ML20138N808

From kanterella
Jump to navigation Jump to search
Forwards Addl Info Re ASME Section III Nf Jurisdictional Boundary for Component Supports, Including FSAR Change,Per 850409 Meeting
ML20138N808
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 12/16/1985
From: Danni Smith
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
0987K, 987K, NUDOCS 8512240164
Download: ML20138N808 (26)


Text

V

,/

I e

If

/

's Commonwealth Edison

-) 0

/

o.

/ On1 First Nrbonit Pirza, Chiggo. libnois

] Address Reply to Post Ofhce Box 767 y

,/ Chicego. Ilknois 60690 December 16, 1985 Mr. Harold R. Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC. 20555

Subject:

Braidwood Station Units 1 and 2 NF Jurisdictional Boundary for Component Supports NRC Docket-Nos. 50-456 and 50-457 h

Dear Mr. Denton:

On Apell 9, 1985, there was a meeting held in Bethesda, Md. between Connonwcalth Edison Company (CECO) and members of your staff to discuss the subject NF boundary. This letter is to document the discussions which occurred at that meeting and to evidence the concurrence by NRR with the pipe support ASME Section III NF jurisdictional boundary definitions established by CECO for the Braidwood Station. These definitions were presented at the meeting and are clarified by supplemental information in this letter.

The material in Attachment I reflects the discussions at the meeting.

Attachment II responds to five questions raised by your staff members at the meeting. The last of these responses is the proposed change to the FSAR which will be included with the next amendment submittal.

Please direct any questions you or your staff may have concerning this issue to this office.

One signed original and fifteen copies of this letter and its attachments are provided for your review.

truly yours, J) l t

David H. Smith j

Nuclear Licensing Administrator

,i

  • /klj g

0987K L

i-s M

8512240164 851216 PDR ADOCK 05000456 A

PDR

m e

0,

'e e

Attachment I

's MATERIAL PRESENTED TO NRC/NRR REPRESENTATIVES ON (APRIL 9, 1985) AND SUPPLEMENTAL INFORMATION.

4

. A

4

<c

' ' ' - " ^ ^

ym gem p-y s. y u _ W;y;9,

,1

o _ g m

C

- fL.

mh

~;

l

% y[

M W.

34

'I.-

- NF Jurisdictional Boundaries 1 t

,s 11%q Commonwealth Edison CompanyL(Ceco)) believes we have complied with the W 4,y requirements of,ASME.Section III, SubsectionLNF, in L establishing, the ;

' J!!'

boundaries between building structure = and NF; supports.. The following 1

-s.

code references' of-ASME Section:III states

., J }

%c~

= 1.c

! NA-3220,' Catenories of the owner's Responsibilities 7.. '

The responsibility of.the, owners orf his agent include the

'f011owing p

(b); - Provision of ' adequate. structures for supporting the items covered by the rules of this Section

-(NA-3240).-

(c)

Frovision of Design Spe'cification_ covering the W

construction of items and establishing the -

boundaries of jurisdiction (NA-3250).

-2.-

NA-3252,1 Contents of Design Specification The Design., Specification shall include (e)

The~ definition of ;the boun'daries (NA-3254)..

4 3;

iNA-3254, Boundaries of' Jurisdiction

' In. order to define - the boundaries-of components with respeet to adjacent components or: other structures,- the design ;

specifications sha11' include:-

~

(a)

The: structural characteristics >ofLthe attached components or structures, whether or not they ~are within, Code jurisdiction when such components or-g-

structures provide constraints to the movement of components or appurtenances.

4.

NA-3254

. (e ) - -(Added in'the W74-Addenda) Component supports - The

' n '

boundaries for component supports-are depicted in NF-1130.

a cy

,.7 i Page 1 l}

l L_..

._S.-

g; ;p.

c

__ g =- =v;=

-=

n-

- +..

7 s

4 f

NF-3271.6, ' Supplementary Structural Steel Members -

5.

i

- Where it is necessary to-frame. structural' steel members L

between' existing structural' steel members, such supplementary.

c f members.are not in jurisdiction of. this Subsection.

,In complying with theselrequirements, CECO has provided'a Design L Specification governing Component _ Support,s.for Braidwood Station Units 1 -

and 2..: This. document.is 'Sargent & Lundyf(S&L) Engineer's Specification, DS-NH-01-BR (current,1y Rev. L 2, 1,0/10/84).

In the S&L Specification;(Division 3, Par. 301.4)' the z boundaries.are idefined:ssi' "The ~ jurisdictional boundary.between the building" structure and Section III pipe support shall be the surface of the. building U

structure. The 1974 Edition of NF shall be used to determine NF (jurisdictianal boundaries."

~

LThe boundaries: of the; supports that are covered by this specification

.are-illustrated in Figure 1.

Figures. 2 through -9, which -are based on the boundaries : defined in Figure 1,' illustrates typical boundary combinations between the building Jstructure,: building -auxiliary steel, and,the NF piping supports.1Also zincluded in these figures are the vario'is schematic illustrations of boundaries from Figure NF-ll31-1L for,raference 'and examples of. NF 1 boundaries from other nuclear plants.,

As' indicated above,' the defining _9 = NF boundaries using the. paragraphs f

Jc of Subsection NA and NFJhave been followed consistently at the 'Braidwood -

c

Project.

9 Y

Page 2 4

1 Y

j-

~

.,?

d j

STRUCTUR AL - STEEL (s.P.Q (At p.

g,

,,,g o

MSTRUCTLRAL l g

.g(

STEEL (8, P.

l1 rl z'

2 WCLD

-SUPPL N 4,

TARY STEE

!ARY STE WELD PER NF g

r;,

U-K)L T PER NF

. NF" _

ON-NF i

I I

l l

_y

'r NF "I

p f (

_ _ _ _ ** - l WELD

- [

SUPPLEMENTARY NB NC,OR ND k

/(_T STEEL NON-NF ag

/

F WELD i

{

y t4 i

N WELD

'?

NF WEL W WELD' y

[

y NEL NC.OR ND J p:t g4 I

NF NON-NF

/T

' l 2

i WEL ifa' A l M*. \\g g

? bu-BOLT,

f. * -

y f

l9 NB NC.OR w

~

CCLMJLATOR

~

TANK WALL hjik_

~

g NC WELD 3

NF.

NF.

2h l

WELD WELDW NB,k,OR ND NC MATERIAL O'

U-BOLT

. gk

i' ta PER W WELD

~

I PER W--

WR.SFRNG e

+

l Z

i,.-

1 SUPFORTg g

g 2

i+. w.t..sM h-[T l

[

zL p

AISC MATERAL 3

i f TI 1.P.\\

[T

-t-

^'sC WELD

[in~

NUCLEAR SAFETY RELATED

_NF JURISDICTIONAL BOUNDARIES q

NOTES:

t) 1500uDAmiES APtE BASED GJ 1974 EDITIO*J -

' OF ASME SECTIOlj III-SUBBCCTsou NF.

2) LDij-MF SUPPLEMENTARY STE.EL SHALL BE AISC. f TEMR.

i FIGURE-1

2. _e m..

s

.s 9

.I g

L L.

e r

I I

I 43' ts

-k !

EMB.PL.

Ene.PL.

i i

rl hI*'

T*

,%(.n i

sm N.

H Q F

H Q l' NF NF o

y I

g

.I I

,U l

I I

1 m

m.

v 4 ;.c V

~k 4

q.

1 Q

1

=

A

_.L U

.' F.l t

.1

.L T.

T.

k D

A Aft!$0lCTIGIAL Aft!$01CTimeAL EDUISAltY touleAltY N

y

_... ~ - -

D O

Ifl IG DffE8EAL Sf9tBIT (D) CDetCTG TD (b) PIE 554sE IETAlstIS EDMBuptf ( Al BilLSIIS STIRICTWE (El COWECT!!BI IN CDeECTED TO A MBD-lW7EWLAL 3rMulf AEEIBRAIIEE Wi m W (31. CSEECfitBI 14 actneemct ylm W C

FIGURE 2

Page 4 m

.....sve**.

              • ~e

~ -s e -~.

e~

~ *. ~

                    • '*****~~ * ~~'

w

E p.

c EE.PL.

_ _ f. _ _ _ _ _ _

<i

...a

// /

/

H 3.

h

/

i

/

NF y

/ /

l

// /

D j

tt /

/

[f E W.PL.

- s L

4 A

o h.

4,

.=

I' e

e

(

A AstlWICTieAL Ast1SICTIEML A _

  • ~

{

.me 1

4 Ibi FIESSIDE IETAINIfe CIWONUff ( A)

(f t MEl-firTYWIAl. SrPORT (99 C3eECTED TO CSEECTED TO A IEBe-!NTEWIAf. RIPPGli WILp!NS ETmftfuE gel. CDsECTim le 195e CIBGECTISI IN JCCUBAHIE WITH IW" ACCIEW4MCE flIW IF

.; - ll *.

4.

J es::

FIGURE 3

..,g.,

v.....,.,u,,

......v

. _, _. =,.

r-n U-BOLT NF D'

sa-EMB.PL.

)

(

r b

A D

' Aftt$0lCTI0lt4L

.Mt150!CTIONAL g

Stu eART BlueMtY fV N

D E

Y\\

3

  • * ~~

iba PIE 3SMIE IETal'a'ING CIBMMDIT ( Ai~~ ~ ~

~

~ Ifl IE3l 3NTEstat. SFPGli (D) CtpeECTG TO CGeECTED TB A IEst INTEstAL SIPPGli allLDla8 STIEfC7tsE IEl. CDuECTilpf 35 808. CIBGECTICBI IN ACCWW4flCE f!TH IF ACCDWest TITH IF D

l FIGURE 4

~

Page 6 w--

<-an-,

..--,,.----..,--------.,.-,,.----,----r,.,-

--,-,------,_-,---,,.ne-m.,,,,,---,--,,,----,,m-a,,-m as

i I

r 7

E I-l ~ - T -- - Il 1

,i l

ll nA HA D

!l W l1 EE.PL.

<.a i

A l

k E

A

w..

PRESSURE RETAINING COWONENT (A)

JD BUILDING STRUCTURE (E).

ND JURISDICTICNAL BOUNDARY ir?

NO PORTION OF THIS SUPPORT IS NF

%^'

I

?

. ~. '

FIGURE 5

l l

Page 7 gy..

w

-,y

-.._.....m


.,.w--,

e

--w

8 8

e e

L.

L.

l-1 I

?Q I

I I

I q

I I

,ii

  • --a
  • v-g g

g r-*,

l l

l d

k r

NF 1

T.

r e

I l

l j

{

~

l l

I I

I I

=

1 I

I

!.7!:

-I! !

i n

a -o I

1

%f

.L NF.

.l l

i

~I T

e l

BRAIDWOOD l

r

. q a --

h'

~

s L

y Q, p n.

. I.

-=

y T.

s 4

g'

\\

EAST COAST NUCLEAR PLANT 4

..s s.

'}

4 \\

T i

, f.

s.

s., c s.,

'4,

w

'4 x

FIGURE-6 m

\\

.+

ss. -...

l

.s Page 8.

~

t A

l

= : s., w. -

l

.... w

...s.

-. e-

.a t

I

. _,,. _ < - ~ _.

w

4

.c5 EM8.PL.

f 1

s.

a

,/,

,/ /

H gg F

~

~

//

NF y

/

j

//

l

//

f 4:*-

EWS.PL.

5 E W.PL.

4 es:

-_____/_-_.__

}

h'

_L l '/

l t

//

F

_ 1

//

//

NF.

I h

//

V T

//

g

/i /

//

I BRAIDWOOD

/ /

/ /

l ft/

t

//

E E.PL.

/

o 3,

c

.. a..

EMS.PL.

r

,j y

_ _ _ __ _ __e_ _ _ _._ _ _

W,

/<

/

U_ 1

/

8 gg F

'/

NF I

At f

~

~

l

/

F

,/

l EAST COAST NUCLEAR PLANT.

I

/

/

l

(

f/

f l

EMB.PL.

3; 4

F l

wl m

>=

l Et'.# u j

I

. FIGURE-7 m:

4 l

OTHER NUCLEAR PLANT e

d U-BOLT' NF h"

5:ts

+

ES EE.PL.

<a h'.Y Y 4

$l

.r.

r

.,-BRAIDWOOD 2

1 -i

(

t*

i BENT E hs:r.+. i

+

=>

EE.PL.

n es 3w f

EAST COAST NUCLEAR PLANT NO PORTION OF THIS SUPPORT IS NF

==

t o

L L

FIGURE-8 r

e p

Page 10 l.

,-----,,s---:.-~,,...

- e.-.

s. s aure t. -

s.-- -.. rv a - +-n e. ew -

}.

\\

T

  • 7 l l --y---- l; I

l l g

i ll l

w.

ll [+

Fli I

=>

,I i

EMB.PL. --

BRAIDWOOD T"' ----7 NO PORTION OF THIS Il I

l li SUPPORT IS NF I I 1l l

w.

ll [+

Fjl

(

45 I

I E E.PL.

M i

EAST COAST NUCLEAR PLANT

't--

l 9

NO PORTION OF THIS NF

-SUPPORT IS NF ar g.

-=

=

=>

.EMB.PL. ______-{_g____

EE.PL.

l FIGURE-9

=c -

OTHER. NUCLEAR PLANT l

l

~

~

.- 'NM Page 11 MNW _ _ _ _ _ _ _ _ _

.o

>~

,( p,

un; iv,, :.

' finNc s

'A e

- II.- $ Comparison Auxiliary Steel vs. NF Sections of the Support As an aid. in. showing the-equivalence between the Auxiliary Steel and NF 4

Sections. of the support, a comparison was made of the following attributes:

'AISC and ASME Design' Criteria Material:

-c Issuance 3,.

Fabrication and-Installation

- +

. Piping: Support Inspection--

~

i.

L(a)-

Compatison of AISC and ASME Design-Criteria-

~

The comparison of. AISC and ASME design criteria show they are similar except for differences in the following subjects:

4 1.

Effect of temperature on ' steel properties 2.

Allowable weld stress

~

3.

- Allowable axial stress for compression members 4.

Stress limits for thermal and:SSE load conditions l Figure '10 shows the comparison of the permitted values of

~

- p pc

~

tyield: stress;and modulus of-elasticity given in AISC and ASME 0

-for temperatures from '100-200 F.'.

As can be seen, the differences at the design temperature of'150*F are negligible

~

'and are of~no consequence to the.de'ign..

s Figure -11 shows' the1 allowable weld stress for.E70xx series-welding electrodes given in the AISC and ASMEl Codes (1974 ASME l Code). The~ current ASME-NF uses the same. allowable'value' (21.0 KSI) as'-the AISC Code.

c Figure 412 shows' a comparison of -axial compression stresses. -

m

~

.The curve labeled: 2/3 of critical-buckling,' is that required L A

.by ASME Code Subsection'NF.1 JW can be seen from the ' curve labeled:, actual compression stress, - the typical. calculate axial stress range is significantly' lower than the ASME -

allowable.'

Figure"13 shows' a' tabulated comparison of allowable stresses

for AISC,. ASME,: and the design ~ basis. used for Braidwood for.

L the conditions-of: normal operating 'and 0BE, thermal loads,

- and:SSE ' loading. As can be seen from the comparison, the Braidwood-design' basis is the usame'or-more - conservative than ASME.

I b

Page 12 p

l..

ls k

-u ax _ E"x

r:

we

-p_p ps,

~

t

.=

s A '

m

- A comparison of-AISC and ASME design criteria'and the design

^

criteria used for.Braidwood shows that the design was not affected by the differences in.the two Codes.. In idition.the.

design, basis used for.Braidwood is more conservata-than that-s permitted.by the ASME~ Code.

(b) : Material:'-ASME,~ (NF) vs. AISC

) As specified' on -the' support dedign drawing materials used

~

' within' NF: jurisdictional' boundaries are:

1.

ASME/SA Material Specification =

2..

MTM/A Material Specification per applicable code case (s)..

Materials used for pipe support auxiliary steel are' covered in

' ASME/SA materiallspecifications or ASTM /A material, specifications, which are 'substantially. the. same materials Jused in the NF jurisdictional boundary. 'The following'is a comparison.of. support material documentation and issue control.-

Documentation:-

NF

-Auxiliary Steel

-1.

.CMTR(I)~or C of:C(2) as

'CMTR.cr C'of C applicable, (NF-2700, NF-2130) certifying conformance certifying conformance :to the to the ASTM /A material"

'ASME/SA:or ASTM /A material specifications..

specification for ITT Grinnell and(CECO site procured material.

!(Note,lthe.'1974 subsection NF,

~

applicable to
ITT Grinnell Tsupports did not include. require-ments?to supply code data reports-and.staaping.)

~

-2.'. Code data reports (NF-1;and NF-2).

'for E1cen fabricated component.

~

standard supports required : due'.to.

'~

~

a--later P.O. date.-

,~

(1)

. Certified Material Test Report

- (2),

Certificate of Conformance or Compliance 3

Page 13 w

K a

r := z

y EFFECT OF IEMPERATURE ON STEEL PROPERTIES IEMPERATURE YIELD STRESS MODULUS OF ELASTICITY L(OF)

(KSI).

(KSI)

AISC ASME AISC.

ASME 100-36.0-36.0

. 29,000 29,000 150'-

36.0 34.4 29,000 28,750 200-

-36.0 32.8 '

29,000 28,500 AT DESIGN TEMPERATURE OF 1500F:

- YIELD ~ STRESS'15 REDUCED BY 4%

- modulus OF ELASTICITY IS -- REDUCED BY < lE i

p EFFECT OF TEMPERATURE 'AT SUCH LOW TEMPERATURES IS NEGLIGIBLE-t t

FIGURE 10 Page 14 y

,,,,-.c, nn

-n-

-n


.--e-

~

4 ALLOWABLE WELD STRESS-

-- /

AISC

=

21.0 xSI R

ASME

=

18.0 xs!

!0NLY-3-KSI' DIFFERENCE'

' DIFFERENCE DUE TO TIME LAG IN UPDATING OF ASME CODE t

CURRENT ASME NF USES 21.0-KSI ALLOWABLE INCREASE FROM 18.0 xSI TO 21.0 KS! WAS TO ACCOUNT FOR-USF OFJSTRONGER E70_ ELECTRODE

~

E70 ELECTRODES USED FOR INSTALLATIONiOF SUPPORTS AT-BRAIDWOOD WELD STRESSES MEET.' CURRENT ASME' CODE ALLOWABLES c

s

~

F I~G U R'E 11 Page 15 b

m2..

> ~ - -

AXIAL COMPRESSION STRESSES FF = 34 4 kel

, 6150.F

'E

= 28,T50ksi

'50 '

STRUCTURAL STABILITY RESEARCH COUNCIL CRITICAL BUCKLING STRESS 40-ASME ALLOWABLE i

- (2/ CRITICAL BUCKLING) 3 N

30-m to aoa P-*

a 30-b.

~~

TYPICAL CALCULATED AXIAL STRESS RANGE 0-

  • *..... '. '. '.. '* ' '......... =. *. *.....

....*..*.*.a.*.*.*.*...'.'..'.'.'.'.*..*.~...'. * *. '. '. * *. *. *..... *. *. '. *. *. *. *. *

.. *. '. '.. '.. *. ' ' '. * '. * *... *'. ~.

.. '.. *. *. =. *. *. *. *. *. *.. *... *. *. *....

...c.............'...'.....*..

f....'........'*.*..*.'.'.'.......'.'..'*..'.*..'.'......'.*.*.*.....

s.

f

..... *. '... ' ' ' ' '. '.. ~.. '. '... -

_... '.,.,. _. ',.. '... _... _... _. '. '. '. '. '.. *. *. '.. ',.. '. '....... ~..

........,._.................*.',.c I

i i.

i e..

o 10 20 30 40 50 so 70 80 90 10 0 11 0 12 0 130 14 0 150l 16 0 170 10 0 190 200 e

i

\\:

-9 NORMAL RANGE 1:

}:

kl/r PIPE SUPPORTS

~

FIGURE 17 g

'. b 4

6

COMPARISDN OF All0WABLE STRESSES

-1.

NORMAL OPERATING CONDITIONS-AND 03E CONDITIONS
  • AISC/AND ASMELUSE'SAME ALLOWABLE' STRESSES 11.

THERMAL LOAD CONDITIONS MAJOR AxlS MINOR Axis TENSION.

BENDING BENDING JH_[A:

RAIDWO D ASIS

.90 F

.95 F

.95 F

.55 F EShGNAl C,:S.95.F )

Y Y

Y-y LAh' Mb.

1.80 F 1.98 F 2.25 F l'.20 f:

-(.

AISC)-

Y Y

Y

. Ill.

SSE LOAD CO'NDITIONS MAJOR'AxlS MINOR Axis TENSION BENDINQ BENDING SHEAR

RAIDWO D ASIS

.95 F

'.95 F.

.95 F

.55 I ESdGN.Al C, i.95'F )

y Y

Y y

..l.13 F 1.29 F 1.41 F

.75 li

'gg gg y

y y

l

  • BRAIDWOOD DESIGN BASIS'MORE' CONSERVATIVE THAK ASME

~

~

FIGURE 13 Page 17 J. o..' e..

f'(;;* y 5L -

~ q

~

v.

w~

, age

r

^

._(c)) 1 Issuance'for Fabrication' Installation

~

s,

For both NF an'd Auxi11ary S' teel the. material is issued by istores1 request with the following information recorded as applicable:

7-1NF---

Auxiliary' Steel 4

.1.

Ceco MRR Number.

1.

. CECO MRR-Number.

2.

. Heat Number or Heat Code -

2. -

Heat Number or Heat l Code.

-3. LManufacturer's Type.

=.,

2-w

- Identification-

^

14.. Manufa'cturer's Serial Number 3

'w With the exception'of'some Cla'ssLA materials, for a majority -

l of -'.the. NF ' supports, the material requirements (NF-2130,.

, NF,-2600) o' ly ; require ~ C _of C's for manufacturing and supply.

n

Therefore,
there. is no significant. technical difference..
between documentation required for ASME Section IIILSubsection.

-ENFJsupports'and Auxiliary Steel.

.g'(d) 1 Fabrication and Installation g;

iTlie ffabrication controls. in place at Braidwood are:.

- Welding -

~

NF Auxiliary Steel.

2

ASME.Section-IX qualified- ~

ASME Seetion~IX qualified.

1 procedures and welders -

. procedures and welders -

SFA specific 5 tion-welding -

SFA specification welding ifiller materisl.

filler material

~ '

J A

7Each; weld'on,'each support-Groups of welds on each-Ldrawing.is. assigned a

' support. drawing by' base separate' number which m'aterial~ designation which-

. includes :

. include s :

j Base metal types.

Base metal' types

^

' - IWeld procedure Weld! procedure Weld' size: indicated on_

Weld size: indicated.on-J

- traveler. 6. design drawing design-drawing.

~ Preheat ~ requirements-

_For preheats above-150 F

+m welds are. assigned in-dividual-identification y.

!'~e Welding material issued.

Welding material: issued by rod slip-by rod slip.

e p.

<~

Page'18

_y.%d'. _ 7, "s_

5 h' T

C5.

(-.

,~7, e

, :;q

~

l'l Welding Document $ tion

}@[

Auxiliary Steel Welder Symbol and filler Welder symbol and filler

material heat' numbers'docu-material heat number of

~ mented for each weld.,

do'cumented for each group of welds of the base metal types for each support.

'.(e)

Piping Support' Inspection.

}g[-

Auxiliary Steel Inspection per support is as follows!.

1.

-QC/QA Inspections Inspection required 'by NF when-required) y (and NDE, Final: weld _vis Final visual. documented documented for groups of. weld on for each weld.'

support.

' Inspection not required by NF Hold point / monitor' point' on Hold point / monitor point' all; welds requiring pre. heat.;

on above 150 F..

Hold-point / monitor point on

.Fitup by craft.personneli

'fitup.

and monitotad by CECO and Contractor's-QA.

Completed' support inspection Checklist-support inspec-:

hecklist.-

' tion checklist.

c 2.

. Inspection

. Visual-weld acceptance Visual weld acceptance criteria more restrictive

.criteriaL more restrictive than NF-5360 : requirements..

than NF-5360 requirements.

3.

Personnel Qualification-

, 'QfE,

_ Inspection qualified to

. Inspector qualified to.

SNT-TC-1A-(NX-5500) and SNT-TC-1A (NX-5500) and

^

ANSl' 45.2.6. -

45.2.6.

. (1)-

Approximately 1% of 'the NF supports. require NDE other than visual.

Page.19

1 y

- ~.

- v ts 2

?III'.

-W-5 Data' Report' s

For system completeness and to facilitate reconciliation of as-built configurations, the data reports will include both NF component supports and' auxiliary st' eel component supports. The auxiliary. steel

'f component supports will be-denoted byLan asterisk with an explanatory

' note at the. bottom of the N-5 Data Report which describes that these Jsupports are being listed for informationLonly. -Additionally, there>

will be a note which states that-the NF component support data package's will detail;the ASME Section III NF material boundaries and

[ welds. l Included in the NF component support data packaEe is the iapplicable AE drawing.which indicates the NF boundaries.

E

~

Y-

[TO' CONCLUDE, THE FOLLOWING STATEMENTS-ARE INCLUDED AS A

SUMMARY

j.

CLASSIFICATION'FOR NF BOUNDARY JURISDICTION IS CONSISTENT WITH APPLICABLE ASME NF GUIDELINES

.a THE~ASME CODE ASSIGNS THE RESPONSIBILITY FOR DEFINING THE.

JURISDICTIONAL' BOUNDARY TO THE OWNER PIPE SUPPORT AUIILIARY STEEL HAS BEEN DESIGNED IN ACCORDANCE WITH THE AISC CODE J--

FOR' SAFETY-RELATED PIPING, PIPE SUPPORT AUIILIARY STEEL HAS

. BREN IDENTIFIED AS-SAFETY-RELATED AND HAS BREN COFSTRUCTED AND EIANINED IN ACCORDANCE WITH 10CFR50, APPENDII B

. PIPE SUPPORT AUIILIARY STEEL TO THE CONNECTION OF THE.FIRST NF W -

COMPONENT IS CONSIDERED AN EXTENSION OF THE BUILDING STRUCTURE

~

f COMPONENT STANDARD SUPPORTS THAT TRANSMIT LOADS TO THE EXTENSION OF.THE BUILDING STRUCTURE ARE NF THE CLASSIFICATION RESULTS.IN A SAFE CONSERVATIVE DESIGN 1

y

-PaEe 20 (Final) 1

'}-

6
h,,

.?

N Attachment II RESPONSES TO NRC/NRR QUESTIONS-I.

  • l-e

'e

')

' E1 J

ni

+C:.

^]

s':

~

4 RESPONSES TO NRC/NRR' QUESTIONS

' li-Question

. Discuss. hold points.for> fit-up of non-NF items.

Response -

QC hold. points-are not. implemented on the auxiliary steel. sections

,}

of the-pipe' support. Weld -procedure (s), visual examination

~ procedere, and AE drawings pertaining to pipe support installation.

guidelines' and _ tolerances 'contain criteria for fit-up.. Applicable

personnel are-trained in the requirement of the subject documents. -

' Monitoring of ' the -implementation is. included under: the contractor and Commonwealth' Edison Quality Assurance programs..

2. : Question

~

Discuss independent -inspection of: non-NF.' components.

i g.

h3

. Response y

~Contractoriand Commonwealth Edison Quality Assurance programs apply j

to1the auxiliary: steel. sections ' of the. pipe support.

In-addition,.

p.,..

%}

. independent overview -inspection programs are - in -place that -cover' the

.'j.

auxiliary steel' sections of the pipe ; support. These inspections are

?:9" comparable 11n coverage'to thatlof.the: independent inspections of the

>NF section. of the ' cupport.

.3.:-Question-LAddress equipmentLaupport NF. boundaries.

N

Response

InJsafety-related equipment specifications design and construction requirements 'for the equipment under the jurisdiction of ASME -

Section?III 'are1provided' as follows.:

" Equipment: covered under this specification is rated as Code'

. Class 1, 2, or 3 and as such, shall' be designed and '

7,.

Jconstructed 'in accordance with Subsection NB, NC, or ND,

' respectively?of the ASME-Code,Section III."

1 1

I' Page 1 c

[h

;;.. ~

f sl

^

gj4;p

+ ',.

~

d-F..-'

~RespsnaasJ to NRC/NRR'Questiens' y

4fi

+ e Supports /forSection-IIIequipment,'suchaspumpsand~ vessels,.can

/beidesigned and constructed in accordance with the rules-in the _

~

4 applicable equipment specification and subsection of ASME:Section

III for
the ~classiof component' being furnished or. alternately:in accordance with ;the: rules'of Subsection.NF Structural Steel,

. equipment; supports may alternately;be' designed to.the AISC. Code.-

(4.;-Question'

._s

~

Discuss weld examination with respect to non-NF Class 1 supports.

m.

Response

Information relative.to weld inspections of pipe supports is

3. :

fincluded in Secticn II(e): of the letter.

m' q

~;

5.~

Ques' tion >

y -

Review the FSAR to make - sure it'.is complete and -accurately reflects the stated NF. Code boundary definitions.

~

c,

Response-

~

' The following will be,added to the FSAR Section 3.9.3'to clarify the s

1 NF ~ jurisdictional boundaries for component. supports for the project:

3.9.3J

' ASME Class-1.- 2 and 3~ Piping,iComponents, and Component Support - Structures

[

General

@g9-JASME Code-Class 1,=2,.and 3 Piping and Components are designedE 1

and constructed in accordance with Section III of the ASME q Boiler and Pressure. Vessel Code and Code Case (s).. For Component

-Support Structure - for: Piping, ' the jurisdictional, boundaries have =

-3

~

been established in accordance with the ASME Section III,' 1974 f',

~'

' Edition.

Inlaccordance with ASME, a specification has been provided for R

Epiping-supports which defines the jurisdictional: boundary for the NF portion of the piping ~ support.: The auxiliary steel for r@

~ 5

.the piping support is considered an exterision of the building.

-:y.

_. structure.and has:been designed to'the AISC Code.- The' piping.

-support auxiliary steel;is identified in'the design

~ specification and-the support drawings as not being with'the.

>.f

- '. jurisdiction of Subsection NF of the ASME' Code.

9

- p, P

Page 2 g-

?-

s

__ _ h;

~- k o J

7 y --

a..-

e:

. e Responsesito NRC/NRR Questions s

For equipment component supports, such as those'for pumps.and

' vessels, the supports:have generally been furnished by the.

manufacturer.along with the equipment. The supports have been

. designed and classified by thelvendors and meet either ASME

~

Subsection NF, the rules for the class - of. the component being furnished..-or AISC,-as appropriate. '

i ag y f d-h F

F

.\\

t J

w 4

t

... b,y 4

Page 3 N:;,.+

~

>