ML20028B519

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License for Transnuclear,Inc to Export 8,580 Mci Cf-252,in Oxide Form,To West Germany
ML20028B519
Person / Time
Issue date: 10/29/1982
From: Jacob Zimmerman
NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP)
To:
References
TNF-422, NUDOCS 8212020198
Download: ML20028B519 (2)
v • d • e


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Paga 2 of 2 Pages U.S. Nt' CLEAR REGULATORY COM%flSSION EXPORT LICENSE Conditions License Number IB001158 Condition 1 - Licensee shall file with the Customs Officer or the Postmaster two copies,in addi-tion to those otherwise required, of the Shipper's Export Dectoration covering each export and mark one of such copies for transmittal to the U.S. Nuclear Regu.

lotory Commission, Washington, D.C. 20555. The following declaration should oc-company or be placed on the Shipper's Export Declarations for such exports:

"This shipment is being made pursuant to specific license number (specific license number) filed at (location of Customs office where license is filed),

on (date license was filed). This license expires on (expiration date of license), and the unshipped balance remaining on this license is sufficient to cover the shipment described on this dectorationf Condition 2 - Exports authorized in any country or destination, except Country Groups Q, S, W, X, Y, and Z in Port 370, Supplement No.1, of the Comprehensive Export Schedule of the U.S. Department of Commerce.

Condition 3 - This license covers only the nuclear content of the material.

Condition 4 - The material to be exported under this license shall be shipped in accordance with the physical protection requirements for special nuclear material in 10 CFR 73.

Condition 5 - Special nuclear material authorized for export under this license shall not be transported outside the United States in possenger carrying aircraft in shipments exceeding (1) 20 grams or 20 curies, whichever is less, of plutonium or uranium 233. or (2) 350 grams of uranium 235.

Condition 6-This licen;e authorizes export only and does not authorize the receipt, phys! col possession, or use of the nuclear material.

Condition 7 - The licensee shall complete and submit on NRC Form 741 for each shipment of source material exported under this license.

Condition 8 - The licensee shall advise the NkC in the event there is any change in the designo-tion of the company who will package the nuclear material to be exported under this license, or any change in the location of the packaging operation, at least three weeks prior to the scheduled date of export.

i

g-

' Illinois Power Company cc w/ enclosure (s):

Mr. L. J. Koch Jean Foy, Esq.

Vice President 401 South Busey Illinois Power Company Urbana, Illinois 61801 500 South 27th Street Decatur, Illinois 62525 Mr. Juifus Geier Illinois Power Company 500 South 27th Street Decatur, Illinois 62525 Sheldon Zabel, Esq.

Schiff, Hardin & Waite

< 7200 Sears Tower 233 Wacker Drive Chicago, Illinois 60606 Mr. H. HI Livermore Resident Inspector U. S. Nuclear Regulatory Commission RR 3, Box 229 A Clinton, Illinois 61727 Mr. R. C. Heider Projset Manager Sargeny & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Mr. D. L. Foreman Project Manager General Electric Company 175 Curtner Avenue, M/C 682 San Jose, California 95125 Reed Neuman, Esq.

Assistant Attorney General 500 South 2nd Street Springfield, Illinois 62701 Prairie Alliance P. O. Box 2424 Station A Champaign, Illinois 61820 Philip L. Willman, Esq.

Assistant Attorney General Environmental Control Division 188 W. Randolph Street - 2315 Chicago, Illinois 60610 4

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SARGElPT & LUNDY ENGINEERS rouwoEo esos as Easr woNRoE STREET CHICACO, ILLINOIS 60603 (3sa) 269-2000 SLLI-746 October 21, 1982 Project No. 4536-02 Illinois Power Company Clinton Power Station - Unit 1 Draft FSAR Changes Explaining the Use of ASME Codes on Structural Design Mr. Herb Williams Licensing Project Manager Standardization and Special Projects Branch Division of Licensing Office of Nuclear Regulation Room 340 7920 Norfolk Avenue Bethesda, Maryland

Dear Mr. Williams:

As requested by Illinois Power Company, I am sending you a copy of the draft FSAR revisions for Section 3.8.

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

Yours very truly,

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(,.,ip s ej.

9 8 m,:,

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Michael Launi CML:aab Licensing Engineer Attachment Copies:

H. Livermore (1/l)

J.

D.

Geier (1/l)

J.

S.

Spencer (1/l)

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~~

G.

E.

Wuller (1/l)

B.

Erler (1/l)

R.

C.

Heider (1/l)

'~~

R.

A. Witt (1/l)

'~

P.

K. Agrawal (1/l)

NSLD File:

1C-10a File:

2.4.1 - S&L e

k 4

1

=

)

O) i p /[

CPS-FSAR

-l a.

pedestal cavity area:

6 feet 0 i ch;

,/

a b.

sump floor area:

9 feet 0 inch; a suppressio'n pool area:

3 feet 0 inch.

c.

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 problems.

3.8.1.1.5 Polar Crane Girder Brackets The polar crane girder is located just 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 Codes, Standards, and Soecifications This section lists codes, specifications, standards of practice, Regulatory Guides, and other accepted industry guidelines which are adopted to the extent applicable, in the 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

. specification reference number.

The reference numbers for the

.(

containment are:

through f; ~7 -f 9

a.

14 b.

11 through X ; -30 thcwyh W 16/ 77 lS 2-LI i

j j

%9 c.

23, 25, Jef J4',

35, 36,'38 through 41; and 47 d.

43, 44, 4 6, pdd 4 8 W So j

the provi' pions of Articlg CC 3000 of ASME B&PV Codg, Sec.

Al]

Div. 2{ are followed in the design of't e containm nt b g g,4 II]

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

VEU'"

f the'/

\\

landPresureVessejCode,fproT.ft Y

The pr isions 1971 ASMK Boilp Sec ti n III, Div.ision 1, with sbmme( of 1973 a de 'da are adopted b b2

  • forp enetration kleeves, thepersonnelairlockh/ndequipment hatth.

\\'

j 3.8.1.3 Loads and Loadino Combinations The containment structure is designed using th.e loads, load combinations, and load factors listed in Tab;1e 3.8-1.1..

Loads and Icad combinations listed in Table 3.8-1.1 are used for the design of the steel liner and liner anchors, but the load factor for all load cases is 1.0.

3.8-6

~

. CPS-FSAR The desig.( nd analys s procedure are,1 1 comp-l ce th th requir ments,of Article CC-30 g F the A

'2. /

U.B&VPCkde, E

Se )t 6n II

, Dpision;O Throughout e analysis, special attention is given to the fol-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 O'.y

.The method of analysis 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.

Overall 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 results 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 J

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 clab is also analyzed using the c6mputer progra'm'CSEF-III to contirm the results from the finite-element analysis.

3.8-8 i

)

CPS-FSAR AMENDMENT 8 OCTOBER 1981 Except for the allowable tangential shear stresses listed in Subsection 3.8.1.5.1.1, all reinforced concretepie in accordance with Article CC 3400 of ASME B&PV Code, Sec. III, Div.

2.

3.8.1.5.1.1 Tangential Shear OA The containment is designed for the peak tangential shear.

The tangential shear stress capacity of concrete v is limited to 40 l

e psi and 60 psi respectively for the, service a,nd f,actored load i

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 sPV discharge loads, l'

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, I

and Code Class MC penetration assemblies, are designed in accordance with Subsection NE,Section III of the ASME E&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 ths following list of figures from Section III Div. 1 of ASME B&PV Code:

a.

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

normal and upset conditions, Figure NB-3222-1; 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 Desien

~

All head fittings (cover plates of flued head's), -whi'ch'hre 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.

3.8-11

CPS-FSAR AMEt:DMENT 8' OCTOBER 198'l

~

l 3.8.3.2 Acolicable 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' and standards are listed and discussed in Table 3.8-4 and given a reference number.

For each structure internal to the containment, the reference numbers are listed in Subsecti'ons 3.8.3.2.1 through 3.8.3.2.4.

T 3 s '8 - R fves * /kli n t' dw

& My, nw,

p s, a m '

m * ~ f m n

m

-wn.

m; Ja <<

D A

m 4 M -~

W

/M4 yd

~

L 4m m p.i1 9 % "%

^%,

k y

9 e

eulm e

M*

e G

~

CPS-FSAR AMENDMENT 8, OCTOBER 1981-

~ '

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

25 Land 20 'or reactor pedestal; A

a.

f b.,

21 and 23 for reactor shield val'l; and 28, M 41, 43, Aoi and 47 for both' reactor c.

pedestal and reactor shield wall.

_ Item: 25 Cnd 25 Cra acL ueell-able f v't i. uav Lm shiald wall. M 3.8.3.2.2 Drywell Structure

~

The reference numbers are as follows:

1 through [; 74N 9 }

a.

tt4

~

b.

11 through -M; 16, M lh 2 q; j

c,.

21, 23, 25 A)% 28; and d.

&+, 35, 38, 41, 43, 44, 46, 47, 48, and 49.

m 3.8.3.2.3 Miscellaneous Platforms and Galleries, Refueling Floor, Eculpment Rooms, Suoeression Pcol Weir v

Wall, Process Pipe Tunnel, and Structurai Support System for Recirculation Pumps The reference numbers are as follows:

C a.

1 through F; 7 9'j 14 b.

11 through 3&; 16; 17, If 7Cj j

c.

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

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

3.8.3.2.4 Containment Pool The reference numbers are as follows:

s i

'a.

1 through y; 7 9 9

)'

~

  • ~ - '

/ 1 i

tu b.

11 through OG;

/6,I7,iE,2.Dj QGC i,

21, 23, y 2 5tL E+,

28, M, 35; and c.

l d.

37, 38, 41, 43, 44, 4 6 ', 47, and 48.

m f

\\

3.8-23

~

v CPS-FSAR RMENDMENT 8 OCTOBER 1981 f

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 of the pedestal.

Two Sargent & Lundy shell-of-revolution programs, SOR-III and DYNAX, are used for analysis.

The seismic and pipe rupture forces

~

transmitted to the pedestal are included in the design as. shears 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 so proportioned that the pressure suppression efficiency is not impaired by the deflection of the weir wall under design loads.

3.8.3.4.4 Refueling Floor, Miscellaneous Platforms and Galleries, and Support System For Recirculation Pumps The platforms, galleries, and structural supports for the recir-culation pumps are designed using conventional elastic design

(

methods.

3.8.3.5 Structural Acceptance Criteria 3.8.3.5.1 Reinforced Concrete Deformations of the drywell structure, containment pools,,and 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 when the effects of thermal gradients are considered.

For section analysis, the strain in the reinforcing steel and 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

.I strain is 0.002 in./in.

the specified concrete compressive strength.and the stress is 0.85 fy, tensile ; is where f The strength of the concrete is neglected.

j,.

(

y a u x s G (,,

, g,e Except for the allowabic 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 318-1971.

Servicability checks are made in accordance with ACI 318-1971 to assure crack contro1 and to keep deflections below the limits prescribed in ACI 318-1971 or to the manufacturer's 3.'d-23

CPS-FSAR r-for each unit are in their cwn missile-protected cubicles.

Each cubicle has its own cooling unit which is electrically segregated

~

from the others.

Each cubicle is flood protected by bulkhead

. doors.

No single f ailure 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 Apolicable Codes, Standards and 'Soecifications The codes, standards and 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:

5 1 through H; 7,5,9 j l1 -iQ l'lj IG,17,18 j a.

23,.25 c Es,6 45 b.

21, j

and 28; c.

31,4F&r 35, 37, 38;gand 43 V4n-446 f

41fthro' ugh 48.

d.

j 3.8.4.3 Loads-and Loadino Combinations C

The list of loads and their definitions and the loading combina-tions applicable to the design of Seismic Category I structures

.outside the containment are given in Table 3.5-1.2 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., ficots 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 wi-thstand suction pressure induced by 'the design wind 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 gradients, and pipe rupture loads, wherever applicable.

Floors and roofs are checked for their ability to transfer -she,a.t.through-diaphragm action.

' The walls, interacting with the floor slabs, "are designed to withstand the effects of seismic induced shears and mom All walls are designed for external and internal missiles, ents.

transient thermal gradients, tornado-induced pressure, lateral soil and hydrostatic pressure and pipe rupture loads, wherever applicable, in addition to their own welaht and associated loads from slabs

(]}

and beams framing into the walls.

For the design cf subgrade walls a surcharge load of 500 psf or AASHO H-20 wheel loading considered.

is

e.

t CPS-TSAR AMENDM NT I a

e OCTOBER 1981 e,

. TABLE 3.8-4 LTST OF SPEC!rICATIONS, COOES AND STANDAPDS SPEOI-SPEC!rICATION FICATION CR REFEPENCE STANDARD NLH B E R

_DESICNATIOM TITLE EDITION REMARFS

  • ~

ACI 318-71'i~77au11 ding s ade Requirements for

'4NNH Appendix *A*

adopted 1

. Supplerent 1974 Reinforced Concrete jg 7/ gV 7,7 for seismic design v' 2 ACI 301-72 Specifications for Structuaal 1973 e

Revision 1973 Concrete for buildings b3 ACI 347-68 Recommended Practice for Con-

.heea, 1968 ANSI A145.1-1968 crete.Forr rk 4

ACI 305.".4 ~If-Reconmended Practive for Hot

-4+M'" ! S 7 b ANSI A170.1-1972 Weather concreting ACI 211.1-M Recommende? 'ractice for 444+ M 'l N 5

"NC c ; ',7 1 - l++t-Selectint.roportions for

~

Normal Neaght Concrete e

6

--?f! f;4 - 7 5 rw.v--su.ua i..w....

10?:

_r:::;:1--

e--

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

ACI 306-66 Reconnended Practice for Cold 1966 Weather Concreting 9

ACI 309-72 Recommended Practico for

-Susch, 1972 Consolidation of Concrete Title 69-56 10

- A; 4...

e.

...m

, c.._

^

  • "c'

'15? I."':

..s

...; 1...

.w.......

'm.

,/

11 ACI 303-71 Recomnended Pra-tice for 1971 Curang Concrete title 69-1 12 ACI 212 Cuade 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 Co pression Test Results of Field Ccocrete 14 ACI 311-64 Recome. ended Practice for 1964 Concrete Inspection 15 cAC" !? :

n:nu:1 -' "- -- -

ta-----

10C0

_re.w cas n..

16 ACI 304-73 Reco sended Pract:ce for. Mea-1973 suring, Mixina, Transcortir.g and Placing Concrete 17 Report by Placing Concrete by Pumping' ACI Journal ACI Committee 304 Methods May, 19 71 Title 68-33 18 Re por t by Strength Evaluation of Existing ACI Journal

}

ACI Co nittee 437 Concrete Structures

-Nov 19b7 a

Subcor.mittee 1 Title 64-61' 19 Deleted

'-~

20 ACI-ASME-359 ASME Boiler & Pressure vessel Code,Section III, 01 vision 2

  • ' 1973 Issued for trial use and' cc'm.me n t Concrete Reactor vessels and Containments
r. s AJSC-69 c[rl[ Specification for the Cesign.

J:L.

'0, 1969 v# li ') [

s./

21 Tabrication, and Erectaen of Structural steel for Bat 1 dings N

Sheet 1 of 3 9

s CPS-FSAR A. MEN;MgN3 8 OCTOBER 1981 TABLE 3.8-4 (Con t'd )

'e9 SPECI-SPEC!r! CATION FICATION OR REFERE?;CE STA12DARD e

NUMEER DESTC*IATION TIT!,E EDITIO?!

REMARKS 22

-@^--

F ;i4 4eee4en-fete-t6 A.. g v.~

. 14 M @t 2:;; Cc!d-Fema-ed-Steel *

=4t e _r-1'--M

_. A DI*I

, Structural welding Code 1976 *#

D 23 24 g..-e -- ------ -

;;.._.;. d e4.ps --- ; r -

i 'aldiny

)?ff.

~

.. i. gem

_A n lG Eon,am-Re-M e F w a-u r ~ - ;,.,;-...,

g 25

.M.MG--

_10. T.;- : :....

M

fi'.;

W.... : '..

~

p w_m j -

e

!a

2..m t,N ;.. _ ;

P + --

.r-26 y.. :} M. m '-% n.. :ua.. :

...-J.

n.v.r

__e--.t--

...-. a m,

'. " ? 2 '.dd ende.

27 X.-

m=C a., :........ '- - :

--.. m mess.nf,a c.....

.~..s.

~

..- : W;.:_

s.,

4q4, _.... :P2 6..

.w w ;

-_._ -.m 28 ASTM Annual Books of ASTM Standards

-2177" 29

""r!

251...^

.. 1. J ; L....

m.

y_g p --

e..

m s.~,..

a t. < ~_.

30 n,

e,-

ep-rat ~. w w _.i q n--i 3, ;;3

_r n e.m...-

y 31 UBC Uniform Building Code 1970 d M ~I $

32

'-*'--_-1 E1:st+io Ccd:

1;t.;t-attton~

33 UJ '--

--M

et est--
  • ==regelet tons-ea t e n-r esoect-to edit aon.- -

M redging ashi4 onstructaons==

34

,31eiger.Occa;atirins.sd et"

' = test --

-and.Healt.h-ACT

"*~

35 23nc Regulatory Mechanical Cadweld Snices in Feb. 1. 1971 Withdrawn by the 2;RC =l Guide 1.10 Reinforcing Bara of Ccacrete 7/8/81 Containments t

36

""n"- T.. :,. :.- t.cy Instrun.entation for-Earth.;.ubs Re

.~L, Cei4J 1:11 *

.Apr. 1974,

j 37 NRC Regulatory Fuel' Storage Facility Design Rev. 1 4

6 Guide 1.13 Basis Dec. 1975 l

38 13RC Regulatory Testing of Reinforcing Bars Dec. 28. 1972 Withdrawn by the : RC ~,

Cuide 1.15 For Concrete Structures 7/8/81 (revision 1) t_

39 1 P.C Regulatory Structural Acceptance Test for Dec. 28 *1972 Withdrawnbythe2;RC$

Guide 1.18 Concreta Pri.ary Pcactor Con-

..,. 7/8/81'*

l tainr.ents (Revision 1)

'e 40 NRC Regulatory Nondestructive Exa.anatiens of Aug..ll. 1972. WithdrawnbytheNRC(

Cuide 1.19 Primary Contain ert Laner Ecids 7/8/81 (Revissor. 1) i

'~'

41 M C Regulucry

.',u211-/ Crow Clasnficat':ns -

. -747 3.

Calde 1..'4 an.1 Standards Ta'.p.' 197G i

42 MN -f==,u 1 *.t:.,

,..~..
1.. - ;.. A A..

e.-

e p

.Cuid a ' "-

,: e... 17 - -

Y 43

!JRC Regulatory Seismic Design Classification Rev. 3 Cuide 1.29 Sept. 1978 I

Sheet 2 of 3

~

e Changes to FSAR TABLE 3.8-4 No.

Standard Title Edition Remarks 25 ASME ASME Boller and 1971 with for Containment Pressure Vessel Summer 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 Code,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 TsEME Boiler and 1977 for Fuel Pool i

Pressure Vessel Liners Code,Section III, Div. 2 enan 4 y

+

i e

n t

e

,a,

,-e,--

9 CPS-FSAR

- AMENDMENT 8 s

OCTOSER 1981 e-TABLE 3.8-4

- (Cont'd)

SPECI-SPECIFICATION

  • . ****
  • TICATION OR REFE RENCE STANDAPD

==, 3 NUMBER DES! CHAT!C.

TITLE EDITION REMARKS 4

17.,0.. " 4.. NRC Regulatorg

.%ntrol of Stainless Steel R*V.

3e j-Guide 1.11 dalding APr. 1976 q#""

45 NRC Regulatory Control of Elecircstag Dec. 28, 1972 Cuide'l.34 Nc1d Properties g

~

  • i 46 Chs1 Manual of Standard Practice 1973 T"

47' *

  • ANS'I N45.2.5 Proposed Sup
  • ementary CA 1972 1972 Requirements Tor Installation.

Inspection and Testing of Structural Concrete and 0-structural Steel during Con-struction Phase of Nuclear Power Plants 48 -*

NRC Pegulatory Concrete Placement in Category Rev. O.

Withdrawn by the NRC'

    • Cuide 1.55 I Structures June 1973 7/8/81 49
  • NkC Regulatory Design Limits and Loading June 1973 Guide 1.57 Combinations for :!etal Primary Reactor Containment Systeem cnd Component:

50 NRC' Regulatory Materials for Concreta Oontain-Rev. 1 Guide 1.136 ments (Article CC-2000 of the Oct. 1978 Code for Concrete Reactor Vessels and Contain ents)

I

l.. :

Explanation of Abbreviations

j.,..

7.:

ACI American Concrete Institute

, AISC American Institute of Steel Construction

  • AISI American Iron and Steel Institute American National Standards Institute ANSI American Petroleum Institute API American Society of Mechanical Engineers AGME American Society for Testing and Materials ASTM American Welding Society AWS d

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

[~

Uniform Building Code UCC d

Sheet 3 of 3

l i,

g l,

N I'i' 1 CI 4 EAR Table 3.8-9 7

(ree Note 1)

DUIZ ETi;I;/

FAFICATIJN ERECTION l

I g

.rj q s7 f; w I

. y.7,. ; _?,-

gt t, :n ;

tyjutsx;;<y:

g7 t.yyy, gygg;;;g;c,;

3.

9:TA TW?*'

NRC Regulatory No

  • M,3 a.

Linar tecked t'y AGE, (proposed)

AGE, CC-2500, ADE, CC-4500, Aac, NRC Regulatory CC-4500. A3E, 021de 1.19, Rev.1 conerate T+etion III,Section II Sec. I!!, Div. 2 Sec. III. Div. 2 021de 1.19, Resl gietion III, Div. 2 D1visten 2 (1973)

(1W1, Sun. '7J1 an!

an!

(Proposed - 1W3) an!

A3E,Section IX CC-550C, A3E and CC-5500, ASE, (1971, 32mer '73)

Sac. III, Div. 2 ASE,Section IX Sec. III, Div. 2 (Proposed - IWJ:

(IWI, Smmer '73)

(Proposed - IW3) an1 an$

NE-5000, MIE,

NE-5000, AG E,

g Sec. III, Div. 1 Sec. III, Div. 1 (1W1, Sam. '73)

(1W1, 32m. '73) and ers!

ADE, S*etion V A3E, Seetton V (1W1, 32m. '7J)

(1M1, Sam. '73)

I b.

Pipe Penetratian ASE,Section III

AGE, NF-2000 ASE, ADE,Section IX NE-2000, A3 E,

NE-4000, A3E, NE-5000, A3 E,

Yes No Sleeve s Division 1 (1974 Section II Sec. III, Div.1 (1WI, 32mer '73) fee. III, Div. 1 Sec. III, Div. 1 Sec. III, Div. I with Summer '74 (1771, 32m.'73:

(1971, Sum. '73:

(1(r[1, Sam. '73)

(1WI, 32sumer '73)

(1971, Sumer '73)

Addenda) c.

Pars?nnel locks A!1E, Saetion III

ASE, NA-4000 &

NE-4000, A3E, NE 5000, A3E, NE-4000, A3 E,

IE-5000, A3E, Yes Yes Division 1 (1W1 Section II NE-2000, A35, Sec. III, Div. 1 Sec. III, Div. 1 Sea. III, Div. 1 Sec. III, Div. I with Smrw r '73 (1W1, 32mer Sec. III, Div.1 (1WI, 32m. '73)

(1W1, 32m. '73)

(1WI, Sum. '73)

(1WI, 32m. '73)

AManda)

'73)

(lo71, Ams.7) and and and and ADE Section IX ASE, Sec. V ASE,Section II A3E, Section -Y g

(1 WI, 32m. '73)

(1WI, Sum. '73)

(IW1, Sas. '73)

(1WI, 32m. '73) 1 Equipment Hetet.

ASE, feetion III AD.ft,

NA-t/inD &

NE 4000, ASE, NE-5000, A3fE, NE-4000, A3 E, NE-5000, A3 E,

Yes No Division 1 (l'#71 Section II NE-TOOO, ASE, Sec. III, Div. 1 Sec. III, Div. 1 Sec. III, Div. I rec. III, Div. 1 with 32nar '73 (1W1, 3msner Sec. III, Div.1 (1W1, Dmn. '73)

(1971, 32m. '73)

(1W1, Sam. '73)

(IM), Sm. '73)

Adienla)

'73)

(IW), Sum. '73 and and and ani A3E,Section IX ASE, Sec..V.

ASE,Section II ASE, Section Y (1 WI, Sun. '73)

(1WI, Dam. '73)

(1W1, Sun. '73)

(1W1, S m. '73) 4 i

T

^

i+1ere nces ta the A;1E Coir parvr%r.c meda thrau;trat this table are for tactatest requirements only; administrative requitvinents, such as tervparation of Design Ppecification, DesiCn Report, G.h Data faport. 7Ji! Invcement or stesping, ar-not includej urd*cc neted in la::t two columns.

unte r;al Control imlofe:; requ!wmeror for Certified MsterIs1 Test Peperts, impsets, identification & treceability, unless ottmerwise indleate3.

s t

I 2

K AP T *

  • h 1. S-9 I'2 _ cf _4 (Cent'dt
  • C;Z

%U,: *4 FA5F;CATIZ EPJCIION i

IU

. n - "- 1J -.

ry:

_._t e ;

all-O E 7.w!M110*

El m t w.'T*p; yJ

=

PP.iT~* 1

.l a.

.upp rers!cn Poel L!rer AJE, ( Prepor-3 )

A3C.

Emivaler.t to Equivslent to h% 5000, A3 E, Np-4000,A3E, NN5000, ASE, ho No Section III, Section 11 Nk200 & KA-NN4000, m.

See. III, Div. 1 Sec. III, Div. 1 Sec. III, Div. 1 D!vicion 2 (17'3) (1 ~4, Winter 4rra, m, See.

See, III, Div.1 (lo74, Win. '75)

(1774, Sucener '74)

(1074, Smeer '74)

'75)

III. Div. 1 (1W4, Sx:ncr '74) an1 ani an$

(1774 Edition, an1 m,Section V A3E, feetion II ASE, Section Y SA v r '74)

A3E rection IX (1W4 Edition, (IW4, amner '74)

(1W4, Smraer '74)

(1W4 E31 tin,

Winter '75)

Winter IWS) 4 52 ABS DI.1, Rev. 1 7t.

b.

Forn Flota A!SC 1%Q or IMS A'N-IT6 Cartified Not Appliemble Not Applicable ASE, Sec tion IX ND-5000, A3E, N3 E) ntsterial Test (IW4 Edition, Sec. III, D!v.1 Reports Qtly amenar '74)

(1074 Edit!co, 3

Smeer '74)

AWS DI.1-Rev.1, IWt an$

A3E, rection V (1W4, nrmer '74) 4 e.

Fire Penatretion ASE, S*ction III, ASE, NF-2000 4 NA-A3E,Section IX NF-2000, ASE, A3E,Section IX NN5000, ASE, N3 No Sh eves Div. 1 (1 W 4,Section II 4000, ASE,

(IC74, S m. '74)

Section III, (1074, Sm. '74)

See. 111, Div. 1 Cerser 1774)

(1W4, 3rn. 741 Sect!an III, Division 1 3

(1074, Sm. '74)

Div. 1 (1974, Sm. '74)

ABS DI.1, Rev.1 '76 and (1W4, Sm. '74)

A3E,Section V (1074, a m. '"/4) 1.

Personnel Ich 6

~t t.7E.Section III AGE, NE-2003 &

NE-4000 ASE, NE-5000, ADE, PE-40CV}, ASE, h?-5000, A3E,

Yes p2 Hatet, Drywa;11 Fea3 P!visie'n 1, 32b g Saetton II KA-400), A3E, Sec. III, Div. 1 See. III, Div. 1 Sec. III, Div. 1 Sec. III, Div. I seet un ha, (1 774 (1074, Smner See. III, Div. J (1W 4, Sm. '76)

(1W4, Sm. '76)

(1974, Sm. '7$)

(1074, On. '76)

Idttien, Sm ncr

'76)

(1974, 3rn. '76) and and an3 anS

'7c Adder %)

ADE,Section IX l A3E, Sec. V A3E Sec. IX A3E,Section V e

~

(1W4, an. '76)

(1W 4, am. '76)

(1W4, sm. '76)

(le74, Sm. '76)

.l f

c l

s l

l o

3 4

g F::AR Tabla 3.8-9 For er e

(Cont'd)

A':I l NAMFIN".,

II Iy; w.77TIA1 T E :"ATI Z ERE *II3 IN ri - r : -

y.

cz - u.-,,

ste: 3 D;rn; FK svI; Iw3 Iv/ar u7p:

1 Pe M3 !r( T.11,e s A:15, rection IIT, m, Tec. II, NE ?'YD & NA-NE-4000, A3E, NE-5fD' M, NE-4000, A3E,

.NE-5000, M,

Ne Q

Iivir!an 1, mW (IT, Winter Arm, m, Sce. III, Div. 1 Ere. III, Div.1 Sec. III, Div.1 Sec. III, Div. I

~

rection NE, (l e

'77*

  • e. III, D!v.1 (1877, Win.' '77)

(187, W in. **e?)

PI'774, Sm. '74)

(1974, Sam. '74)

Edit ion, Winter (1W7, Winter eni and and and m Allenda)

'~r7)

AM,Section IX A3E, Saet ion Y A3E,Section II M, Section Y (IW7, Win. '77)

(1777, Win. '77)

(1974, Sam. '74)

(1974 Sm. '74) 9 3.

HA*Tra FT MI*

A:2/5,Section III, A M. Sec. II NA-4'YJO, NF-NF-4000, A M,

NF 5000, A3E, NF-4000, AM, NT-5000 A M,

No No Division 1, 32b-OW4, Wtnter 2000, A M,

Sec. III, Div.1 Sec. III, Div. 1 Sec. III, Div.1 See. III, Div. 1 rection NT (1W4

'75)

Section III.

(197QWin. '75)

(1774, Win. '75)

(IW4, Win. '75)

(1W4, Win. '75)

{

T.11tfon, Wir.ter Div.1 (IW5, and and and

'75 AMenda)

Win. '75)

A M,Section IX A3E,Section V A M, Saetion V i

(1974, Winter '75)

(1974, Win. '75)

(1774, Win. '75)

Teh 4.

FEIR Tall A3ff, (Preposed)

A M, See. II, Equivalent to ASE,Section IX Erp11 valent to A3E,Section II ET11hlent to No 163 s.

Liner Section III, (1974, Win. '75) NN?OOO & MA.

  1. 1974, Win. '75)

CO-4$0), A X,

(1774, Sm. '74)

CC-5500, AS E,

Divlaton 2 (1973) 4000, m,

2 Sec. III, Div. 2 2

See. III. Div. 1 Table 3-2 Sce. III, Div.1 AWS DI.1, Rev. 1-(Propowd, IW3)

AWS D1.1, Rev. 1-(Proposed,1083)

(1974, Sun. '74 IW6 and 1776 and NN507), A3E, NN5000, A3E, t

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

(1774, Sun. '74) a 5.

FIFTP ""f!T13 Ull AISC ICM or le79 ASW-1W6 Equivalent to A M,Section IX NN5'vD, A3E, AM, Secticra IX NN5000, A3E, No No NN2000 & NA-(1774, Winter '75)

See. III, Div. 1 (1W4, Sm. '74)*

Sec. III, Div. 1 4'YO, AST, 2

(17'4, Win. '75) 2 (1W4, Sun. '74)

Sac. III, Div.1 A33 DI.1, Rev. 1-and AW3 DI.1, Rev. I-an!

(IW4, Win. '75 1976 A3E, Section Y

1776, A3E,Section V I.

(1W 4, Win. '75)

(1774, Sam.'74) t t.

00'rTAir?'"7 P71 A M,Section III ASE, Sae. II Equivalent to 00-4000, A3E, Equivslent to CC-4000, A3E, ETaivalent to No No e.

Steinless Steel e

tirar Division 2 (1 7 )

(1977 Edition)

NN2000 & NA-Sec. III, Div. 2 CC-5*CO, A M,

Sec. III, Div. 2 CC-5500, A M,

4000, A3E, (1977)

(1777 and (1977)

Sec. III, Div.2 and on$

A M,Section IX and (1 777)

A M,Section IX A3E,Section V (1777)

A3E,Section V i

A1W7)

(17""7)

(1777)

- - ~ ~ ~ '

5 I

I lf l

t.7h1ela 1.8-9 T c 1 of L

( Cimt 'd)

IifION u;,ngin FA3P.ICATIO!;

ERI*IION gy m,ggg II*~

t :rIcn: r.

cr : 1.?,et. ;

am!?,;

DJJ'!uTIm sT rit, Is;;*;u Ion t.

Pool Getes AM,Section III m. Sec. II ND-2000 & NA.

ND-4000, m,

Equivalent to ND-40rO, AI3E, Equivalent to No No Division 1 (IW7) (1W7 Editions 4030, m, Sec. III, Div. 1 CC-5500, m,

Sec. III, Div. 1 CC-M00, m, Datsection ND Section III, (1W7)

Sec. III, Div. 2 (2W7)

Sec. III, Div. 2 Division 1

  • ani (1W7)

(1W7)

(1 777) m, Seetlan II and ani (177/)

m Section V M, f*ction V (IW7)

(1 717) 9 7

PIPE rdIP W 4%

AISC (1%4 or ACIlf-1W3 Equivalent to NF-40rK), m, Equivalent to NF-4000, Al3E, Equivalent to No No Icr78)

N N2000 & NA.

Sec. III, Div. 1 NF-5000, m, Sec. III, Div. 1 NF-5000, m,

4000, m,

(1W4, Win. '75)

Sec. III, Div. 1 (1774, Winter '75)

Sec. III, Div. 1 Sec. III, Div. 1 and (1W4, Win. '75) and (1714, Winter, '75)

(1W7, Win. '78]

m, Sectfan IX and m,Section IX and (1W4, Win. '75) m, Sec. Y

(,1774, Winter '75) m,Section V (1974, Win. '75)

[

8 a.

Concre ta j m, (Propsed)

ACI Codes and ANSI N45.2.5, Not Appliemble Not; Applicable Not Applicable Not 1.pplicable No No (Ireluks contaiment 1 T+ction III, usil, drfwell well, Division 2 (IW3)j Stanlards Draft 3, Rev. 1 (Refer to ym Jan. 1W4

, eir wall, contain-

. Table 3.8-4) w rent pool wsils &

refuelirg floor r. lab).

V b.

Pear A3.E, (Proposed ACI car sai Certified Not Appliestic Not Applicable NRC Regulatory Oulde, NRC Regulatorf No No (Includes same itmsSection III, standards.

Waterial Test 1.10, Rev.1 Ouide, 1.10, as sto w)

Division 2 (1%, ) (Refer to DS/J Reports Only

~

Rev. 1 Table 3.8-4)

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C0tlCRETE BUILDING STRUCTURE CONCRETE PORTION SPECIFY - ACI CODES AflD STAllDARDS - ANSI N45.2.5 SUPPLEMENT WITH - ASME SECTION III, DIV, 2 (TRIAL USE AtlD C0l?1ENT ISSUE) LINER NON-LOAD CARRYING REFEREtlCE - ASME SECTION II ASME SECTION III, DIV 1 ASME SECTION III, DIV, 2 ASME SECTION IX TECHNICALLY MOST APPROPRIATE STANDARDS ASME NOT SET UP TO IMPLEMENT COULD NOT REFERENCE ANY ASME CLASS IN ITS ENTIRETY \\ 1 m

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ve t % es PLAN AT BOTTOM CP DEDESTAL CLINTON POWER STATION FIN AL S AFETY AN ALYSIS REPCRT FIGURE 3.8-26 REACTOR PECESTAL DETAILS (SIEET 1 of 2)

STEEL BUILDING STRUCTURE RPV PEDESTAL ASME SECTION III - NF BOUNDARY AT RPV SKIRT - PEDESTAL INTERFACE PEDESTAL A BUILDING STRUCTURE SUPPORTS STRUCTURAL FRAMING FILLED WITH CONCRETE PIPE WHIP RESTRAINT SUPPORT SUPPLEMENTED - AISC REQUIREMENT WITH ASME PLATE AND SHELL REQUIREMENTS \\ i 't l

OTHER STRUCTURES 1 -P0OL GATES - NOT ASME COMPONENT PART OF CONCRETE STRUCTURE-ASME TECHNICAL REQUIREMENTS ARE APPROPRIATE PIPE WHIP RESTRAINTS - NOT ASME COMPONENT (NF-1110) 4 1 e I~ 4 1 ,,,-.,-r,.-- ,,,,, ~,. - - -.

SUMMARY

CODE AND STANDARDS CLINTON STRUCTURES e WHEN APPROPRIATE EXISTING STRUCTURAL STAtlDARDS ENilANCE BY: REFEREilCING TECHNICAL REQUIREMENTS OF ASME REFERENCING CODE AtlD STAf!DARDS UNDER DEVELOPMENT ADDING OTHER SUPPLEMENTARY REQUIREMENTS e EXCEEDED REQUIREMENTS OF STANDARD REVIEW PLAN e CONSTRUCTED SOME AS ALL SAFETY RELATED STRUCTURES UNDER QC/0A PROGRAM MEETING 10CFR50, APPENDIX B ANSI N45.2 4 9

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i ) C?- Y-8604 L31-82(10-22)-6 October 22, 1982 TO: J. S. Spencer, T-29 -FROM: J. D. Geie

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. 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 appropriate. 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. (5 The parties whom I contacted on this matter include the following: 1. Commonwealth Edison Company LaSalle, Byron, and Braidwood applications Nayne Stiede, Assistant Vice President / Engineering 312-294-3107 4 2. Stone & Webster Engineering Corporation Boston Office Charlie Miczek, Chief Engineer 617-589-2002 --- 2t : c=W2Rfver~ Bend ~ Station - 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, Proj ect Manager Adrian Zacharia, Project Manager 4. Tennessee Valley Authority ( Knoxville, TN L. Dwight Patterson, Chief Engineer 615-632-2247 I

f Y-8604 C 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 that 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 t 'k -~ =2:' n~s ':.~ := ~ : ~ ::.

R E C ElV E D. ~i r t u.. -t s,. s ....:cr.g o ! :..is p :. !; c a. C o m pt.iiy l t.. :. ...:.NT"Bi LTH :T//. 801 East Sixth Street.! AI *E RCO! New Castle, Delaware-197p, / C,7 302 328 1371 October 11',_1982 Mr. P. K. Agrawal SARGENT & LUNDY ENGINEERS 55' East Monroe Street Chicago, Illinois 60603 Clinton Power Station Containment Liner & Drywe lhlS. BY / Baldwin Associates for 3 Illinois Power Company DATE 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 Containme..t Liner and Drywell work. This letter 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 fabricated in accordance with ASME Section III, Division 1, Subsection NE. ASME Code Authorized Inspection and ASME Code Data Reports were l provided. These locks were stamped as ASME Class MC. vessels, j The 1971 Edition with Summer 1973 Addenda was employed in this l wo Ls. I 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 l dcsign to the extent of CBI's design responsibilities, r.ta terial, 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. l f No ASME Code stamping was provided.

i - .?: j ChicL' . I.* ' ~ !a. :. Cc:op: :.y ~ Mr. P. K. Agrawal Sargent &.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.'o (A) above were' certified t as complying with ASME Section III, Class MC rul's 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 attachment welds, were certified as complying:with ASME Section III, Class MC rules for fabrication and examination. Drywell Equipment The pers.onnel lock including sleeve, the equipment hatch, ' and the drywell 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 Sunmer 1976 Addenda was used for all the drywell work. We trust this summary provides the information needed. Please l let us know if we can be of any further assistance. ~ Very truly yours, Y 0 ,!, } ('Al L,. 0:. *< J l RAY E. AKIN ENGINEERING SUPERVISOR id /dr. H. M. Sroka, Sargent & Lundy cc: Mr. W. J. Harrington, Project Manager, Baldwin Associates Illinois Power Co., Clin, ton Project, Document Control Center I

9 4 U-0572 /LLINO/S POWER COMPANY L30~82(10~29)~6 [l/ 500 SOUTH 27TH STREET, DECATUR, ILLINolS 62525 October 29, 1982 Mr. Cecil O. Thomas, Chief Standardization & Special Projects Branch Division of Licensing U.S. Nuclear Regulatory Commission 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. 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 stamps, 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. .Go, s e i r m m r,, k n

?"

  • 90 U-0572 L30-82(10-29)-6 Mr. Cecil O. Thomas October 29, 1982 Page 2 You will be notified when a vendor han 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 Is 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 -e- = ene. ,m -e a% 4 1 6

NOV 2 4 1982 MEMO DATED: MEETING

SUMMARY

DISTRIBUTION:

' Document. Control f(50-461 ).

~ NRC POR Local PDR PRC System NSIC LB#2 File EHylton JHWilliams Goddard, OELD RKirkwood, MEB N. Chokshi, SEB J. B. Henderson, IE H. Abel son .}}

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