s-s (~(>

REGULATORY INFORMATIQN DISTRIBUTIQN SYSTEM < RIDS)DISTRIBUTION FQR INCOMING MATERIAL

REC: STOLZ J FNRC

ORG: CRANE P APACIFIC GAS 5 ELEC

DOCDATE: 05/ii/78DATE RCVD: 05/is/78

DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVEDSUBJECT: LTR 1 ENCL 40FORWARDING SUPPLEMENTAL INFO TO APPLICANT"S LTR DTD 02/14/78'ONSISTING INFOON SUBJECT FACILITY"S STEAM GENERATOR ASYMMETRIC PRESSURE) IN REGARDS TOEFFFCTS QF. POStULATED BREAK IN THE REACTOR COOLANT LOOP PIPING AS DISCUSSEDIN 04/12/78 MEETING BETWEEN

PLANT NAME: DIABLO CANYON — UNIT iDIABLO CANYON — UNIT 2

NOTES:J HANCHETT Wli CY ALL MATERIALF HEBDQN W/i CY ALL SAFETY MATERIAL

PSAR/FSAR AMDTS AND RELATED CORESPONDENCE(DISTRIBUTION CODE B00i)

REVIEWER INITIAL: XJMDISTRIBUTER INIT1AL:~

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ++++>>>~>>>>>>+>+>

FOR ACTION:

INTERNAL:

EXTERNAL:

ASST DIP~A LL044LTR ONLYPR e~hb4$ 0 +W/ENCL

REG FILE++W/ENIh E~ CL

P. COLLINS+4W/ENCLHELTEMES4+W/ENCLMIPC++LTR ONLYBOSNAK+4W/ENCLPAWLICKI+4W/2 ENCLNOVAK44W/ENCLCHECK+4W/ENCLBENARQYA~~~~W/ENCLIPPQLITO>>W/ENCLGAMMILL~~W/4 ENCLBUNCH++W/ENCLKREGER++W/ENCL

LPDRiSSAN LUIS OBISPO'A+>W/ENCL

TIC++W/ENCLNS IC++W/ENCLACRS CAT A+4W/i6 ENCL

BR CHIEF STOLZ+4LTR ONLYLIC ASST HYLTON++LTR ONLY

NRC PDR+4W/ENCLOELD~%LTR ONLYHOUSTON++M/ENCLCASE4<LTR ONLYKNIGHT++LTR ONLY8 IHWEIL44W/ENCLROSS++LTR ONLYRQSZTOCZ Y+4W/ENCLTEDESCO++LTR ONLYLAINAS4+WfENCLF. ROSA++@/ENCLVOLLMER44LTR ONLYJ. COLLINS++A/ENCLKIRKWQOD++W/ENCL

DISTRIBUTION: LTR 56 ENCL 46SIZE: iP+13P

THE END

CONTROL NBR: 78i380026

4

'I

,~ !

II

II

E'A.CIFXC GA.S A.ND ELECTRIC COMPA NY77 BEALE STREET, 31ST FLOOR ~ SAN FRANCISCO, CALIFORNIA 94106 ~ (415) 781 ~ 4211

~JOQN C ~ MORRISSKYVICE PRESIDENTAND OENERAL CDIJNSEL

MA I COLM H. Ic LJ R 8 U 8 PIAECDCIATC CENTRAL COO NOEL

CHARLCS T VAN OCVSCNPHILIP A. CRAN C, IJR,HCNRY J ~ LCPLANTCRICHARO A, CLARKC

~JOHN S OISSONARTHUR L, HILLMAN,%I R,

ROSCRT OHLSACHCHARLCS W. THISSCLL

AEEIETAATMIIECALESVAHL

May ll, 1978JOSNUA SA1 LEYRO ~ EAT I.. SD1DONLEIOH O. DAS ~ IDVSEANAAD J, DEllASANTAWllllANH, COWAADSJOSE ~ 'H O CNOLCAT JAJONH H FAVCPATAIOK 0 OOLOENPETEA W HAN~ CHENJUA» H JATOF, RONkla LAUSHEINEAHE1EK C LISSOHJANET D lODCDDNROStAT S, HOLEHNANRICNA10 H, HOC ~ROOTS J.PtHA ~ROSEAT R, Rl~ KETTSNIALEYA SAHOEA~ ONJACK W SNUCK~ NIALEYA WOO

J, PtTEA OAUHOAATHta~ TKVKN P, SUCKSPANELA CHAFStlltOAIAH S, DEHTDHOAAV l, CHDIHASDONALD CAIOK~ OHDAVID D, EHLOCATAHNETTC OAEKNROSEAT L HAAAI~KKCHIT R, KUSITETHEODOAC L, LIHOOEAO, JA,RICHk10 F, LOCKCHAS AY W LOUO, J1RIOHAAO L HEISSDOUSLAO A, OOLCSSYJ. Hlaaktl, REIDEHSASHIVOA C, CARSONSUE ANH LEVIN SCNIZFDAVIDJ, WILllANEONSAUCE R WOATNINOTON

OILOEAZ L HAAAICII CDHAAOJ, MCDAHNEVOLEHNWC~ T JA, DANIEL C OI ~ SONDAH Oa*V~ ON lU~ SOCK JO ~ E ~ 'H I~ KCLLYJACK F FALLIN JA HOHAAOV OOLU ~

~ EHIOA COUNSEL

Mr. John F. Stolz, ChiefLight Water Reactors Branch No. 1Division of Project ManagementU. S., Nuclear Regulatory CommissionWashington, D. C. 20555

Re: Docket No. 50-275-OLDocket No. 50-323-OLDiablo Canyon Units 1

Dear Mr. Stolz:

Ct)HI>1EJJ

EAJ LCfJ

~C/l~TTI

Cand 2

EO C)CD

EFJZJ I

EO EJT

NE Q7

C7

Attached are 40 copies of additional information onthe subject of steam generator asymmetric pressure. This sup-plements the information provided the Staff in our letter datedFebruary 14, 1978 regarding the effects of a postulated steamline break, postulated reactor coolant loop break,. and postu-lated pipe break in the pressurizer compartment.

The additional information is in regard to the ef-fects of the postulated break in the reactor coolant looppiping as discussed in the April 12, 1978 meeting between NRCand Westinghouse. This should complete our response to allNRC requests on the subject of asymmetric pressurization.

Five copies of this submittal have been sent directlyto Mr. Dennis Allison.Kindly acknowledge receipt of the above material on

the enclosed copy of this letter and return it to me in theenclosed addressed envelope.

V y truly yours,

AttachmentCC w/attachment: Service List,

7+$ 380026 g>DI

D P„TIJ'

E

h

U

f

F

iL eDiablo Canyon Steam Generator

~ Asymmetric Pressurization

Evaluations have been performed on the effects of asymmetric steam generatorpressurization resul.ting from postulated breaks in the primary loop piping.Double ended flow areas have been conservatively assumed in this calculation.Two evaluations have been performed: (1) TMD analyses were performed to estimatethe magnitude of the loads, and (2),the steam generator supports have

been'valuatedto determine the asymmetric load carrying. capability. These will beaddressed separately.

Steam Generator Pressure Differentials

A TMD analysis was performed with an 18 node containment model in order to evaluatethe pressure differentials across the steam generator for an RCS loop break. The18 node model and associated input reflect the information currently presentedCn the Diablo Canyon FSAR (Section 6.2.12). In order to pursue the effect of thecompressibility factor, which is not include'd in the current FSAR results, addi-tional analyses were performed using the bounding assumption of A»n/Amax = 0.0.The effect of compressibility on steam generator pressure differentials wasinsignificant. For the worst case of hot leg break in loop compartment volume P3,including compressibility effects, the maximum pressure differential across thesteam generator is 6.04 psi. This compares to the same case without compressibilitywhich yielded a maximum pressure differential of 6.00 psi. This difference isinsignificant. The cold leg case for a break in loop compartment volume k'3(worst case) was less limit'ing, yielding a maximum steam generator pressure differ-ential of 4.48 psi, including the compressible effects.

The TMD flow path network is diagrammatically shown in Figure A. The associatedvolume and flow path descriptive input is described in Tables A and B. Table Ctabulates the mass and energy release rates for a hot leg double-ended break.Table D tabulates the maximum pressure differentials across the steam generator.The pressure differential transient for the worst case of a hot leg break in volume83 is shown in Figure B. The TMD volumes are illustrated in Figures C thru G.

Steam Generator Su orts

The steam generator supports were evaluated to determine their ability to withstandasymmetric loads. In order to completely envelope the problem and to demonstratethe margin available, extremely conservative aP's were chosen. Two loadings wereapplied which would separately maximize the effects on the lower and upper steamgenerator support.

En the evaluation of the lower support, 20 psi differential pressure was placedacross the steam generator between the bottom of'the generator and the elevation

of the upper support. No differential pressure was assumed above the upper

support as this sP would only decrease the load in the lower support. A dynamic

load factor of 2.0 was assumed with this differential pressure and the load was

combined with the maximum seismic load, the maximum pipe break thrust loads from

a primary system break, and normal operating loads. The asymmetric pressure was

combined with these loads absolutely independent of the time of peak occurrence.The steam generator lower support was shown to be below the stress allowables forthese applied loads. The upper support was also acceptable. A 20 psi differentialpressure across the, bottom of. the steam generator (from the bottom to top resultingfn a vertical load),.gas also sho~n to be acceptable with a dynamic load factor of2.0.

In order to evaluate the loads in the upper support, a 10 psi differentialpressure was applied across the entire length of the steam generator even includingthe portion protruding into the open containment. This load with a dynamic loadfactor of 2.0 was combined with the maximum seismic and maximum pine break thrust .

loads from a primary loop pipe break independent of the time of occurrence of thepeak loads. The steam generator upper support loads for this case were shown tobe acceptable. The resulting loads in the lower support for this assumed pressuriza-tion case were also acceptable.

In summary, two cases were analyzed to determine the ability of the steam generatorsupports to withstand asymetric loads; (1) a 20 psi differential pressure across thelower portion of the steam generator and (2) a 10 psi differential pressure acrossthe entire steam generator. Each load with a load factor'of 2.0 was combined withseismic and pipe break thrust loads. The resulting loads were compared to theallowables for the steam generator upper and lower support and were shown to beacceptable. This is an extremely conservative evaulation of the steam generatorsupports considering th'at the peak differential pressure resulting from the 'QG)

compartment analyses was-6.04 psi across the lower portion of the steam-generator.The'symmetric 'loads on the steam'enerator are acceptable.

~ ~

~ ~

~ ~

I

~ ~ ~

~ 0

TABL<8 -:: ..'.

ClNi TALENT ERESSUHE DIFFERENTIALELEMENTS FOR LOOP COMEARPKNT AND PRESSURIZER BfCLOSURE ANALYSIS MODEL

~ ~

Elament Volume (Ft

2 860 x 10

"... 2o550 x 10

';.. '+660 x 10

- '...-:2.660 x 10

. 2.550 x 10

2.860 x 10

'''o270 x 10

~ I

Descri. tion

'oop Compartment

Loop Compartment

Loop Compartment

Loop Compartment

Loop'Compartment

= Loop Compartment'

'ome

~ ~~ ~

~4

.. 3+525 x 10

'..: .4.015 x 10

'., ":.7,251. x 10

.". 1.415 x 10

X.732 x 10,I','- ~ .;2o098 x 10

;$ .706 x 10

1 650 x 10

2e497 x 10

." 1o337 x 10

1

. 2042 x10~,5

Compartments

8-12 Below

E1evation 140 andI

above elevation

117 'outside the crane wa13.~'

,Compar tments

X3-18 Below

„'ELevation 117

outside the

crane wa11

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".," LOOP COEPART.'1ENT ANALYSISHASS AND ENERGY RELEASE RATES

DOUBLE EHDED SEVERANCE OF A REACTOR COOLANT HOT LFG

~ QQ(Seconds)

~ g ~

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5.0070E-02'. " So7580E-02

6 5080E-02io5120E-02So2570E-029o2510E-02lo0001E-01

''lo1759E-01le2751E-011 6002E-Ol'", lo7507E-Ol

~ lo7755E-01lo9512E-01

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,'. BLESS RELEASE RATE'

Qb/Sec)

So4704E+05r

7e3494 E+04-..7.2355E«4

7 0343E+04....:": '.8460E«4'6e7699E+04

;." 8,8473E«4'9e3921E+04,9 7912K+04': '.":: >.0044E+o5

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~ ENERGY RELEASE RATE(SXV/Sec)

1 3834E+O8.' 0804E«7

": -.: '4e0173E+07 - .

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TABLE D

NRIMUM PRESSURE 'IFFERENTIAL ACROSS STEAM GENERATOR

BREAKTypE LOCATION

MAXIMUM PRESSUREDIFFERENTIAL PS I

, BETWEENCOMPARTMENTS COMPRESSIBILITY

OEHL

DEHL

OEHL

DEHL

OEHL

DEHL

DEHL

DECL

1

2

3

4

5

'63'

(worstcase)

3(worstcase)

5.50'9 .0185

5.26 9 .0144

6.04 9 .0184

5.98 9 .0184

5.26 8 .0144

5.45 9 .0185

6.00 9 .0184

4.46 9 .0215

sec.

sec.

sec.

sec.

sec.

sec.

sec.

sec.

4.48 9 .0215 sec.

1-2

2-1

3~2

5-6

6-5

3-23~2

3~2

yes

yes

yes

yes

yes

yes

AO

no

'I

yes

0

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