ACI 204-73 Reco. mended Practice for Mea-1973 suring, Mixino. Transporting and Placing Concrete 17 Report by Placing concrete by Pumping' ACI Journal ACI Committee 304 nachods May, 1971 Title 68-33 18 Report by Strength Evaluation of Existing ACI Journal 1

ACI Co.,ittee 437 Concrete Structures "

.Noy 19%7 Subcor.mittee 1 Title 64-6'1' "

• 19 Deleted 4

20 ACI-ASME-359 ASMr soiler s Pressure vessel

• 19'73' Issued for trial use Code.Section III. Diviston 2 and* co'mme nt Concrete Reactst vessels and h,

Containments AISC-69 gHfs} [ Specification for the cesign.

-....:. 1969 ud' li "?

21 Tabrication, and tractics of Structural Steel for Sut1 dings N.

Sheet 1 of 3

CPS-FSAR AMENDMENT 8 OCT02ER 1981 TABLE 3.8-4 (Con t'd)

SPECI-SPECIFICATION TICATIC::

CR F.ETERE';0E STANDARD

.s EUMitR DES TC?'A?!O!8 TITt.E EDITIO?1 R tw.AR MS 22 M-On M i c :isa ttah

..,.i w.'

9

>-> 14 t%

!.ii.i

"^!d-Ft=er ed-StetI.

-4teve r - - ! ' - - M :

23

^"8 01*1

..-......... Structural Welding Code 1976 d M ")

24

'AW,,....,,

a

_,'_C'"'*,p.__.&en

'-Id4e**

M.

__,1 e

. i : s. m_

ye c7--r,, ion g re.fe....' w..

,ce,v-_r. n r" u.t i

. ~..

25 AG#re-4

~1.

M 841--

M '" ;'i'..

y

.;.;.. ::!;. :.. ~ :-^

T i : ! ' ;...

~

.m+l..*

2-m s

26

.a..

... :O=2=,4.e

^

u-

-- ; 2., : :. ~...... :...%............... '-

a.w.a.

.:... m u.,

1" : '.4d enda.

__'a-*'

27 n....

-ar-me s-n f,=

.-C ;.., ".....

..!: 7.d ;.d.

%.,...;.... :N r. o.....-

---C..' --..;.- '

s.. w.w.

28 ASTM Annual socks of ASTM Standards

-tTT:--

29 "r:

al...^

2....l..J 0.2.

1;;.;; -

mye 7 e+_...

si.r..

24.<,..-

30 l

'. - * ~ * * *

'.^-..'"~*.4".-.. _ ' - - ^ ' ' _ - _ ' "___'.

e....

en-31 UBC Uniform Building Cade 1970 TI$

j 32

'!^- 1 ?Irsc+ M ed:

1.;.;-

.liilo r-33 s, ' - -

.;;ett--

- - u m leuone-*e rm-resoect-tc d &t40sh--

.-cred tag-and Consasuctaone.-

9 34

,,,3.121202. Occ;.ca tien.5.sf aty

'

• tes*

nd.Healt.h Ac?

-'t>4--

35 Unc Regubtory Mechanical Cadve1'd Solices in Feb. 1, 1971 Withdrawn by the NRC*

Cuide 1.10 Reinforcing Bars of Ccn: rete 7/8/81 Containments 36 C".0-T.a; ;as.vy

trus.entation for-Earths.a-tes - -. Re. -1;

[

Cci tr l:ll'*

.Apr. 1974.

j 1

37 HRC Regula tory Tuel' Storage Tacility Design Rev. 1 i

Guide 1.13 sasis Dec. 1975

. 38 URC Regulatory Testing of Reinforcing Bars Dec. 28,1972 Withdrawn by* the NRC [

Cuide 1.15 For Cc.. crete Structures 7/8/81 (revision 1) t 39 U?.C Regulatory Structural Acceptance Test 'or Dec. 28,,1972 Withdrawn by the NEC.

Cuide 1.18-Cencreta Pri ary Pcactor Con-

• .... 7/8/81 ~~

t.inments (Revision 1) e 40 URC Regulatory Nondestructivs Examinati:ns of Aug. 11, 1972. Withdrawn by the NRC Guide 1.19 Primary contain ent Liner Walds 7/8/81 (Revis t o.a. 1) 41 N c Regulu:ry

.Mality Crog. Clasnficatiens -

-Pev. 3."

Calde 1. 4 an.5 standards Te'.r. 197G i

42 ett!-e-ee,u l t..,

^J.... a.....m o.

Aid a 1^7G 43 URC Regulatory Seisnic Design Classification Rev. 3, Guide 1.29 SCPt. 1978 1

Sheet 2 of 3

Changes to FSAR TABLE 3.8-4

' No.

Standard Title Edition Remarks

' 25 ASME ASME Boiler and 1971 with

-for Containment Pressure Vessel S_ummer of Locks and Hatches Code,Section III, 1973 Addenda Division 1, NE 25a ASME ASME Boiler and 1974 with for Drywell Pressure vessel Summer of Locks and Hatches Cole,Section III, 1976 Addenda

• Division 1, NE 25b ASME ASME Boiler and 1974 with for Reactor Pressure Vessel Winter of Pedestal Code,Section III, 1975 Addenda -

Division 1, NF 25c ASME ASME Boiler and

' 1977 for Fuel Pool -

Pressure Vessel Gates Code,Section III, Div. 1, Subsection ND 25d ASME ASME Boiler and

-1977 for Fuel Pool Pressure Vessel Liners Code,Section III, Div. 2

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l*

i gg "

g e

b

,v

. ~.-

v i

e

=

CPS-FSAR

'AMENDME;;T I a

=

OCTOBER 1981 e.

~

TABLE 3.8,4 (Cont'd)

{.

.. SPECI-SPECIFICATI0*3

• • *

• FICATION OR REFEREME STANDARD e.

NtJMB ER DESICHATIC'.

TITLE EDITION RLd.AEU -

e a.

hy '.. *44... NRC Regulator */ *.ontrol of Stainless Steel g

Rev. 3,

{*

Cuide 1.31 dalding APr. 1976

~

<i 45 NRC Regulator */

Control of EleYucsAag Dec. 28, 1972 Cuide'1.34 Wcld Properties

[*i 46 CRSI Manual of Standard Practice 1973 47* ** ANS'I'n45.2.5 Proposed Sup 'e=entary QA 19h2 1972 Requirements for Installation, Inspection and Testing of Structural Concrete and

'O.

Structural Steel during Con-struction Phase of Nuclear Power Plants 48 NRC Regulatory Concrete Placernent in Category Rev. O, withdrawn by the NRC*

'~Cuide 1.55 I Structures June 1973 7/8/81 49 NkC flerJulatory Design Limits and Loading June 1973 Cuide 1.57 Co:-binations for Metal Prir.ary Reactor containment Systems

[

and components 50 NRC Regulatory Materials for Concrete Contain-Rev. 1 Guide 1.136

ents (Article CC-2000 of the Oc t. 1978 code for concrete Reactor Vessels and Contain=ents)

.I

-f* * *.

-)

Explanation of Abbreviations C 3.*. *

• American Concrete Institute

.ACI American Institute of Steel constr'uction AISC

~

- AISI American Iron and Steel Institute ANSI,-

American National Standards Institute American Petroleum Institute API American Society of Mechanical Engineers ASME American Society for Te. sting and Materials ASTM American Welding Society AWS d

Concrete Reinforcing Steel Institute CRSI National Electric Code NEC Nuclear Regulatory Comission NRC

"~

Uniform Buildiner code U8C 1

s.

~

.o sheet 3 of J

6

'I g

g,

=

1-* ' -'i*-

r,An tesle 3.s-'

DRA FT (See Note 1)

IC1Z nt.179] A*

FA!4t1CATIGH EllECTION l

gy

.Iif!51 TAT!"U l C.t?i blate ?

o!D]Ni E7AMlf; Ail (3!

STibitfG

[m'!';A!}CP; 3.

&WTTAlff frger e.

Liner teeked 17 At1E, (proposed)

ADAE, CC-2500, A'as, CC-4500, A3E, NRC Regulatory CC-4500, ASE, NRC Regulatory b

allo concrete Section III,Section II Sec. III, Div. 2 See. III, *Div. 2 Ostde 1.19, Besi qdetton III, Div. 2 Ostde 1.19, Dev.1 Division 2 (IWJ)

(1 W I, Si.e.'7J) and and (Proposed - 1W1) and ASE,Section II CC-550C, A3E and CC-5500, A3 E,

(1W1, Sammer '73)

Sae. III. Div. 2 A3E,Section II See. III, Div. 2 (Proposed - IWJ: (1W1, Sammer '73)

Irreposed - IWJ) ani en$

i E-5000. A3dE, IE-5000, ASE, Sec. III, Div. 1 Sec. III, Div. 1 (1W1, Sam. '7J)

(1W), Sam. '73) and and ASE,Section V A3E,Section V (IW1, aan. '73)

-(1W1, Sam. '7J) i I

I b.

Pipe Penetration A34E,Section III' A3dE, NF-2000 ASE, ASE,Section II IE-2000, ASE,

&4000. ASE,

&5000, A3E, Yes llo Sleeves Division 1 (IW4 :

Section II Sec. III, Div.1 (1W1, n=r '73)

See. III, Div. 1 See. III, Div. 1 Sec. III, Div. I with Smuner '74 (1971, Sam.'73:

(1971, Sun. '7J; (ITA, Sun.'7J)

(1W1, Summer '73)

(1W2, hr '73)

Addende) l, e.

Pers9nnel locks A3E,Section III

ASE, NA-4000 &

NE k000, A3E, 6 5000, A3E,

& 4000, AS E,

IE-5000, ASE, 7es Yes Division 1 (1W1 Section II NE-2000, A3E, Sec. III, Div. 1 Sec. III, Div. 1 Sea. III, Div. 1 Sec. III, Div. 1 with Sener '7J (1W1

%=cr Sce. Ill, Div.1 (1W1, Sam. '73)

(IW1, Sam. '73)

(1M1, Sam. '73)

(1W1, Sam. '73)

Addende)

[

'7J)

(1971, Sam ' '7,)

. and

. and and erw$

ASE Section II A3E, See. Y A3E,Section II A3E, Section Y j

(1W2, aus. '73)

(1971, nam. '73)

(1W1, Sun. '73)

(1W1, ass. '73) l a

d.

Equipment flatet.

A!34E,Section III

ASAE, NA-4000 &

NE-4000, A3E, IE-5000, ASE, NE-4000, AS E,

NE-5000, A3E, Yes les Division 1 (1 W 1 Section II 57000, ASE, Sec. III Div. 1 Sec. IIT, Div. 1 Sec. III, Div. 1 Sec. III, Div. 1 3

with Smuner '73 (IW1, Summer Sec. III, Div.)

(1W1, Dan. '73)

(1971, Sam. '73)

(1971, Sam. '73)

(1MI, Sam. '7J)

Addenle)

'73)

(1MI, Sam. '7J and and end eat A3E,Section II ASE, Sec..Y -

A3E, Sectica II ASE, Section Y l

(1W1, Sun. '73)

(1W1, Sun. '73)

(1W1, Sun. '73)

(1W), Sam. '73) a s

e

• C:

i i

l#f er. nces to tlur Ali.tL Co.1< g ar.crn;4e mode thrmetrat this table are for tact.nlent requirements only; meninistrative requirements, such as preparettoo of Design Ipeelfleetion, DestCn Deport, G.h Data lieport, ANI involseneent or stamping, are act inclu$cJ unlees noted In last two columns.

ttattrial Control include: requir mere for Certified Meterls) Test Peports, impmets, identification & treeeability, unless othersloe indleateS.

l l

i

!~

s l

F*AN Table.1.8.c.

Top _2 of _4 (cont'd)

MJIOC IATIFin FA57tICAT133 ERfCTION i

• TI T!T!.7 ::C (2.W1.!.ite 2 s11rIN3 p;ogIhAII3:

3TISIM Iv fa*!c7IJs I

2 Dnren a.

Da;7ression Pool L!siar A!IE, (Prorored)

A3'E,

Equivalent to Equivalent to NN5000, A3E, NJh.4C00, A34E, Ir%$000, A3C, No lesSection III,

&ction 11 N.%2000 & NA.

NB.4000, A3E, See. III, Div. 1 Sec. III, Div. 1 See. III, Div. 1 D! vision 2 (1973) (1W4, Winter 4fE0, A3E, See. Sec. III, Div. 1 (lo74, Win. '75)

(1W4, hr '74)

(1W4, Sammer '74)

'75)

III Div. 1 (1W4, Sameer '74) and an1 and (1W4 Editicm, and ASE, Section Y ASE, Section D ASE, Section Y g

Smener '74)

A3E Section II (1W4 Editaan, (1W4, Sammer '74)

(IW4, %=ar '74)

(IW4 Edition, W 3ter '75)

Winter 1MS) 9 2I ABS DI.1, Dev.1 *N b.

Form Plate AISC 1%9 or 1W8 ASDI-197h Cartified Not Applicable Not Applicable ASE, Seettaa II Nft.3000, AS E,

Na No nesteriel Test (1W4 Edition, Sec. III, Div. 1 Neports Chly h r '74)

(1W4 Edittm, 3

h r '74)

As3 DI.1-New. 1, 1 Wd ens ASE,Section V p

(1974, h r 4)

^

e.

Pipe Penetration A3E,Section III

ASE, NF.2000 & WA.

ASE, Sectlas II NT 2000, A3E, A3E,Section II ub$000, ASE, No No S1beves Div. 1 (1974,Section II 4000, A3E, (1W4, Sam. '74)

Seetton III, (1974, Sam. '74)

See. III, Div. I asumer IW4)

(IW4, Sam. 74)

Section III, Division 1

• 2 (1974, Sam. 74)

Div. 1 (1W4, Sam. '74)

AWS D1.1, peu.1 '76 and (1W4, Sam. '74)

A3E,Section V (1W4, ass. '74) d.

Personnel talk &

A3E, Seetton III,

ASE, IE-2000 &

IE.4000, ASE, IE.5000, A3E, IE-4000, ASE, IE.5000, A3E, Yes No Hetch, Dryugli feed Divisjon 1, Sab.

Section II NA-4000, A3E, See. III, Div.1 Sec. III, Div. 1 Sec. III, Die Sec. III, D e. I section Na, (1W4 (1W4, Sasumer Sec. III, Div.1 (IW4, Sam. '76)

(1W4, Sam. '76)

(1974, Sam. *h (1W4, Sme. '76)

Edition Danner

'76)

(1W4, Sam. '761 est g

and and and

'76 Ad:scrase)

A3E,Section II l ASE, See. Y ASE, Sec. U AAE,Section V (1974, aan. '76)

(1W4, sm. '76)

(1W4 sm. '76)

(1W4, aan. '76)

I i

p.

/

8 s

e m

s

' If l l

,e I

I 3

FSAR Totle 3.8-9 Poit eF

( Cont 'd) g 3,y ag;,Trn;g IAIEI"A71%

IRI3ICK

' l gggyggq gg IN fv3FNATM.

m.m (4

• • 7 BEIMO UMP;ATI'E t?IPInc I'Jy*t47m e.

Reihe 3 Ing" I*11N 3 A!!E, Section IIL A3 F,

.**c.

II, NE.*YU & AA-NE-4000, A3E, NE-$Wi A3E, NE-4000, ASE,

, IE-5000, AM, No IQ Itivision 1 Saw (1 W', Winter 407), A3E, see. III, Div. 1 See. III, Div.1 See. III, Div.1 See. III, Div. 1 section NE, (l'rr7

'776 et. III, Div.1 (1977, Win.' '77)

(18FF, Win. '77)

Pl%74,. Sam. '74)

(1 W4, S m. '74)

E.d tt lan, Winter (1W7, Winter and and and and

'77 AJdcode)

'77)

A M,Section II A3E, Section Y ASE,Section II ASE, Section Y (1977, Win. '77)

(1W7, Win. **f7)

(1974, Sun. '74)

(1974, Sam. '74) 9 3.

FEA'TCH MS"fAL ADE. Section 111, A3E, Sec. II NA-4000. NF-NF-4000, ASE, NF-5000, ASE, NF-4000, ASE, NF-1000, AS E, No No Division 1, saw (3W4, Winter 2000, A3E, Sec. III, Div. 1 fee. III, Div. 1 See. III, Div. 1 See. III Div. 1 section NF (1 W 4

'73)

Section III, (1974,-Win. '75)

(1974, Win. '75)

(1W4, Win. '73)

(1W4, Win. '75) l Edition, Winter Div.1 (1973, and and end

'75 Addenda)

Win. '75)

A3E,Section II ASE,Section V A3E, Sectica V l

(1974, Winter '75)

(1974, Win. '75)

(1974, Win. '75)

(a 4.

FEIR Wall A3E, (I'ruposed)

A3E, See. II, Equivalent to ASE,Section II Erptivalent to A3E,Section II Egulveleet to No Its s.

Liner Section III, (1774, Win.'75) NS-?000 & NA-(1974, Win. '75)

CC-6300, A3t,

(1974, Sam. '74)

CC-$300, A;AE, Division 2 (197J) 4000, A3E, g

Sec. III, Div. 2 3

Sec. III, Div. 1 7eble 3-2 Sec. III, Div.1 AWS DI.1, llev. 1 (Pr3 posed,1973)

ABS D1.1, Jter.1 (Proposed,1083)

(1974, Sam. '74 1 976 and 1 976 NS-$000, AS E,

and NS-3(I)0, A3E, e

See. III, Div. 1 Sec. III, Div. 1 (1974, Sam. '74)

(1774, Sm. '74)

I?AfTT pil'fD 11.11 AISC 3964 or Icr78 ASTts.1W6 Ergulve3ent to ASE,Section II NP-5000, A3E, ASE, Sectican II 3rs.3000, ASE, les geo ND-2000 & NA-(1W4, Winter '75)

Sec. III, Div. 1 (1974, Sam. '74)

See. III Div. 1 4000, A3E, 3

(1W 4, Win. '75) g (1774, Sam. '74)

Sec. III, Div.1 AW3 D1.1, New.1-and AWS D1.1, Bew. 1-an't (1974, Win. '75l 1976 ASE, Sectican Y

1976, ASE,Section V

(

(1 W 4, Win. '7$)

(1974, Sam.'74) 8 e

e e

6.

00'rT 4 f f m.T PCYi A34E,Section III A M, Sec. II Equ!velent to 00-4000, A3E, Equivslent to CC-4000, ASE, Epsivelent to IIo No e.

Stein 3ess Steel e

Lirer Dtvision 2 (1777)

(1977 Edition)

Nft-2000 4 NA-See. III, Div. 2 CC-5500, ASE, See. III, Div. 2 CC-5500, A3E, 4000, A3E, (1977)

(1W7 and (1777)

Sec. III DivJ and and ASE,Section II and (1977)

A3E,Section II ASE, Sectica V (1977)

A3E, Section Y g

A1977)

(19'7)

(17r7)

I a

s.

V' r

g

~

l F.*.8% b t1= 1.8-9 Top 1 of L i

(Cint'd)

IE11 Cab MAGIA1 FA'!EICATICE EAECTION gg

,g3g

~T7 7: F* a7:T; r 2T6 'i-t;?te a aI1rI?el DJJ'DLATICE u? ! ries'.

EvarIr.t713:

t.

Pool Getes UM. Sect ion III A25. Sec. II ND TF10 & NA.

IO-40CD, m, Equivalent to ND-4000, m.

Evalvelent to No 10 0 Division 1 (1777) (IW7 Edition) 4DJO, m, See. III, Div. 1 CC-5500, m,

See. III, Div. 1 CC-5500, m, Gabsection ND Section III, (1977)

Sec. III, Div. 2 (2W7)

See. III, Div. 2 Division 1 eni (1977)

(19T1)

(1777) m,Section II and and (1777) m. Section Y m. Section Y i

(1?T7)

(1 777) t 7

PITT eMIP MP> f f'f*.

AISC (1969 or ASIM-1978 Egalvelent to NF-40CD, m,

Equivalent to NF-4000, m,

Equivalent to No No 1W8)

NATIO0 & MA.

Sec. III, Div. 1 NF-$000, m, See. III, Div. 1 NF-5000, m,

4000, m,

(1774 Bla. '75)

Sec. III, Div. 1 (1774, Winter '73)

See. III, Div. 1 Sec. III, Div. ]

and (1974, Wla. '73) eni (1974. Winter, '75)

(1977, Win. '78; N. Section D and m, Section D and

'(1774, Winter '75) m, Section Y (1974, Win. '75) m,Sec. T (1774, Uta. '75) 8 a.

Oonerete m, (Propsed)

ACI Omtes and AN31 N45.2.5, Ibn Appliemble Not p lieeble Not Appliemble Not App 11eeble No No (Imludes containment.

Teetion III well, drywell well, Division 2 f1773)l Stan3erds Draft 3, Rev. 1

, (Refer to FSut Jon. 1974 weir well, centein-

Tahle 3.8-4) pent pool welle &

rvfuellru; floor sleb) s b.

Refer

m. (Prososed) ACI Cades mas Certified Not Applicable Not Applicable WNC Deguletary Onide, ISIC Negulator[

No 10 0 (Includes same items as ston)

Section III{1773) sten 3erds Material Test 1.10, Nev. 1 Divisten I (Refer to CAR Reports (hly

^

Oelde, 1.10, Dev. 1 Table 3.8-4) g e

4 4

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--m.v.no i DETAIL A CLINTON POWER STATION FIN AL S AFETY AN ALYSIS REPORT FIGURE 3.8-31 DETAILS OF THE-DRYWELL HEAD AND CONTAINMENT P0OL COMPLEX (SHEET 2 of 2)

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L31-82(10-22)-6 i'~

October 22, 1982 l

TO:

J. S. Spencer, T-29 FROM:

J. D. Geie M

SUBJECT:

Specification Interpretation /ASME Boiler Code The purpose of this letter is to record the results of a number of telephone calls that I made to A/Es and others.

We discussed the matter of industry practice (if any) when engineering specifica-tions require limited use of the Boiler Code.

i All parties listed below indicated that their standard practice -for specification writing includes limited use of the ASME Boiler Code when it is convenient or apprcpriate. 'They all agreed that when their specifications say " design and build in accordance with ASME Boiler Code but do not stamp," they do not expect the user of the specifications to have an ANI or equivalent third-party inspection and signoff of the work.

(.h The parties whom I contacted on this matter include the following:

1.

Commonwealth Edison Company LaSalle, Byron, and Braidwood applications Wayne Stiede, Assistant Vice President / Engineering 312-294-3107 4~

2.

Stone & Webster Engineering Corporation Boston Office Charlie Miczek, Chief Engineer 617-589-2002 n:,=..__b.gg 3g,n'd ~ Sea: tion m.

John Fletcher, Project Engineer Charlie Buckley, Project Engineer 3.

Bechtel Corporation Gaithersburg. MD Robert Trickovic, Grand Gulf Project Manager 301-258-3530 J. N. Ward, Project Manager Adrian Zacharia, Project Manager l

4.

Tennessee Valley Authority

(

Knoxville, TN

(.

Dwight Patterson, Chief Engineer 615-632-2247

f.

Y-8604

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L31-82(10-22)-6 J. S. Spencer October 22, 1982 Page 2 5.

Cleveland Electric Illuminating Company Perry Station Larry Beck, Licensing Manager 216-259-3737 6.

Gilbert & Associates Perry Station Office Joe Schatzman, Project Engineer 215-775-2600 All of the above indicated a deep interest in the outcome of this issue.

Bechtel plans to have an observer at our Washington meeting on October 26.

S&W (Fletcher) indicated tFat they may also have someone in attendance.

JDG:dl cc:

R. C. Heider, S&L L. J. Koch, B-25 D. P. Hall, B-16 C.

A. J. Budnick, T-32 G. E. Wuller H. B. Perkins

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...!:n r t.hy 20'1 East Sixth Street,.:AL*E RCO* *I New Castle. Delaware-1972^.

302 328 1371

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October 1r,_1982 Mr. P. K. Agrawal SARGENT & LUNDY ENGINE'RS E

55' East Monroe Street Chicago, Illinois 60603 Clinton Power Station Containment. Liner & Dryweljgg, gy Baldwin Associates for Illinois Power Company D/ TE

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Clinton, Illinois CBI contracts 74-2563 & 73850 S&L Specs K-2816 & K-2896 Gentlemen:

In accordance with our telephone conversation on October 8, 1982, '

we are providing a revised general discussion of the ASME Code material, fabrication, erection, inspection, stamping, and certification for the containment Liner and Drywell work.

This 1etter supercedes and replaces my earlier letter of October 7, 1982.'

Containment Liner Material for the bottom, shell, and roof with embedments and attachments was designed, fabricated, erected, and examined-generally in accordance with the April 1973 proposed ASME Section III, Division 2, Subsection CC.~

No ASME Code-authorized inspection, data reports or stamping was provided.

The personnel locks excluding.the sleeves were shop fabricat'ed in accordance with ASME Section III, Division 1, Subsection NE.

ASME Code Authori::ed Inspection and ASME Code Data Reports were provided.

These locks were stamped as ASME Class MC. vessels.

The 1971 Edition with Summer 1973 Addenda was employed in this work.

All Shop and Field work for the equipment hatch, and Shop work

• for material and/or assemblies for penetration sleeves (including lock sleeves) was inspected by an ASME Code Authorized Inspector and certified using modified ASME

' Manufacturer's Data Reports.

The certification included design to the extent of CBI's design responsibilities, material, fabrication, and examination for compliance with ASME Section III, Class MC rules as defined below.

The 1971 Edition with Summer 1973 Addenda was employed.in this work.

No ASME Code. stamping was provided.

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Mr. P. K. Agrawal Sargent i.Lundy Page Two October 11, 1982 Included in the work certified was:

A)

Penetration sleeves were certified as complying with ASME Section III, Class MC rules for material (pressure retaining),

., fabrication, and examination (if,any).

~

B)

The weld of liner insert plates.to (A) above were' certified as complying with ASME S'ction III, Class MC rul'es for e

fabrication and examination of Category D joints.

C)

Permanent attachments to (A) a$ove excluding attachments backed by concrete and test channels, were certified as complying' with ASME Section III, Class MC rules for material.

D)

The welds of attachments to (A) above, exclusive of stud at'achment welds, were certified as complying:with ASME t

Section III, Class MC rules for fabrication and examination.

Drywell Equipment The pers,onnel lock including sleeve, the equipment hatch,'and the dryw411 manhole were shop fabricated-in accordance with ASME Section III, Subsection NE.

ASME Code Authorized Inspection

-and modified ASME Manufacturer's Data' Reports were provided.

No ASME Code stamping was provided.

The drywell refueling head was fabricated and partially assembled in the shop.

Final assembly was performed in the field.

Design, materials, fabrication, assembly and examination were in accordance with ASME Section III, Subsection NE.

ASME Code

~

Authorized Inspection was provided for shop and field work.

Modified ASME Manufacturer's Data Reports were provided.

No' Code stamping was provided.

The 1974 Edition with Summer 1976 Addenda was used for all the drywell work.

We trust this summary provides the information needed.

Please let us'know if we can be of any further assistance.

,Very truly yours,

,. f l.

_.// !.

-;;.sq v. w.. ~-

RAY E! AKIN i

rNGItiEERING SUPERVISOR l

V i

id

/dr. H. M. Sroka, Sargent & Lundy cc:

Mr. W. J. Harrington, Project Manager, Baldwin Associates i.

Illinois Power Co., Clin, ton Project, Document Control Center l

i

U-0572, q$~Y h ' L30-82(10-29)-6 ILLIN0/S POWER COMPANY j:

1 500 south 27TH STREET. DECATUR, ILLINOIS 62525 October 29, 1982 84 Mr. Cecil 0. Thomas, Chief 3-L Standardization & Special Projects Branch Division of Licensing

$)

U.S. Nuclear Regulatory Commission V

Washington, D.C.

20555

Dear Mr. Thomas:

Clinton Power Station Unit 1 Containment Liner and Reactor Vessel Pedestal Documentation Reviews In accordance with agreements reached in NRC's Bethesda offices on Tuesday, October 26, IP agrees to the following:

1.

An independent review will be performed for the Clinton containment liner and reactor vessel pedestal records.

2.

The liner review will include documentation of exceptions taken to the ASME Boiler Code plus a review of documentation of the work stipulated by the S&L design specifications.

1 3.

For the containment, we will review liner plate and appro-priate appurtenances, but we will not include the air lock, penetrations, or other features for which Code stamph, ANI certification, or independent inspection by the ANI were previously obtained.

4.

For the pedestal, the review will cover documentation of ASME

-- - -- --- Boiler Code requirements stipulated in the S&L design speci-fications.

IP will make suitable arrangements for the documentation review to be performed by an inspection organization qualified to perform ANI-level inspection for ASME Boiler Code work as described in the S&L design specifications.

l O N puff

4 U-0572 L30-82(10-29)-6 Mr. Cecil 0. Thomas October 29, 1982 Page 2 You will be notified when a vendor has been selected to perform this work and when the work is completed so that proper coordina-tion with NRC Licensing can be assured.

Sincerely, b

G. E. Wul er Supervisor-Licensing Nuclear Station Engineering JDG:dl cc:

J. H. Williams, NRC Clinton Project Manager H. H. Livermore, NRC Resident Inspector Illinois Department of Nuclear Safety 4

e O

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