ML20044G614

Rev 0 to 92C1737A, Recommended Operability Review Criteria for Piping Sys Subj to Level D Svc Loadings for Carolina Power & Light Nuclear Stations.

ML20044G614
Person / Time
Site:	Harris, Brunswick, Robinson
Issue date:	07/31/1992
From:	STEVENSON & ASSOCIATES
To:
Shared Package
ML20044G611	List: ML20044G610 ML20044G613 ML20044G614
References
92C1737A, NUDOCS 9306040013
Download: ML20044G614 (11)

Text

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FM NO. 2165872205 P.03 JUL-10-92 FTt! 16:25 .

i 92C1737A *

, REVO RECOMMENDED OpenauxtxTV RavZsw CRITanzA F0n PIPING SYSTEMS-SUBJECTED TO LEVEL D StavtCE LOADINGS FOR CAROLINA power AND' LIGHT'S_ ,

NUCLEAR Powra STATroNS' Revision 0 Stevenson and Associates

- July 1992 -  :

-l

1.0 BACKGROUND

If a seismic Category I piping system at one of the CPR Nuclear Power Stations.

identified in Section 2 is determined to'have an indeterminate seismic design  ;

basis, it is subjected to an operability review. The purpose of this review is to'avaluate the subject system's structural integrity in the event of a DBE (SSE). In addition the seismic design adequacy of the subject system will be upgraded to the current individual plant design basis and any required in-plant hardware modifications will be ic:plemented using currently approved construction criteria at the next refueling outage.

2.0 SCOPE 2.1 Nuclear power Station Ooerability This document and the suggested criteria is applicable to' the following Cp1L Nuclear Power- Stations:

a) Brunswick Unit #1'and #2-b) H.B. Robinson c) Shearon Harris Unit #1 The analysis methods, procedures, and load combinations for this criteria-are common to all the subject power stations.f and are given in Section 3.0 and 44. i The response spectra, input and piping acceptance criteria are unique for:each  !

power ' station, and are given. in Section 5.0 and .Section 6.0 respectively. l 2.2 Soecific Aeolicability of the Criteria'  ;

This criteria document is applicable to the evaluation and qualification' of the

. piping : and any piping . standard components. While it is applicable to the generation 'of loadings applied to piping component supports inline mounted 1

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I equipment and non-inline equipment, in contact with the piping these items are j outside the scope of this criteria document. 1

(

3.0 ANALYSIS METHODOLOGY- f 3.1 Deadweicht A deadweight run will be made with all deadweight supports active and the system j will be evaluated against specified code limits for deadweight loading. Supports i which are non-standard or exceed MSS-SP-58 load capacities and which cannot meet normal AISC code requirements for dead load shall be considered inactive and the ,

deadweight analysis rerun. The deadweight pipe. stresses, nozzle loads,- and' -

a support loads at a given location will be taken as the maximum of these two runs.  !

3.2 Seismic Runs A DBE (SSE) response spectra analysis shall be performed using as input the Power )

Station's (Plant) specific response spectra as defined for a given power station i in Section 5.0. All supports other than spring-supports _will be assumed active .j (hangers, U-bolts, . stanchions, snubbers, etc.). - For rod hangers the seismic  ;

loads will be reviewed and compared to the deadweight loads. For any rod hangers -  !

for which the vertical seismic loads exceed the deadweight loads, lift-off could i potentially occur. A second seismic run will be made with any rod hangers, whose seismic loads exceed the deadweight, removed from the analysis. . A downward force equal to the deadweight load may be applied at the removed rod hanger locations. )

In addition in this second run, any supports'which cannot be demonstrated to withstand the DBE (SSE) evsnt shall also be removed from the analysis. The piping seismic inertial stresses, nozzle loads and support loads at a given

~

location will be taken as the maximum of these two runs.

If a computed differential seismic anchor motion exceeds 0.5 inches at equipment nozzles, pipe to branch interfaces, and/or between different buildings, a seismic anchor motion analysis will be done using the methodology defined in the applicable Power Station (Plant) Piping Design Specification. -Two base cases will be run: one with all seismic supports assumed active, and the second with  ;

the rod hangers determined to have poter.tial lift-off in the seismic inertial '

analysis removed from the analysis. In addition,- in this second analysis run, any supports which cannot be demonstrated to withstand the'DBE event shall also be removed from the analysis. The seismic anchor motion pipe stresses, nozzle i loads and support loads at a given location will be taken as the maximum of the two runs.

- ~ -

4.0 LOAD COMBINATIONS 4.1 Pinino lead Combinations {

The following Load Combinations will be used in the piping evaluation 2

4 m em.,.., m w- -y.-wen -

y p . r.,-.%-g -, wev,. ei y -w ,,~we s,~- ..wew..-u..-_ _ _ e--___- -._ -___. _ _ -__----- ----

i JUL-10-92 FR1 16:27 FAX NO. 2165872205 P.05 l

)

L3 -

P + D + DBE, (4.1)

L2 -

DBE' , (4.2)

Where:  !

I P, = Maximum Operating Pressure-  !

l 0 - Deadweight DBE , = Maximum resultant seismic inertial loading DBE' , = Maximum resultant seismic anchor motion loading 4.2 Suonort Load Combinations ,

)

The following Load Combinations will be used in determining the loads on piping j supports:

L3 = 0 + T' + (DBE 2 + DBE' ,3)'" (4.3)

Where:

D = Deadweight DBE , = Maximum resultant seismic inertial loading j DBE' , = Maximum resultant seismic anchor motion loading T' = Restraint of free end displacement loads resulting from normal operating thermal effects 5.0 PLANT SPECIFIC INPUT RESPONSE SPECTRA 5.1 Brunswick Units #1 and f2 A 3-D response spectra analysis will be 1erformed in accordance with the l methodology defined in Section 6.2 of Spec' fications BSEP-005-011 [ Reference i 7.1]. ASME Code Case N-411 (PVRC damping) damping will be used incorporating the 'l restrictions listed in Attachment 3 of BSEP-005-011 (Reference 7.1]. The l applicable DBE spectra will be obtained from BSEP-005-011 using the spectra selection requirements of Section 6.2 of the reference document [ Reference 7.1].

r.

5.2 H.B. Robinson , ,

The input response spectra for this evaluation shall be floor response spectral curves based on a HOUSNER spectral shape. Floor spectra shall be based on 5.0 percent composite building structural camping values with an equipment (piping) damping not to exceed 2 percent critical damping. The ters

• composite building.

structural damping" implicitly conservatively includes SSI effects.

3

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l JUl.-10-92 F?.I 16:27 FAX NO.,2165872205 P.06 l l :l' l

l The basis and. limitations for use of' this input spectra is defined in the .l following document

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" Recommendation for Input Floor Response Spectra for Use- l in Piping System Operability Reviews for the H.B. Robinson- 3 Reviews for the H.B. Robinson Nuclear Power Stations,"  !

Revision 0, Stevenson and Associates, July 1992:[ Reference.7.2]. l 5.3 Shearon Harris .l A 3-D Response Spectra Analysis will be done using the methodology specified in Section 3.7 of the ' Shearon. Harris' FSAR [ Reference ,7.3]. . This methodology. i includes the use of. floor response -spectra generated from . dynamic building 1 structural models using a ground input' response spectral shape based on .

Regulatory Guide 1.60 normalized to .15g for the SSE. ASME Code Case N-411 (PVRC  !

damping) damping will be used incorporating the restrictions listed in Reference 1 7.4. . In addition the limitations to the application of' Code Case N-411 with .:

respect to ' the- ANS SC-1 ~ systems specifi~ed in' Section 3.7.1.3 of - the FSAR : i

[ Reference 7.3] shall apply.

The applicable floor response spectra will be .]

obtained from CPL-HNP1-C-001 [ Reference 7.5]. l 6.0 PLANT SPECIFIC. PIPING EVALUATION CRITERIA i i

6.1 -Brunswick Unit #1 and #2 j 6.1.1 Initial Evaluation - l The piping shall be judged capable of meeting operability requirements with a one time occurrence of the DBE (SSE) if the following equations / criteria are met: j P, [d,2/ (0,3-di a)) , {$,2 , 43,231/2. I 2.0 S y (6.1) 1' and

[S'38 + 4 S',2)tn i 2.'0 S y (6.2)

Where:

S, - Ifi (13 +- (i M ,1 21 3n [i 1 1.0) ,

Z -l S, - _.

S',. - f(i M'mia # g 4 g, ,3 21 1n [i 1 1.0] -

7 i

S', - E',

21 p" 4 l i

, _ . _ a .- .. _ _ _. ._ . _ n . . _.a

I JUL-10-92 FRI 16:28 . , _

.,,,FfXNO.2165B72205 .. .

. P.,07, _, ,

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i = Applicable stress intensification factor (i 11.0)"'

Map = Bending moment in plane of member due to absolute  !

summation deadweight and seismic (in-lb) l f( = Bending moment ' transverse plane of member due to  !

absolute summation of deadweight and. seismic (in-lb) l l

M, = Vorsional moment due to absolute summation of deadweight seismic (in-lb)

M', - Bending moment in plane of member due to seismic anchor motions M ' 3, = Bending moment transverse plane of member due to seismic anchor motions M' - Torsional moment due to seismic anchor motions i Z = Section modulus of the pipe (in3 )"'

dg = Inside diameter of the piping (in)"3 D.

= Outside diameter of the piping (in)d)

P, -

Pressure (psi) which occurs coincidentally with the DBE.

i -

Sy -

l Material yield stress (minig tensile yield) at normal operatingtemperature(psi) t = Nominal pipe thickness (in)"3 i

"'These properties per USAS B31.1.0 - 1967 tz)This property per Section 6.1.4 6.1.2 If Equation 6.1 is Exceeded For any points which exceed Equation 6.1 and 6.2 of Section 6,1.1 acceptability can be demonstrated by meeting the following equations:

PJL + .75i M. i_ 2.0 S y [(.75 i) 1 1.0] (6.3) 4t' Z ~-

I and

%l i 2.0 S, (i 1 1.0] (6.4) l M, =

(M,' + M'eg + M,8)

• l 5

l a -. . , - - , , , . - , -

m. m .~ .m  ;

JUL-10-92 FPJ 16:29 FAX N0. 2165872205 P.08 ,

M ' ,- -

(M',a , g, a + t',a)w 1

0 ',P,D "), t") , M,, M., , M, , M ' w. M ' w , M ' , , S '3 y ' , Z'.3 3 p e r Section 6.1.1 unless otherwise noted. t U'These parameters per Section 6.1.4 l a . ,

j 6.1.3 Isolated Non-Q Points which Exceed Equations 6.1 to 6.4 i i

!= If isolated non-Q locat' ions exceed the criteria of. equations : 6.1 through 6.4..

acceptability may be demonstrated by meeting the following

.

1 l (a) Demonstrate the locations arejn the non-Q portion of the system. .  ;

1 (b) Demonstrate the piping--in the ' vicinity of .the location meet Li

equations 6.1 and 6.2 or'6.3 and 6.4.  ;

4 l (c) Meeting the following equations:

i

+ .751 s3 [(.75.1) 2 1.0) (6.5)-

4 j and i '

i

lli' , s 2.0 S y [i 1 1.0]- (6.6) i Z i

Y = the greater of 2.0 Sy or .7 S, l

S, - minimum specified ultimate material strength (psi)"'

i i I, i, S per y Sections 6.1.1 and 6.1.2 unless i j P , D.,ise notedt, M , M's, olherw ,

! 1

!' "'This. parameter per Section 6.1.4 1

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1 6.1.4 Parameter Identification

, For ASME Code defined parameters not otherwise identified herein, the ASME B &

PV Code Section III Class 2 - 1974 Edition shall be used.

l 6.1.5 Material Properties-In lieu of material properties specified by the code, actual best estimate material properties as determined by in-situ test may be used.

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i 6.2 H.B. Robinson l

6.2.1 Initial Evaluation l The piping shall be judged capable of meeting operability requirements with a one time occurrence of the DBE if the following equations / criteria are met:

l P, [d,a/(D,2-di a)) , [3,2 , 43ajitz t 1 2.0 S y (6.7) and (S'na # 4 3,,2)i/2 2.0 Sy- (6.8)  ;

1 Where: I 5, =

I(i (): # g4 g t3ajit Z

[i 1 1.0)

S, = i M

21 S', = Ifi M'g)8 + fi M,g21/2 3 (i 2 1.0]

Z S', =

4 ,

2Z i = Applicable stress intensification factor (i 21.0)'5)  :

M. = Bending moment in -plane of member due  !

sumation deadweight and seismic (in-lb) . to absolute M, = Bending moment transverse plane of member due to absolute summation of deadweight and seismic (in-lb)  ;

1 M, = Torsional moment due to absolute sumation of deadweight i seismic (in-lb) t M'y = Bending moment in plane of member due to seismic anchor motions l

M'm

- Bending moment transverse plane of member due to seismic anchor motions

M', = Torsional moment due to seismic anchor motions ~ - -

Z = Section modulus of the pipe (in5 )'5' l

l di = Inside diameter.of the piping (in)(8) l

.0utside diameter of the piping (in)(5)

D,- =

P. .

- Pressure (psi) which occurs coin'cidentally with the DBE.

7

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_ JUL-10,-92_F.R.I 1.,6'30 , FAX N0. 21658,72205 P.10 l

l l

Sy -

Material yield stress-(minige tensile yield) at normal operating temperature (psi) 3 t = Nominal pipe thickness (in)("

(3)These properties per USAS B31.1.0 - 1967

(')This property per 6.2.4 6.2.2 If Equation. 6.7 limit is Exceeded .

For any points which exceed Equation 6.7 and 6.8 of Section 6.2.1 acceptability can be demonstrated by meeting the following equation:

+ .751 M. I 2.0 S y ((.75 1) 2 1.0) (6.9) and

%Z i 2.0 S y (i 21.0)- (6.10)

Where:

M, = (M,8 + Ma + M,2)1/2 i

a M's (M ' g,' + M'w ,g,,ayt/a 1

i(#3, P., D,(7), t(7) , M,, Ma3. M,, M',, M' a , M',, Sy (7) Z(7) per.

]

Section 6.2.1 (7)These parameters per 6.2.4 i

6.2.3 Isolated Non-Q Points which Exceed Equation (1) and (2): l

l If isolated non-Q locations exceed the limits of equations 6.9 and 6.10,  !

acceptability may be demonstrated by meeting the following:

[ .. .

l-i (a) Demonstrate the locations are in the non-Q portion of the system. .l (b) ~ Demonstrate the piping in the vicinity of the location meet the limits of equations 6.9 or 6.10.

(c) Meeting the following equation:

1

eguvrwrv --un Jl]L-10-92 FR1 16:30 FAX N0. 2165872205 P.11

+ .751 M. 1S [(.75 1) 1 1.0) (6.11) and

.111'. 1 2.0 Sy (6.12)

I l

5 = the greater of 2.0 Sy or .7 S,,

S, = minimum specified ultimate material strength (psi)("

P., D,, t , M , M's , 2, i, S per y Sections 6.2.1 and 6.2.2 ca3This parameter per 'Section 6,2.4.

6.2.4 Parameter Identification l For ASME Code oefined parameters not otherwise identified.herein, the'ASME B &

PV Code Section III Class 2 - 1974 Edition shall be used.-

1 l

S.2.5 Material Properties In lieu of material properties specified by the Code, actual best estimate material properties as determined by in-r.itu test may be used.

6.3 Shearon Harris (Non ANS SC-1 Systems) 6.3.1 Initial Evaluation

+ ,751 M. 5 2.0 Sy [(.75i).11.0) (6.13) and

$ 1$ 2.0_ S y [f 2 1.0] (6.14) l where:

• M*

M, =

( + a + M,')'8 i M's (M'g a , g, a . g,,z)tn i - Applicable. stress intensification factor (121.0)'"

9 t

TUU10-52FR]16:31 FAX N0. 2165872205 P.12 i

l

% = Bending moment in plane of member due to absolute summation deadweight and seismic (in-lb)

Mg - Bending moment transverse plane of member due to absolute summation of deadweight and seismic (in-lb)

M, = Torsional moment due to absolute summation of deadweight seismic (in-lb)

M'g - Bending moment in plane of member due to seismic anchor.

motions M' a

= Bendir.g moment transverse plane of member due to seismic anchor motions M's

- Torsional moment due to seismic anchor motions I = Section modulus of the pipe (in3 )")

di = Inside diameter of the piping-(in)"3 D, - Outside diameter of the piping (in)"'

P, = Pressure (psi) which occurs coincidentally with the DBE.

Sy =

Material yield stress (minimym tensile yield) at normal operating temperature (psi)'8 t = Nominal pipe thickness (in)")

"3 These properties per Section 6.3.2 6.3.2 Property Identification For ASME Code defined parameters not otherwise identified herein, the ASME B&PV Code Section III 1974 Edition shall be used.

For ANS SC-2 piping, specific piping parameters shall be determined from )

Subsection NC-3600,- For ANS SC-3, ANS NNS, and Seismic Category I B31.1 piping, j specific piping parameters shall be determined from Subsection ND-3600.  !

i I

6.3.3 Material Properties

- In lieu of minimum material properties specified by the Code actual materfaT' properties as determined by in-situ test may be used.

6.4 Shearon Harris (ANS SC-1 Systems) 6.4.1 Evaluation The piping shall meet the operability requirements if the requirements of 10  !

l i

l

- Appendix F of the'ASME B&PV Code,Section III, 1974 Edition are met.

6.4.2 Material Properties In lieu of material properties specified by' the Code actual best estimate material proparties as determined by in-situ test may be used.

7.0 REFERENCES

7.1 " Carolina Power & Light Company, Brunswick Steam Electric Plant.

Specification for Seismic Design Criteria" Specification No. BSEP-005-011, Revision 2 dated 22 September 1988.

~

7.2 Letter from Dr. John D. Stevenson and Mr. Timothy'M. Adams of S&A to Mr.

H. . Lee Williams of CP&L transmitting, " Recommendations for Input- Floor Response Spectra for Use in Piping System operability Reviews for the H.B.

Robinson Nuclear Power Station, dated 8 July.1992.

7.3 Shearon Harris Nuclear Power Plant Updated FSAR 7.4 Letter fron ' George W. Knighton of the NRC .to LMr. E.E. :Utley of CP&L titied, "Use of ASME Code- Case N-397 and N-411 for the Shearon '. Harris Power Plant Unit #1, dated 28 October 1985.

7.5 Carolina Power and Light Company, Specification for Response Spectra for the Shearon Harris Nuclear Power Plant, Specification No. CPL-HNP1-C-001, Revision 0, 29 August 1989.

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