ML20053B595

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Slide Presentation Entitled Plant Unique Analysis Rept,Mark I Containment Program
ML20053B595
Person / Time
Site: Cooper Entergy icon.png
Issue date: 04/30/1982
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20053B592 List:
References
NUDOCS 8206010026
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Text

-.._.m,_

Nebraska Public Power District l

l l

1 l

Cooper Nuclear Station Pi_ ANT UNIQUE ANALYSIS REPORT l-Mark I Containment Program i

l I

Revision 0 A p ril,19 8 2

$50'Eb8EE'o?888 hse PDR

- ~ - - - -

~

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j INTRODUCTION 1

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l s

CNS MARK I CONTAINMENT REEVALUATION COMPLETE e

REEVALUATION BASED ON LOADS NOT CONSIDERED IN ORIGINAL DESIGN e

PUAR DESCRIBES EVALUATIONS PERFORMED LOAD DEFINITIONS MODIFICATIONS INSTALLED.

ACCEPTANCE CRITERIA EVALUATION RESULTS e

PRESESENTATION ATTENDEES MR. L. KNNCL, (NPPD) DIVISION MANAGER, NUCLEAR ENGINEERING MR. J. PILANT, (NPPD) DIVISION MANAGER, LICENSING AND QA MR. R. D. BOYLE, (NPPD) MANAGER NUCLEAR ENGINEERING i

MR. D. W. OGDEN, (KE) PROJECT MANAGER, CNS MARK I PROGRAM MR. R. J. STUART, (EDS) VICE PRESIDENT l

MR. M. N. SHULMAN, (EDS) DIVISION MANAGER, ADVANCED ANALYSIS i

1 MR. R. BROMAN, (EDS) DIVISION MANAGER,

[

l ENGINEERING SERVICES MR. A. P. CIMENTO, (EDS) SUPERVISING ENGINEER, ADVANCED ANALYSIS l

1 PRESEN'TATidN CONTENTS

~

ll t

SUMMARY

1:

OF CONTAINMENT ii MODIFICATIONS

SUMMARY

OF LOAD DEFINITION AND TREATMENT i

SUMMARY

j l

OF STRUCTURAL i

EVALUATIONS i

i I

i i

1

l OVERVIEW 0F PROGRAM HISTORY e

ORIGINAL DESIGN CONSIDERED ONLY DESIGN TEMPERATURE AND PRESSURE FOR LOCA e

IDENTIFICATION OF ADDITIONAL LOADS MARK III CONTAINMENT LARGE SCALE TESTING MARK I OPERATING EXPERIENCE e

NRC REQUEST IN 1975 FEBRUARY, S/RV DISCHARGE APRIL, NEW LOCA LOADS e

FORMATION OF OWNER'S GROUP SHORT TERM PROGRAM LONG TERM PROGRAM l

SHORT TERM PROGRAM e

OBJECTIVE VERIFY INTEGRITY AND FUNCTIONAL CAPABILITY JUSTIFY CONTINUED OPERATION e

RESULTS REPORT OUTLINING TASKS IN 1975 EVALUATIONS COM'LETED IN 1976 REQUIRED ACTIONS TAKEN REQUIREMENT FOR PUA ESTABLISHED FUNCTIONAL PERFORMANCE OF CONTAINMENT DEMONSTRATED FACTOR OF SAFETY OF 2 AGAINST

~

FAILURE

^"*--*eN~

y._

4 LONG TERM PROGRAM e

INITIATED IN JUNE 1976 e

OBJECTIVES DESIGN BASIS LOADS RESTORE ORIGINAL SAFETY' MARGINS e

REQUIREMENTS EXTENSIVE TESTING AND ANALYSIS PROGRAM ESTABLISH CRITERI A EVALUATE LOAD MITIGATION DEVICES AND SYSTEM MODIFICATI0t:S PLANT UNIQUE ANALYSIS AND MODIFICATIONS e

STATUS PUAR COMPLETED MODIFICATION TO BE COMPLETED BY SEPTEMBER 1982 i

- _ --. - _7._;, - _ _ _ _..

e DESIGN CRITERIA i

1 l1

,i Original New Requirements Requirements Exceptions u

li Mark 1 Structural Dynamic Response ASME B&PV Code

  • L Structural Acceptante Criteria Combination S tion III PUAAG - I.s modified June 1967

- i by NRC Acceptance j

Criteria jl 4

Mark I Structural Dynamic Response Piping USAS B31.1 PUAAG - As modified

+

1967 by NRC Acceptance Criteria

.}

Mark I Structural i

Acceptance Criteria Systems

^

None PUAAG

'As modified by NRC Acceptance Criteria 1

Design Pressure G.E. Load Definition DBA CO Random Phasing Loads and Report (Nov. 1981)

MVA S/RV Pressure Temperature as modified by NRC Combination Acceptance Criteria 30% R.H. in S/RVDL II I,

n i 5

PRESENTATION CONTENTS -

SUMMARY

OF MODIFICATIONS Load Mitigation

-Systems

-Hardware Structural Considerations j

-Torus

-Vent System o

-S/RVDL Systems l

-TAP Systems ll

SUMMARY

ll OF LOAD DEFINITION it ja AND TREATMENT b ',

SUMMARY

l OF STRUCTURAL

]

EV ALUATIONS -

I i

SUMMARY

OF CONTAINMENT MODIFICATIONS e

LOAD MITIGATION PUMP AROUND SYSTEM - MAINTAIN AP S/RV LOW-LOW SET LOGIC MSIV WATER LEVEL TRIP TORUS TEMPERATURE MONITORING SYSTEM TRUNCATION OF DOWNCOMER VENT HE ADER DEFLECTOR T-QUENCHER INSTALLATION e

STRUCTURAL REINFORCEMENT TORUS SUPPORTS STRENGTHENED ADDITION OF SADDLES TORUS RING GIRDER STIFFENERS l

DOWNCOMERS REINFORCED l

VENT SYSTEM SUPPORT ALTERED VACUUM BREAKERS REINFORCED l

PLATFORM AND MONORAIL SUPPORTS CT!HTORCED S/RVDL PIPING REROUTED S/RVDL PIPE SUPPORTS MODITT2b,.:a0ED TAP SUPPORTS MODIFIED, ADDED INTERNAL AND SMALL BORE PIPE REROUTED PUMP AND VALVE CONFIGURATIONS STRENGTHENED

OBJECTIVE: INCREASED COLUM CAPACITY RlhG f GIRDER TORUS m

SHELL I

I I

il llll WEB L

R EIN F.

PLATES I

IllL.. JII i

ll

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  • SUPPORT ~

l 1l.

l

-h COLUMN _

8 l

w14" x iss" l

p

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COL REINF PL p p 4

Ip,q ti 2-1S" x %" INSIDE COL.

1 i t' ll lI 2-16" x 1" OUTSIDF COL.

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i ANCHOR i

pj BOLTS j

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PLAN TYPICAL COL ANCHOR ASSEMBLY TORUS SUPPORT COLUM

.,,. _ ~, _,.. _ _

l OBJECTIVE: INHIBIT SHELL OVALIZATION I

E, COLUMN E TORUS 5

13*-6 3/16" RING 4

GIRDER

j f

'I TORUS

(

4

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GIRDER SHELL

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FuNGE OVERLAY 8~

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WELD

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WEB REINF.

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BASE PL ll FLANGE PL SOLE PL

%" WEB PL 1%" x 20" 3%" x 22" x 3'-6" 1%" x 29" x 3*-0" j

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I TORUS SADDLE I

OBJECTIVE: MITIGATE POOL SWELL LOADS ON VENT HEADER

( VENT HEADER I

h h

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EL 880'-11" 2*-6" ll EL 879*-7%"

2%") PIN 7

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2-4 x 4 x 5/8 Im ANGLES

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l 16"$ SCH. 80 f{4 jg-DEFLECTOR j

WITH 2-8 x 8 x %

b ANGLES

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HWL EL 875*-2"

=-

VENT HEADER DEFLECTOR I

OBJECTIVE: REDUCE DRAG LOADS ON VENT HEADER SUPPORTS

( TORUS N

f RING GIRDER

_q s-

+>.

__e.

.11,

%" PLATE c==a I

VH SUPPORT g

6** $ SCH XXS 8

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4 8" ( SLEEVE

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1" PLATE 2*-6"

)

Et. aso -n-( VENT HEADER I

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57

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i VENT HEADER SUPPORT COLUMNS o

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OBJECTIVE: REDUCE STRESSES AT INTERSECTION E, VENT HEADER,

,4..

5/8" PAD AND STIFFENER PL 9

4' E L. 880*-11" DOWNCOMER

/

REINF. 5/8" PL 4I

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3/8" 4d I

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<"4 SCH.120 SLEEVE 3/8" RING l

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DOWNCOMER REINFORCEMENT

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OBJECTIVE: REDUCE STRESSES AT PENETRATION DUE TO POOL SWELL IMPACT AND FROTH IMPINGEMENT

(, VENT HEADER DRYWELL/WETWELL VACUUM BREAKER

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)

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EL 880'-11"

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5/8" PAD AND STIFFENER PL DRYWELL/WETWELL VACUUM BREAKER REINFORCEMENT

OBJECTIVLS:

-INSTALLATION OF T-QUENCHERS: BETTER DISCHARGE DEVICE DISTRIBUTION

-REROUTE PIPE: MINIMIZE LOADS

-RESUPPORT PIPING WETWELL AN" DRYWELL: QUALIFY F0P. LINE CLEARING LOADS

( REACTOR

'l LLS* lNDICATES

  • A* lNDICATES LOW.LOWSET FUNCTION l

ADS FUNCTION

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( TORUS

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LINE DESIGNATION f

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'L SET POINT PRESSURE O

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T GUENCHER S/RVDL (A TO H) 10 & SCH 43 - D RYWELL

,10 $,S,CH 80 - WETWELL WETWELL ROUTING 0F S/RVDLS

i OBJECTIVE :

TO REDUCE DRAG LOADS PLATFORM-E ' RING GIRDt,q

( TORUS A. /

\\1

& SPARGER E TORUS BAY l

i

  1. 1

/

g E TORUS I

, HPCI DISCHARGE l

24" ( SCll 40 P-gi:-

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24" $ $PARGER e I

5 b.

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SUPPORT -

I ASSEMBLY'

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STIFFENERS f

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t TORUS PEN.

i X214 i

lf SECTION i

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!!D;I TURBIliE EXHAUST - REROUTE /RESUPPORT

OBJECTIVES:

-IMPROVE POOL CIRCULATION (THERMAL MIXING)

-BRACE: 10R HIGH DRAG LOADS E PENETRATION

['p'

._x21,93&B (4

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I a

i 8

TORUS SHELL i

18" 6 RHR RETURN 5

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1%" CO LLAR 18" x 14" RED 0CER

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[

14" LR ELBOW CUT TO 66*. 30'._._

'I......

SUPPORT 8

3" ) SCH XXS

- t.

RHR PUMP TEST RETURN LINE [10DIFICATION

I

....-m-

TORUS ATTACHED PIPING MODIFICATIONS e

PIPE SUPPORTS ON LARGE BORE TAP 14 ADDED 137 0F 239 MODIFIED e

SMALL BORE TAP 60 NEW OR MODIFIED SUPPORTS t

4 LINES REROUTED e

BRANCH PIPING 25 NEW OR MODIFIED SUPPORTS e

VALVES 13 VALVES REINFORCED l

l e

TORUS SHELL PENETRATIONS 1

3 PENETRATIONS REINFORCED e

ECCS PUMPS 4 PUMP ANCHORAGES REINFORCED i

SYSTEM MODIFICATIONS e

DRYWELL-TO-WETWELL AP MAINTAIN PRESSURE DIFFERENTIAL BETWEEN DRYWELL AND TORUS MITIGATE POOL SWELL LOADS ON TORUS AND VENT SYSTEM e

LOW-LOW SET RELIEF LOGIC INCREASE REACTOR DEPRESSURIZATION FOLLOWING S/RV ACTUATION INCREASE TIMING BETWEEN ACTUATIONS REDUCE LOADS DUE TO CONSECUTIVE ACTUATIONS AND NUMBER OF S/RV ACTUATIONS e

MSIV WATER LEVEL TRIP DELAY MSIV ISOLATION TO RELEASE MORE REACTOR ENERGY ELIMINATE 2ND ACTUATIONS OF S/RV DURING IBA./ BA S

l e

POOL TEMPERATURE MONITORING SYSTEM MEASURE LOCAL FOOL TEMPERATURES NEAR T-QUENCHERS ENSURE POOL TEMPERATURES STAY WITHIN ALLOWABLE LIMITS

8 4

~

PRESENTATION CONTENTS - LOAD DEFINITION AND TREATMENT i

8

SUMMARY

OF CONTAINMENT MODIFICATIONS LOCA Related Loads i;

-Pool Swell i

1

-Condensation i

Oscillation

-Chugging S/RV Related Loads l

Load Combinations

,1 :

l

SUMMARY

i n

OF STRUCTURAL.

li 9

EVALUATIONS e

SUMMARY

OF LOAD DEFINITION AND APPLICATION e

LOAD DEFINITION IS BASED ON:

GE LOAD DEFINITION REPORT MARK I PUAAG NRC ACCEPTANCE CRITERIA NRC SAFETY EVALUATION REPORT e

PLANT UNIQUE LOAD DEFINITIONS e

LOAD APPLICATION l-l l

.; _ ~ 7.-_

_ ;- 7 -..

(

LOADS AND LOAD COMBINATIONS e

THERMAL-HYDRAULIC PARAMETERS BASED ON CNS FSAR ALTERED BY SYSTEM MODIFICATION USED BOTH ZERO AP AND CURRENT AP e

ORIGINAL DESIGN LOADS DEAD LOADS SEISMIC LOADS PRESSURE AND TEMPERATURE VENT THRUST LOAD JET FORCES ON DOWNCOMER PIPES e

LOCA RELATED LOADS e

S/RV DISCHARGE RELATED LOADS e

DETERMINATION OF LOAD COMBINATIONS 1

o f

e

- ~~ ~

- - ~,..

~~

~

. _. ~

LOCA RELATED LOADS t

e CATEGORIES OF A LOCA DESIGN BASIS ACCIDENT (DBA)

INTERMEDIATE BREAK ACCIDENT (IBA)

SMALL BREAK ACCIDENT (SBA) e SPECIFIC LOADS AND TRANSIENTS

-. PRESSURE AND TEMPERATURE VENT SYSTEM THRUST POOL SWELL CONDENSAT'ON OSCILLATION CHUGGING I

l i

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5 m

g W

e 0 {

0 6

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h LOAD /STRUCTURI MATRIX d

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$ $h $h " L, a

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InADS e

3 2

3 6

s 4

3 5 30 AE w

c LOCA RE!ATED LOADS Containment Pressure and Temperature X

X X

X X

X X

X X

X X

I I

Vent System Thrust Loads steeds Associated with Pool Swell Terun Met Tertiaal Tends Y

Y Torus Shell Pressure Histories Impact and Drag Loads Vent System IsTaet and Drag X

X X

X X

X Other Structures X

X Troth Impingement X

X Pool Taliback X

X t_N* A Jet 1

1 I

LOCA Bubble Drag Condensation Oscillation Torus Shell Loads X

I X

X X

Vent System Leads Other Submerged Structures y

y Chugging Torus Shell LoaJs X

I X

X X

Vent Svetem Londo Other Submerged Structures y

y y

S/RV DISCHARCE RELATED 14 ADS I

X Terus Shell leads I

X X T/0 k'ater Jet Leeds T/Q Air Bubble Induced Loads y

y y

y X

S/pvrt clearine toads 1

T 4uencher Thrust Leeds

{-TORUS

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DR YWELL 6

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L TORUS EL. 3 76*=T *2**

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t YACUUM BREAKER 4

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4124 lb/ft AP a 0.0 gga

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942 lb/ft i

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__ t(see) l O.504.623 0.7223 (w.r.t. DBA Start) g,g p g g,4 gg g,gyg Time (see)

Impact and Drag Lead on vacuuan Eresker Velve Impact and Drag ".and on nlain Vent.F (L 1

l l

FIGURE 2.17 POOL SWELL !MPACT/ DRAG IDAD TRANSIENTS ON MAIN VENT, AP = 1.0 psid

. _.... - _. _ _ _. +. - - - _ - - _ _.. _ _ -

1 t

t a

a s.

=

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LOAD /STRUCR M ETRIX 3

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a i d

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E E< E EI LOCA REIATED LOADS Containment Pressure and Temperature X

X X

X X

X X

X X

X Vant Systes Thrust Loads I

X X

toads Associated with Paol Svell Terim Met Ver*4aal tends Y

Y Torus Shell Pressure Histories Impact and Drag loads Vent System Impact and Drag X

X X

X Other Structures X

X Froth Impingement I

X Pool Ta11back X

X LTA Jet LOCA Bubble Drag I

X X

  • Condensation oscillation Torus Shell toads X

I Vent System Leads I

X X

Other Submerged Structures y

y Chugging Torus Shell Loads X

X Vent Svetem Leeds X

X X

Other Submerged Structures y

y y

S/RV DISCHARGE RELATED LOADS Terus Shelf toads X

X T/0 Water Jet toads X

X X

T/Q Air Bubble Induced Londe y

y y

y S/RVDL Clearine Leeds I

T-Ouencher Thrust Loads X

1

+ -

-w-w,-

e

- - ~ -

LOCAL Patlluat OSCILLateg amaw wifuqLL waseuues eatStuot CSCiLLat'Og aawkstv06 ase seaCl Aas laf TOmul SOT 10u bta0 Cluttne l

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es 3

o All 50 frequencies soeumed in phase e Frequency set to any torus estural frequency within the band (ring strder eeJd;2 torue frequencies in-dicated on f requency amis) 1 e Envelope 3 alternative emp116 des in 4-16 Na range

=

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10 15 30 25 30 35 M

AS M

l Frequency Ols) l l

FIGURE 2.21

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l TORUS PRESSURE AMPLITUDE DISTRIBUTION FOR CONDENSATION OSCILLAT o

Ll l-(

- - ~ ~ -, - - - -

DBA C0 RAND 0f1 PHASING e

DESCRIPTION

' DESIGN RULE FOR COMBINING STRUCTURAL RESPONSES TO C0 LOAD HNRMONICS 4 ASUM + 46 SRSS 1.3 X TIME HISTORY WITH RANDOM PHASE ANGLES e

REASONS

~

FSTF TEST DATA SHOWS RANDOMNESS ASUM RULE SIGNIFICANTLY OVERPREDICTS FSTF DATA OTHER AREAS OF CONSERVATISM IN CO LOAD DEFINITION e

JUSTIFICATION EMPIRICAL DATA 0 EXAMINE FSTF DATA FOR RANDOMNESS 0 DESIGN RULE PREDICTIONS BOUND FSTF MEASURED RESPONSE ANALYTICAL STUDIES 0 STATISTICAL STUDIES WITH RANDOM PHASING 0 DESIGN RULE EXCEEDS 84% NEP LEVEL GENERIC MARK I REPORT

  • "Wm MPem.e-w%

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1

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LOAD / STRUCTURE MATRIX d

g.

e, 4

4 m

8, A

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=a =5 i(

=

8

=

gg 2

-e 3

W 5

2i j

E 3

7 EE E EI LOADS E

LOCA REIATED LOADS Containment Pressure and Temperature X

X X

X X

X X

X X

X vent System Thrust Loads I

X X

Leeds Associated with Pool Swell Te-tm wet ver m at toads Y

Y Torus Shell Pressure Histories Impact and Drag Loads Vent Svstem tr act and Drag X

X X

X Other Structures I

X Troth Impingement X

1 X

X Pool Ta11back X

X LOCA Jet I

X X

LOCA Bubble Drag Condensation Oscillation Torus Shell Loads X

I Vent System Leads X

X X

Other Submerged Structures y

y

  • Chu gging l

Torus Shell Leeds X

X vent Svetem Loads I

X X

Other Submerged Structures y

y y

S/RV DISCMARGE RELATED 14 ADS Terus Shell toads X

X i

X X

X

?/O Vater Jet 1.eads T/Q Air Bubble Induced loads y

y y

y X

s/RWI, Clearine Leeds l

X T-Ouencher Thrust Loads e

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l

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b O

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LOAD /STRUCTL1tX MATRIX d

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~3 14 ADS E< ~E E 55 E LOCA REIATED LOADS Containment Pressure and Temperature X

X X

X X

X X

X X

X Vent System Thrust i.oads I

X X

Loads Assnefated with Pool Swell

?nrun Met vertfeat innen Y

I Torus Shell Pressure Histories y

y Tepact and Drag Loads vent Svstem Trpact and Drag 1

X X

X Other Structures X

X Froth Impinnement 1

X X

X Pool Ta11back X

X 1.OCA Jar X

X X

LOCA Bubble Drag Condensation oscillation Torus Shell Loads X

X vent Svstem Leadr X

X X

Other Submerged Structures y

y Chugging Torus shall Loads X

I Vent Svetes Loads X

X X

Other Submerged Structures y

y y

  • S/RV DISCHARGE RELATED TAADS Torus Shell Loads X

X X

I X

T/0 Vater Jet Leeds T/Q Air Bubble Induced Loads y

y y

y X

S/nTL Clearine Loads X

T-Ouencher Thrust Loads 6

S/RV DISCHARGE TORUS SHELL PRESSURES MULTIPLE VALVE ACTUATIONS e

DESCRIPTION COMBINATION METHOD FOR SPATIAL DISTRIBUTION OF TORUS PRESSURES DUE TO MVA 1.2 X SRSS OF PRESSURE FROM EACH DISCHARGE DEVICE o

REASONS ABSOLUTE SUM OF PRESSURES ASSUMES IN-PHASE BEHAVIOR OF BUBBLES i-;" PHYSICAL BASIS FOR IN-PHASE BEHAVIOR MVA PRESSURES LIMIT DESIGN e

JUSTIFICATION PLANT UNIQUE STATISTICAL STUDY MODEL ACTUAL PHASING OF BUBBLES WITH RANDOM VARIATION OF PLANT PARAMETERS 1.2 SRSS PRESSURE BOUNDS RESULTS OVER 90% OF THE TIME 1

.i i

l

l

' L_

S/RV TORUS SHELL PRESSURES 30% RELATIVE HUMIDITY e

DESCRIPTION INITI AL S/RVDL RELATIVE HUMIDITY OF 30%

IBA/SBA CONDITIONS ONLY ADS ACTUATION ONLY e

REASONS PURE AIR MASS ASSUMPTION UNREALISTIC STEAM IN DRYWELL DURING IBA/SBA AT ADS, DRYWELL AIR PURGED TO WETWELL e

JUSTIFICATION EXAMINED DRYWELL STEAM CONTENT TRANSIENTS CNS S/RVDL VACUUM BREAKER SET POINTS SHOW 90-100% RH IN DRYWELL SHOW 30% RH IN S/RVDL IS STILL CONSERVATIVE

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LOAD COMBINATIONS e

TORUS SHELL e

VENT SYSTEM e

INTERNAL STRUCTURES AB0VE P0OL e

SUBMERGED STRUCTURES e

S/RVD PIPING e

TORUS ATTACHED PIPING e

FATIGUE BASIS FOR 40 YEAR LIFE c.

i e

e LOCA-DbA PRESSURE AND TDG'ERATURE TRANSIENT SINGLE S/RV ACTUATION

_T_ORU_S SHELL LOADS on-E TORUS SHELL PRESS.

O DUE TO POOL SWELL d

?

8 C/O TORUS SHELL t.oADS

,e

.3 CHUGGING TORUS SHELL LOADS 1

e-I 0.0 5

35 65

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l' Time After thCA (sec) i FIGURE 2.25 s

t TORUS SIIELL IDAD COMBINATIONS FOR IDCA-DBA I

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LOCA-DBA PRESSURE AND TDEERATURE TRANSIENT y

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VENT SYSTEM PRESSURE TRANSIENT AND THRUST 14 ADS d

l

'b t

i

~'

POOL SWELL IMPACT & DRAG FROTH IMPINGEMENT

  • I I

j E

O Uy C/0 DOWNCOMER LATERAL c

LOADS

]

O a

j C/0 VENT SYSTEM IDADS f

k

' l, 8

CHUGGING DOWNCOMER I

LATERAL IAADS 1

1.

'1 CHUGGING VENT SYSTEM LOADS s

0 5

35 65 Time Af ter LOCA (sec)

  • For main vent only.

l

    • For submerged portion of downcomers see also Figure 2.32 3

FIGURE 2.28

(,

l VENT SYSTEM IDAD COMBINATIONS EUR IOCA-DBA**

)

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1 I!

!i 4

1 d

jL

.i

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't t'

'i E

T/Q WATER JE7. IDADS S

l

i o

4 E

O

1' o

T/Q AIR BUBBLE INDUCED LOADS i

8 a

l 1

y a

t to g

2 t

Time After S/RV Actuation (sec) i ti t

l 0"

i!i t - S/RVDL water clearing time 1

i i

t = time at which S/RV bubbles reach pool surface t :

2 ll l :

4 FIGURE 2.35 i

i S/RV DISCilARGE ICADS ON SUBMERGED STRUCTURES

.l

i L

PRESENTATION CONTENTS -STRUCTURAL EVALUATION

.[

i

SUMMARY

OF CONTAINMENT MUDIFICATIONS 1

l

)

SUMMARY

i 3

1

OF LOAD DEFINIT.lON.

AND TREATMENT 4

i Torus Shell & Support l

Vent System & Supports j

l S/RV Discharge Piping l'

L Torus Attached Piping L

4 ll i

1 l

l

TORUS SHELL e

LOADS 27 LOAD COMBINATIONS DEFINED POTENTIALLY BOUh31NG ONES CONSIDERED 4

e DESIGN ALLOWABLES CLASS MC VESSEL - SUBSECTION NE BUCKLING ALLOWABLES e

ANALYSIS METHODS SHELL MODELS 1/32 SEGMENT COUPLED SHELL-FLUID MODEL 1/f4 SEGMENT PLATE ELEMENT MODEL-SEISMIC STATIC ANALYSIS

- PRESSURE AND TEMPERATURE

~

- GRAVITY

- SEISMIC DYNAMIC ANALYSIS

- POOL SWELL

- DBA CO

- CHUGGING

- S/RV DISCHARGE e

CODE EVALUATION MAXIMUM SHELL STRESS FATIGUE USAGE

i

TORUS SHELL BUCKLING ALLOWABLES e

DESCRIPTION INVESTIGATION OF DYNAMIC TORUS BUCKLING BUCKLING NOT A CONCERN FOR MARK I LOADS e

REASONS CODE COMPRESSIVE STRESS ALLOWABLES BASED 1N STATIC, UNIFORM LOADS MARK I LOADS ARE DYNAMIC, NON-UNIFORM COMPRESSIVE STRESSES OF SHORT DURATION e

JUSTIFICATION LOCA TRANSIENTS NOT CONTROLLING HIGH WETWELL PRESSURE S/RV DISCHARGE EVENTS CONTROL EMPIRICAL EVIDENCE IN-PLANT TESTS CONFIRMATORY NONLINEAR ANALYSIS GENERIC STUDY FACTOR OF SAFETY = 7 SATISFY ASME CODE REQUIREMENTS APPLICATION TO CNS GEOMETRY LOADS

q-----._,-_.__..__,

Torus Shell

/

/

Midside Node Locatfores (Typ)

Ring Girder

/

\\..X'

/

/

[

N.,

/

Typical Element

~

NodalizationT((

.g: '

f'T e

M.~ _

,,f: * ^ ;..,,,- **

)Outside Support

.t Yj f'

Ring Girder Saddle

  • ~
  • T..

.i f

'tj' :qf

.N,

{

Inside Support Column

--N i.

l Structure Fluid

~

Reactor Building Plan View FIGURE 3.1 1/32 SECTION TORUS MODEL

..., _ _ _. ~.. _ _....

k I

t 6

\\ \\

l

\\

\\\\

l

\\\\l

\\\\

\\\\

\\ t, 6 m

i

/

l FIGURE 3.2 90' SECTION TORUS MODEL t

- 1

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

.Tpi-M*%.

TORUS SUPPORT SYSTEM e

DESIGN LOAD COMBINATIONS COLUMN AND ANCHORAGE TORUS SHELL LOADS SEISMIC TIES NET LATERAL LOAD SEISMIC S/RV DISCHARGE PRE-CHUG RING GIRDER SADDLE YORUS SHELL LOADS PRESSURE AND TEMPER ATURE e

DESIGN ALLOWABLES LINEAR COMPONENTS - APPENDIX XVII PLATE AND SHELL SUPPORTS - SUBSECTION NF e

ANALYSIS METHODS SUPPORT COLUMNS SUBSECTION NF ANCHORAGE ASSEMBLY APPEND XVII SEISMIC TIES RING GIRDER SADDLE USED 1/32 SEGMENT SHELL MODEL NONLINEAR ANALYSIS USED FOR INTERMEDIATE SUPPORTS e

CODE EVALUATION MAXIMUM COLUMN / ANCHORAGE LOAD MAXIMUM FATIGUE USAGE l

t i

f i

I

\\

i g m shall peldelde secoe

/

tocatlans W I 4.RPV f

+

Ring Cirder

/

)

j p

i j

1

/

n,.ctor mutidia9 Plan Wi**

f t

y f

.Itsstion rt Col"""

A j?x:

\\ w

~

Q t

/g l

s V

  1. I

^1 ming Ciraer saddle

  1. st '

. ff

}.}7, /,'

j

/Q'<lt 4h rtc>j' 3 ia.

I I

. l, FIGURE 3.3 l

t i

1/32 SECTION TORUS MODEL WITil DKTAILED RING GIRDER SADDLE 4

I i

L RING GIRDER e

LOADS SHELL LOAD COMBINATIONS SUBMERGED STRUCTURE CONCENTRATED REACTIONS e

DESIGN ALLOWABLES MC SUPPORT - SUBSECTION NF EXCEPT PORTION WITHIN LIMITS OF SHELL REINFORCEMENT WHERE SUBSECTION NE IS USED e

ANALYSIS METHODS RING GIRDER ALL STRESSES FROM 1/32 SEGMENT MODEL EXCEPT FOR STRESSES DUE TO DRAG LOADS, WHICH ARE DETERMINED SEPARATELY RING GIRDER ATTACHMENTS i

REACTIONS FROM VENT SYSTEM APPLIED AS EQUIVALENT STATIC LOAD o

CODE EVALUATION MAXIMUM STRESS IN RING GIRDER MAXIMUM STRESSES IN WELD TO SHELL

.l ll MAXIMUM FATIGUE USAGE

+---,-...

1 TORUS SHELL PENETRATION AND ATTACHMENTS e

PENETRATIONS AND ATTACHMENTS INCLUDE:

TAP PENETRATIONS SEISMIC TIES MONORAIL SUPPORTS ECCS PIPING SUPPORTS e

ANALYSIS METHOD REACTIONS FROM APPROPRIATE ANALYSIS

- WRC BULLETIN 107 USED TO OBTAIN LOCAL STRESSES e

LOAD COMBINATIONS RESPONSE TO TWO DYNAMIC EVENTS COMBINED BY SRSS

l

DYNAMIC RESPONSE COMBINATION e

DESCRIPTION COMBINATION METHOD FOR PEAK RESPONSES TO TWO (S/RV + LOCA)

DYNAMIC LOADS 1.1 X SRSS OF PEAK DYNAMIC RESPONSES ASUM OF REMAINING DYNAMIC LOADS e

REASONS ASUM RECOGNIZED AS CONSERVATIVE (E.G. NUREG-0484)

~

PUAAG ALLOWS CDF METHOD WITH 84% NEP e

JUSTIFICATION f

EXAMINE CDF'S USING MARK I

~

DATA (GENERIC STUDY)

SHOW l.1 SRSS BOUNDS 84% NEP CONFIDENCE LEVEL >90%

CONFIRM FINDINGS WITH CNS DATA l

l l-ll h

li

'i l

'f VENT SYSTEM AND SUPPORTS e

VENT HEADER AND MAIN VENT VENT SYSTEM ANALYSES VENT HEADER AND MAIN VENT PENETRATIONS e

D0WNCOMER AND TIEBARS DOWNCOMER/ VENT HEADER INTERSECTION DOWNCOMER ITSELF e

SIMPLIFIED ANALYSIS PERFORMED ON:

VENT DRAIN LINE VENT HEADER DEFLECTOR VENT HEADER SUPPORT SYSTEM l

}

t

c VENT SYSTEM ANALYSES e

FINITE ELEMENT MODELS 1/16 SEGMENT SHELL MODEL BE M MODEL - NON-SYMMETRIC LOADS DOWNCOMER/ VENT HEADER INTERSECTION MODEL e

STATIC ANALYSES PRESSURE AND TEMPERATURE GRAVITY AND SEISMIC VENT SYSTEM THRUST e

DYNAMIC ANALYSES POOL SWELL, TIME HISTORY CO, FREQUENCY DOMAIN CHUGGING, EQUIVALENT STATIC S/RV DISCHARGE, EQUIVALENT STATIC e

CODE EVALUATION MAXIMUM STRESSES MAIN VENT HEADER I

PENETRATIONS

' i

'I

Main Vent N

Support Columns i

Y.S tif f ener Vent Header 3 kx 4

^

.?c.,vx-f ;

I MilliIililth.

M.

ill h til(F,SG

//

q,,E A4.$i a yJ g.x E'

i

%%N V e rit H e a d'e r Deflector h

1 Tie-b a r Downcomers FIGUPI 4.1 1/16TH FINITE ELEMENT SHELL PODEL OF VENT SYSTEM

'l l

I

g

  • * - = ~ ~

n

-43 37 h9 @

33 Q36 40 34 g

O e 3.

32 20 h O

h 30 O

0,,

O :.

OO

. 7, o

O 4.

e

=x 0

2 45 @v h

46 g

b 20 18 i9 00 9 is g

i3 h iO

, t'

@Ja yz hY 45 46 l

l O

i

o. O s.

,,191. Gl,'a ~

Ol'

' @ ;;O

' x

(

ri i I

FIGURE 4.2 180* VENT SYSTEM BEAM MODEL

'l

---..__..e

^

DOWNCOMER/ VENT HEADER INTERSECTION ANALYSIS e

DESIGN ALLOWABLES MC COMPONENT

]>SUBSECTIONNE AND Pg+Pg PL ALLOWABLE INCREASED BY 30% BASED ON LIMIT ANALYSIS e

FINITE ELEMENT MODEL DETAILED LOCAL MODEL UNIT LOAD CASES e

EQUIVALENT STATIC ANALYSIS POOL SWELL I

CO LATER AL LOAD CHUGGING LATERAL LOAD S/RV DISCHARGE DRAG LOADS e

DOWNCOMER ANALYZED USING DETAILED MODEL

'i k

.I

7., -

1

,t j

a U

Nl LE y

)

d.

D l

O M

1'

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n, '

NO IS TR CE 42 EN SE RF EF TI NT IS 3

RE 1

ET DA 4

AL EP E

H R

T U

TE G

NS I

ES F

VU

/G R

l N

EG MN k' f, OI CD

' =,

-w WL NU e

OC 4z,1

/

\\/

DN 7s,s I

v 2s-e

.p5<.

D d9

~

E

$s L

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{a A

mk.

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/N

/

D T

W'/.-

~

8 E

,j g RA' VQ

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\\\\

\\ 3

';\\'

1 \\ \\\\

tii.};!l, il'

.t i(li,i i

(

,t J

S/RV DISCHARGE LINES e

DRYWELL PIPING DETERMINED BOUNDING LOADS FROM MAIN VENT PENETRATION COMBINATIONS SEPARATE MODEL FOR EACH LINE A

$\\

p 3 '

=

gg

+

R A

/

I a. see.e n

a f}.--

a

n:: n!!:Ed31::=:"--

STATIC ANALYSIS DYNAMIC ANALYSIS TIME HISTORY FOR THRUST LOADS RESPONSE SPECTRA FOR VENT SYSTEM MOTION

" * * " ' '*~

l S/RV DISCHARGE LINES e

WETWELL S/RVD PIPING LOADS S/RVD THRUST AND WATER CLEARING POOL SWELL C0 AND CHUGGING DRAG T-QUENCHER AIR BUBBLE DP.AG e

T-00ENCHER EVALUATION e

VACUUM BREAKERS LOADS PRESSURE AND TEMPERATURE TRANSIENTS GRAVITY AND SEISMIC COMPONENT EVALUATED ALL PRESSURE RETAINING PARTS HINGE ARM SHAFT FLANGE AND FLANGE BOLTS 9

~~

-mw-+*w--

~

~

=

.-o*

o.e

~~e-~===

s e

e

- - = - -

msse mm-

  • =

oe=~--+-~

e=wm

  • "--e* * *==

=

~-*w-e

g_.._

TORUS ATTACHED PIPING e

EXTERNAL PIPING ANALYSIS LARGE BORE - A TORUS COUPLING INCLUDED -

MULTI-LEVEL RESPONSE SPECTRA SMALL BORE - UNCOUPLED RESPONSE SPECTRA BRANCH LINES PUMPS AND VALVES e

INTERNAL PIPING DYNAMIC LOADS POOL SWELL C0 AND CHUGGING DRAG S/RV DISCHARGE DRAG TORUS SHELL MOTION e

LOADS ON PIPE SUPPORTS INCLUDE SUBMERGED STRUCTURE LOADS 4

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

...~ __

-m+.

+

.+m.

m.

.n

...-n-

- - ~. -.

I P0OL TEMPERATURE EVALUATION e

DESIGN CRITERI A 200*F LOCAL TEMPERATURE LIMIT TRANSIENT CONDITIONS e

TRANSIENT ANALYSIS SUPPRESSION POOL MODEL LOCAL POOL TEMPERATURE MODEL SEVEN TRANSIENT EVENTS

~

EVALUATION RESULTS e

MAXIMUM BULK POOL TEMPERATURE = 179'F MAXIMUM LOCAL POOL TEMPERATURE = 198'F e

POOL TEMPERATURE MONITORING SYSTEM REDUNDANT MONITORS CONTROL ROOM RECORDER SEISMIC CATEGORY I SENSORS ENVIRONMENTAL REQUIREMENTS 1

)

I

MEETING

SUMMARY

DISTRIBUTION

\\

eket File NRC PDR Local PDR (w/ enclosures)

NSIC 1

ORB #2 Reading ACRS-10

~

J. Heltemes (w/ enclosure 1 only)

L r Chief Project Manager OELD I

IE NRCParticipantsN l

cc: Licensee with short cc list (with Enclosure 1 only) 1 Mr. J. M. Pilant, Director Licensing & Quality Assurance Nebraska Public Power District P.O. Box 499 Columbus, Nebraska 68601 l

l t

wr I

l l

Mr. J..M. Pilant Nebraska Public Power District cc:

'Mr. G. D. Watson, General Counsel Nebraska Public Power District P. O. Box 499 l

Columbus, Nebraska. 68501 Mr. Arthur C. Gehr. Attorney Snell & Wilmer 3100 Valley Center Phoenix, Arizona 85073 i

. Cooper Nuclear Station ATTN: Mr. L. Lessor Station Superintendent P. O. Box 98 Brownville, Nebraska 68321 Auburn Public Library 118 - 15th Street Auburn, Nebraska 68305 i

Mr. Dennis Dubois i

USNRC

)

Resident Inspector l

P.O. Box 218 l

Brownville, NE 68321 l

Jahr. T. Collins Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 l

l l

l 1

l l

l l

l 1

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