ML17276B023

Forwards Draft Apps H & I to Design Assessment Rept for Facility.Apps Will Be Incorporated Into Amend Prior to 820701

ML17276B023
Person / Time
Site:	Columbia
Issue date:	01/13/1982
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
GO2-82-34, NUDOCS 8202020260
Download: ML17276B023 (34)

Text

il'<<<<t'"

REGULATORY FORMA'T ION DISTRIBUTION S i M =-('RIDS)

ACCESSION.NBR:8202020260 DOC.DATE: 82/01/13 NOTARIZED: NO, DOCKET 0

FACIL:50-397 NPPSS Nuclear Projecti Vni t '2i Nashington!Public Powe 05000397 AUTH BYNAME AUTHOR AFFILIATION BOUCHEYEG.D, Washington Public 'Power Supply System REC IP ~ NAME, RECIPIENT AF F IL'I ATION SCHKENCER,AD Licensing Branch 2

SUBJECT:

Forwards draft Apps H l' to design assessment rept for facility.Apps will be incorporated into amend <<prior Tto

820701, DISTRIBUTION CODE:

SOOIS COPIES 'RECEIVED:LTR.J ENCL.J SIZE:,

~

$ ~

TITLE: PSAR/FSAR

'AMDTS and Related Correspondence NOTES:2 copies all natl:PM.

05000397 RECIPIENT ID CODE/NAVE ACTION; A/D LICENSNG LIC BR 02 LA INTERNAL0 ELD IE/DEP/EPDB 35 MPA NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/t~iTEB 17 NRR/DE/SAB 2A NRR/DHFS/HFEBPO NRR/DHFS/OLB 30 NRR/DS I/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ETSB 12 NRR/DS I/PSB 19 N

SB 23 REG FIL 04 EXTERNAL: ACRS 41 FEMA-REP DIV 39 NRC PDR 02 NTIS

<<COPIES LTTR ENCL 1

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1 RECIPIENT ID CODE/NAME LIC BR NP BC AULUCKiR~

Ol IE 06 IE/DEP/EPLB 36 NRR/DF/CEB NRR/DE/GB 28 NRR/DE/MEB 18 NRR/DE/QAB 21 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRR/DHFS/PTRB20 NRR/DSI/ASB 27 NRR/DS I/CSB 09 NRR/DSI/ICSB 16 NRR/DS I/RA8 22 NRR/DST/LGB 33 BNL(AM<<DTS ONLY)

LPDR 03 NSIC '5

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I I

i fil ti

8202020260 8201i3 PDR AOaCX OSOOOSV7 A

PDR Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 January 13, 1982 G02-82-34 SS-L-02-CDT-82-014

'ocket No. 50-397 fs Mr. A. Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 REQE)gpss 9

EB g )g82~

10 gg ~@eeeregg TII',

Subject:

NUCLEAR PROJECT NO.

2 APPENDICES TO WNP-2 DESIGN ASSESSMENT REPORT (DAR)

Enclosed are sixty (60) copies of Appendices H and I to the Design Assessment Report for WNP-2.

These appendices are being submitted to NRC in draft form at this time and will be incorporated into a DAR amendment prior to July 1, 1982.

Yery truly yours, G.

D. Bouchey, Dep ty Director Safety 8 Security CDT/jca Enclosures cc:

R Auluck -

NRC WS Chin

- BPA R

Rei1 NRC Si te pp4I

1'

MNP-2 APPENDIX I SRV AND LOCA LOADS ON SUBMERGED STRUCTURES

f t I

X.1 ZNTRODUCTXON The f.OCA/SPV aischarge devices and other submerged s ructures are shmn in Pigures 2.1-2, 2.1-6, 2.1-7 and 2.1>>8 and identi~ied in Table 1.

The nest significant hydrodynan5.c load fox each structure is iden-tified in Table 1 ~

J

TABLE I-3 LOCA SRV Loads on Subeer ed Structures Identification of Structures (a)

SRU Line (b) Quencher<

(c) Quencher Support*

2.

Downcomer Vents>>

3. Concrete Columns

4. Bracing Truss>>

s Vent Exit

5. Platform with Qx'ating (6

Elev. 472'-4",

78% open area) 5.

?li scellaneous

Piping, penetrations and supports alon<< containment boundary Identification of Wst S ia nifican t 8 drodvnmi c Load SRV (Due to actuation of ad)acent SRV)

LOCA )et on arms None significant SRV Pool SwelL Drag Pool Swell Drag

( a)

Below vent equi t

( Elev.

4S4'-4 3/4

)

(b> Above vent exit, below initial pool sur ace

{Elev.

466 '-4 3/4" )

( c) Above 'itial pool sur-face>

below maximum pool swell elevation (484'-4 3/4

)

LOCA jet and SRV Pool Swell Drag Pool Svelte. I-pact Loads on discharge devices and their supports during discha ge through the devices are addres"ed elsewhere.

1 r

t Ii,

2 SUNDRY OP METHODOLOGY USED FOR DEFXHXNG LOCA J-T BUBBLE LOADS LO"4 )et/bubble loads are defined using the ring vortex model.

The pool is divided into cones and "o ensure conse vatisa in design@

largest velocity and acceleration values seen by a submerged structure are ass~ed equal to the maximum calculated values anywhere in the applicable xone.

The L'bCA bubble charging model is used to verify/ensure that the design values are conservative.

X.3

SUMMARY

OF H THQDOLOGY. USED POR D FXNXNG LOCA STEM COHDEHSATXOH LOADS Generic drag load" methodology and plant un'que flow fields are used for LOCA steam condensation loads on submerged structures in compliance with the NRC acceptance criteria.

plant unique flow fields are defined consistently with steam condensation boundary loads.

The generic methodology identifies three components of flow induced loads on submerged structures:

accelerat'ion dependent and velocity square dependent in-line loads, velocity square dependent li t load inoraal to the direction of flow).

Representative plant unique chugging flow fields show that the chugging loads on submerged structures are due to acceleration or pressure gradients established in the pool during the impulsive chugging phenomenon, i.e., velocity dependent loads are small, X.4'UMMARY OF METHODOLOGY USED FOR DKPXHXNG SRV GOADS aorso SRV test data on submerged structures are examined to'supple-ment theoretical approacnes of the acceptance cxiteria.

~ The data and their correlation with theoretical approaches of the acceptance cri-teria conf'rm that SRV loads are primarily due to pressure gradients established in the pool during the SRV discharge, i e., velocity dependent loads are ~sal3,.

The dynamic pressure gradients measured across Caorso

column, vend and SRV line are used to define the peak load values (at quencher eleva-tion), the spa ia'istxibution of the load and its time dependence, The pressure time histories recorded on submerged structures show waveform character'sties similar to those recorded at pool boundary.

The SRV loads on submerged st uctures are defined consistently with the plan" unique boundary loads.

The SRV loads on W~lP-2 structures are calculated using the following formulai

(

V

x 2

4 d

Caorso d

HNP-2 x c(P]x L:

@here:

~ Load on a WHP-2 structure {force/unit length)

~ diameter of the struc" ure

~

a load grad'ent factor established using Caorso SRU test

'ata on submerged structures, The ethod to calculate

{X) is explained in Page 6 and Pigure X-> ~

dCaorso horizontaL distance of the structure from the nea. est actuating quencher in Caorso plant C

d~p 2

~ hori ontal distance of the Wp-2 structure froa the nearest actuating quencher

~ boundary pressure load definition from Re"erence X-1 including any modifications agreed upon with the HRC

~ load margin

~

a minimum, value of 1.4 is u"ed for all piping vhich are adequately braced and a value of 2.0 is used for the column which is the only unbraced stucture and is closest to the nearest quencher

O.

,I

Notes on Fi ure I-1 t.

The SRV load gradient is obtained from Caorso data as follows:

Pba

.>~P)9 9

where:

~ measured gradient across the cylindrical structure Pfxont Pba

" Pback 2.

3 ~

I ~ 5 P~9>

Pa>

Pb+ vaveforw characteristics are similar, The value of (W) for each set of Pf (P42, P4~,

P33 Pgg) and (P40i P39 P3$

P53') is obtained from Caorso SRV test data

{single and multiple valve actuations)

For miscellaneous piping vhich run along the suppression pooL

boundary, the load gradient factor (5) equal to that for the coleman ia specified.

RHPEP~CES I-1 'SRV Loads - Improved Qefinition and Application methodology for Nark II Containments,"

Technical Report (Proprie ary), pre-pared by Burns and Roe, Inc. for application to Mashington Public Poser Supply System Nuclear Prospect Ho.

2> submitted to the.

Nuclear,Regulatory Coamission on 7/29/80.

'N N

7

/7

APPENDIX 8 CONPOEQ&ACE OF RHP-2 DESIGN TQ HRC ACCEPTANCE CRITERIA

r 1

I

H.O Conformance oi %P-2 Desi n to NRC Acceptance Criteria B.)

The following Table {Table 8-l1 is,a smma".y of the r5P-2 posi-tion for each of the pool dynamic loads.

This table provides a

description of each load or phenomenon, the Pwrx IE Caner's Gt'oup load specification<

the HRC evaluation reference and the NHP-2 position on the accept'ance crite"ia for each load.

Table H-l Conformance of MHP-2.h:sign to NRC Acceptance Crft,erma Load or Phenomenon L0CA-Ae1ated liydrodyndmfc Loads A.

Subtt~rged Boundary Loads Uurfng Yent Clearfng 8.

Pool Swell Loads l.

Pool Seel 1 Analytica 1 Hodel a)

Afr Bubble Pressure b)

Pool Swell Elevatfon ha~aTI 5roers roop

~Load 5 ecificacioo 24 psf over-pressure added to local hydrostatic belch vent exft (walls and basemat)-

linear attentuatfon to pool sul fdceo Calculated by the pool scull analytical model (PSRH) used fn calculation of subnerged boundary loads.

Use PSAtk Mith polytropic exponent of l.2 to a maxfmma sue)1 height a8ifch fs the greater of k.5 vent subtnergence or the elevatfon correspondfng to the dry+.ll floor uplift P

per tiUREG 0487 crlterfa I.A.4.

The associated maximums w.teel 1 afr compressfon is used for design assessment.

Evaluation ll.Ael $3]

ill.8.3.a I,l]

lI.A.2 1.2]

os t on on Acce tance Cr Iteria Acceptable.

Acceptab le.

h Acceptable.

Load or Ptrenomnon ar rners roup Load S ecfffcation Table 0-I (Cont fnued)

Fvaluatfon RIP-if%as On on Acce tance Crkterfa c)

Pool SMel 3 Velocfty d)

Pool Seel)

Acceleratfon e)

Metwell Afr Compression f)

Orywell Pressure Yeloclty history vs. pool elevation predicted by the PSAH used to corrtpute impact loading on small structrrres and drag on gratings between initial pool surface and maxfmerr pool eleva-tion and steady-state drag between vent exit and maximum poo l el evat fon.

Analytical velocity var fat ion is used up to max fmum velocf ty.

Haxfmrurrr veloci'ty applies thereafter up to max)mum pool swell, PSAN predicted velocities multiplied by a factor of l.l.

Acceleration predicted by the PSAH.

Pool acceleration is utilized fn the calculation of acce'leratfon loads on sub-'erged components during pool s we l l.

Metwell afr crxrrpress ion fs calculated by PSAH.

fhthods of NEOH-l0320 and HE00-20533 Appendix B.

Utilized

$n PSAH to calculate pool swell loads.

III.8.3.a.3 Qg Ill.8,3.a.4 [1]

II.A.2 t.2]

I II.8.3.a.6 [I)

Acceptab le.,

Acceptable.

Acceptable.

Acceptable.

Load or Phenomenon

'll Load 5 ec ification Table H-1 (Continued) fva 1ua tion os t on on Acute tance Criteria 2.

Loads on Submerged 8oundaries 3.

Impact Loads a)

Sma 1 1 Structures b)

Large Structures.

c)

Grat ing 4.

II'atMe'll Air Compression a)

Mall Loads Haxfmum bubble pressure predicted by the PSALM added uniformly to local hydrostatic below vent exit. (wal ls and basemat) linear attentuation to

pool surface.

Applied to walls up to maxfmua pool elevation.

1.35 x Pressure-Velocity correlation for pipes and 1

beams based an PSTF impulse data and flat pool assumptfon.-

Yarfable pulse duration.

ttone - Plant-unique load where applicable.

t(o impact load specff ied.

P drag vs.

open area corre-lation and velocity vs.

elevation hfstary from the PSAH.

P drag multiplied by dynamic load factor.

Dfrect application to the PSAH calculated pressure due to wet-we 1 1 compress fon.

III.8.3.b fl]

111.8.3.c.l I.l]

111.8.3.c.6 [1]

Cr fteria A.5 f3]

111.8.3.c.3

[13 Criteria A.3 I3]

111.8.3.d.1 Ili Acceptable Acceptable.

h Acceptable.

MHP-2 has no large structures fn the pool se.ll zone.

hccep tab 1 e.

Acceptable.

b)

Diaphragm ffpward Loads 5.2 ps id,for diaphragm loadings 2.12.7 [3]

only.

Acceptable.

I

Load or Phenomenon Nark Il t4ners Group Load Spec )fIcat ion

'fable H-1 (Cont in>mii)

=R

=IRl Tl Ct1 Evaluation Acce )tance Criteria 5.

Asyxeetr Ic Pool LOCA C.

Stela Condensation and

. Chugging Loads l.

Oouncener Lateral Loads a)

Single Vent Loads (24 in.)

b)

Hvltiple Vent Loads (24 in.)

Use 20 percent of maximum pressure statistically applied-to 1/2 of the submerged bubble.

Use single vent dynamic lateral load developed In HEOE-23806.

Use mltivent dynamic lateral load developed in HEOE-24106-P and llEOE-24194-P.,

Criteria A-4 [3j 1l.A.3 [2g 2.3.3.2 f3]

Criteria B.l.a [3j 2.3.3.3 f3]

Acceptab)e.

Accep tab le.

c)

Sfng)e/Hu)tiple Vent Hu)tipiy basic vent loads by Loads (28 In.)

factor f 1.34.

2.3.2.1 [33 O.l.b f3]

2.

Submerged Boundary Loads a)

High/Hedium Steam

- Flux Condensation Osci 1 )ation Load b)

Lou Steara Flux Chugging I.oads Use method described in IIEOE-24288-r f43.

Representative pressure fluctuatfon taken from 4TCO (IIEOE-24285-P) test addeg to local hydrostatic.

2.2.2.1.3 f33 2.2.2.3 f3]

C.O. loads are not governing design condition for N/P-2.

Plant unique.

chugging report entitled "Chugging Loads-Revised Oef inition and App) ication ~

Methodology for Hark 11 Containments" submitted Ju)y, 1981.

A

Load or Phenomenon Table 11-1 (Continued)

'Nar'k I'I Siners Zr'oup HRC Loa~d S eclfication Evaluation

%Rr-EYosl'ffnn on

~Ace@ tance Criteria 4) b)

Low F<ti>aa Flux Chugging Loads (continued)

- Uniforrrr loading conditions Asymnetr ic loading Use method descr ibed in HEOE-24302-PI.4]

Representative pressure fluctuation taken from 4TCO test [NEOE-24285-Pj applied as described tn HEOE-24822-P.-

See previous page.

See previous page.

11.

SRY-Re'lated 8 ~rod anic Loads A.

Pool Tenrperature Limits for K-querrcher S.

Qrencher Air Clearing Loads I

210 degrees Fahrenheit.

Hark 1I plants ut'tlizing the four arrrr quencher, use quencher load methodology described in OFFR.

Criteria II.2 [1]

MHP-2 Plant unique SRV

{X-quencher) load report entitled "SRV Loads

- Definition and Appl ica- 'w tion Nethodologg for Mark 11 Containeents subrrr$ tted

August, 19&0.

HRC Criteria II.1 and Acceptable.

IIe3 [lj C.

Quencher Arrrr and Tie-Gown Loads 1)

N-quencher Arm loads Includes vertical and lateral arm load transmitted to the basenat via the tie-down.

Vertical and lateral loads developed on the basis of bounding assumption for air/

water discharqe frea the.--

quencher and conservative com-b ina't ions of rrraxilllUN/Ihinirrrurrr hubble pressure acting on the quencher.

11I.C.2;e e2 [1]

1I I.C.2.e. 1 Accept able.

Acceptable.

Load or Phenomenon Hark 11 Owners Group

~Load 5 catt'icatton Table l)-1 {Continued) 18C fvaluat)on LFlFYllo~st on on Acce tance Criteria 2.

X-quencher Tfe-down Loads n

C /E~E 3tructure Loada SRY Air Bubble Loads II.C.I above plus vertical transient wave and thrust load~.

Thrust load calculated using a standard nxwenturn ha)ance.

Vertical and lateral moments for air or water clear-ing are calculated based on conservative clearing assuiptinns.

III.C.Z.e.2 ll3 Acceptable.

l.

Standard Drag 1n Acce 1 erat ing Flow Fields Drag Coefficients are presented in Attaclvuent 1.k of the Limner FSAA.

Acceptable with the following mod ifica-cation:

I) Use C}l " CH-1 in the FA formula.

2) For noncyl lndr ical structures use lift coefficient for appropria'te s'hape or CL I 6

3) The standard drag coeff ic lent for pool swell and SRV osc 1llat ing bibb les should be based on data for structures with sharp edges.

Generic "drag load" methodology acceptable.

Plant.un)que flow fields are consistent with 11.8 of this table.

hopi itudes for SRV loads verified by CAORSO data on submerged structures (See DAB Appendix I).

A f

• I

Load or Phenomenon ar wners roup L~oad 5 erirication Table

)1-1 (Continued)

Evaluation Ig-rgosSSon on Acce tance Criteria 2.

Equivalent Un't os Flow Vuloc ity and Acceler-ht ion'.

Interference Effects 8.

Lo"A Jet Loads C.

Steam Condensation Drag

'Loads

!Y. Secondary Loads A.

Sonic Mave Load U.. Cooyressive Mave Load C.,-- Post Swe)1 Mave Load D.

Seisraic Slosh Load Structures are segmented into small sections such that 1.D<

L/0 < 1.5.

The loads are then applied to the geometr ic center of each segment.

A detailed methodology is presented in Attachment 1.k of the 2(mmer FSAR.

Calculated by the Ring Vortex Model.

Ho generic load methodology prov)deda Negligible Load - none specified.

Hegligib)e Load - none specified.

Ho generic load providede Ho generic load provided.

Acceptable.

Acceptable.

2.2.4.3 [33 fAP-2 load specification and NRC review is addressed in NHP-2 SER.

Acceptable.

Acceptable.

Plant unique load speci fication addressed in MNP-2 SER.

.Plant unique load specification addressed in NP-2 SER.

See III. A.l. above See III. A.1. above Acceptable GeneriC-

"drag load" Nzthodo logy acceptab le.

Plant unique f)ow fields are consistent with I.C.2.a end I.C.2.b of this table.

(See OAR Appendix I).

Acceptable.

Accep tab le.

See OAR Pg.N020.44-1 See OAR Pg.R020-44-1

T

Load or Phenoeenon IT~ p Load S ecif ication Table H-l (Continued)

Eva)nation os Qn on Acce tance Criteria E.

Fallback load on Submerged Boundary F.

Thrust Loads G.

Friction Drag loads on Vents H.

Vent Clearing Loads Negligible Load - none spec iffed.

thmentum balance.

Standard friction drag ca lculat fons.

Meg)fgfble Load - none specif ied.

Acceptab le.

Acceptable.

Acceptable.

'cceptable.

Acceptable.

Acceptable..

Acceptable.

Acceptable.

N0TES TO TABLE

[1]

NRC Acceptance Criteria set fortii in HUREG-0487.

[2]

AC Acceptance Cri ter ia set forth in Supplement I of NlAEG-0487.

V f 3]

HRC Acceptance Criter fa set for th in NtJREG-0008.

b

'C