Text

WPPSS Nuclear Project No. 2. Response to Questions Sacrificial Shield Wall Design
	ML18191A286
Person / Time
Site:	Columbia
Issue date:	06/26/1975
From:	Strand N; Washington Public Power Supply System
To:	Anthony Giambusso; Office of Nuclear Reactor Regulation
References
	G02-75-181
	Download: ML18191A286 (61)
	v • d • e

Washington Public Power Supply System A JOINT OPERATING AGENCY P. 0, BOX 968 3000 GEO. WASHINGTON WAY RICHLAND, WASHINGTON 99952 PHONE (508) 946.968l June 26, 1975 G02-7 5-181 8

9

+

O Docket No.

50-397 pEcBUEO Mr. A. Giambusso, Director,.".

Division of Reactor Licensin

'3.HcUp~'>>g,",~""',

Office of Nuclear Reactor Re ul'ion<<l~~~<<

Washington, D.C.

20555 je rg

Subject:

WPPSS NUCLEAR PROJECT 0>>

RESPONSE

TO tlUESTIONS SACRIFICIAL SHIELD WALL DESIGN xI@4+ W +4g

References:

1)

Letter, W.R. Butler to J.J.

Stein, Transmitting Request for Additional Information, dated 5/15/75 (GI2-75-75).

2)

Letter, J.J.

Stein to A. Giambusso, Transmitting

Response

to guestions, Sacrificial Shield Wall Design, dated 2/11/75 (G02-75-37)

Dear Mr. Giambusso:

The attachment provides information requested in Reference l.

This response is intended to resolve the remaining NRC concerns relative to the sacrificial shield wall base design and thereby release the "Hold" which has been placed on the top of the reactor pedestal as a consequence of this problem.

The sub-mittal consists primarily of the design basis pressure loads using the RELAP-3 computer code which has been used to analyze the sacrificial shield wall base.

Also included in the submittal is information concerning the structural analysis of the shield wall base which has confirmed that the design complies with applicable structural criteria documents.

The analyses of the shield wall above the base are continuing at this time.

The RELAP-3 computer program is being used to provide pressure-time histories for these analyses.

As indicated previously in Reference 2, analyses of the shield wall base design have been completed first in order that this design work will have the least adverse effect on the construction schedule.

Since the pedestal and the sacrificial shield wall are the critical path items in determining reactor vessel placement and are the key determinants in setting our construction

schedule, we request an expedited confirmation of our results at the ear liest possible date.

Mr. A. Giambusso Page 2

June 26, 1975 G02-75-181 The information attached is presented, in a manner which we believe will facilitate comparison with your own computer results and ther eby expedite your review.

Please contact us if a meeting or any additional information will expedite your review.

Forty (40) copies of the attachment are being submitted for your review.

Very truly yours, N. 0.

STRAND, Assistant Director Generation and Technology NOS:GLG:ho Attachment

STATE OF WASHINGTON COUNTY OF BENTON ss WPPSS Nuclear Project No.

2

Response

to questions Sacrifical Shield Wall Design N. 0.

STRAND, Being first duly. sworn, deposes and says:

That he is the Assistant Director, Generation and Technology, of the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that he is authorized to submit the foregoing on behalf of said applicant; that he has read the foregoing and knows the contents thereof; and believes the same to be true to the best of his knowledge.

DATED

, 1975

\\

N. 0.

STRAND On this day personally appeared before me, N. 0. Strand to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes therein mentioned.

GIVEN under my hand and seal this P4&ay of

, 1975.

Notary Public in and fear t e State of Washington ~~~

Residing at

'> "lt qp lg r

~

QQG ~ ~,

)(

N I

Washington Public Power Supply System A JOINT OPERATING AGENCY P. Q. BOX 966 3000 GEO. WASHINGTON WAY RICHLAND, WASHINOTON 98$ 82 PHONE I 509) 946.966I June 26, 1975 G02-75-181 Docket No. 50-397 Mr. A. Giambusso, Director Division of Reactor Licensing Office of Nuclear Reactor Regulation Washington, D.C.

20555

Subject:

WPPSS NUCL'EAR PROJECT NO.

2

RESPONSE

TO QUESTIONS SACRIFICIAL SHIELD WALL DESIGN

References:

1)

Letter, W.R. Butler to J.J.

Stein, Transmitting Request

'or Additional Information, dated 5/15/75 (GI2-75-75).

2)

Letter, J.J.

Stein to A. Giambusso, Transmitting

Response

to guestions, Sacrificial Shield Wall Design, dated 2/ll/75 (G02-75-37)

Dear Mr. Giambusso:

The attachment provides information requested in Reference 1.

This response is intended to resolve the remaining NRC concerns relative to the sacrificial shield wall base design and thereby release the "Hold" which has been placed on,the top of the reactor pedestal as a consequence of this problem.

The sub-mittal consists primarily of the design basis pressure loads using the RELAP-3 computer code which has been used to analyze the sacrificial shield wall base.

Also included in the submittal is information concerning the structural analysis of the shield wall base which has confirmed that the design complies with applicable structural criteria documents.

The analyses of the shield wall above the base are continuing at this time.

The RELAP-3 computer program is being used to provide pressure-time histories for these analyses.

As indicated previously in Reference. 2, analyses of the shield wall base design have been completed first in order'that this design work will have the least adverse effect on the construction schedule.

Since the pedestal and the sacrificial shield wall are the critical path items in determining reactor vessel placement and are the key determinants in setting our construction

schedule, we request an expedited confirmation of our results at the earliest possible date.

I

Mr. A. Giambusso Page 2

June 26, 1975 G02-75-181 The information attached is presented in a manner which we believe will facilitate comparison with your own computer results a'nd thereby expedite your review.

Please contact us if a meeting or any additional information will expedite your review.

Forty (40) copies of the attachment are being submitted for your review.

Very truly yours, NOS:GLG:ho Attachment N. 0.

STRAND, Assistant Director Generation and Technology

II

STATE OF WASHINGTON COUNTY OF BENTON ss WPPSS Nuclear Project No.

2

Response

to guestions Sacrifical Shield Wall Design N.

O.

STRAND, Being first duly. sworn, deposes and says:

That he is the Assistant Director, Generation and Technology, of the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that he is authorized to submit the foregoing on behalf of said applicant; that he has read the foregoing and knows the contents thereof; and believes the same to be true to the best of his knowledge.

DATED

, 1975 N. 0.

STRAND On this day personally appeared before me, N. 0. Strand to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes ther ein mentioned.-

GIVEN under my hand and seal this Q4&ay of

, 1975.

Notary Public in and fear t e State of Washington ~~~

Residing at

N

RESPONSE

TO NRC COMMENTS REPORT NO. WPPSS-74-2-R2-Ag SACRIFICIAL SHIELD WALL DESIGN SUPPLEMENTAL INFORMATION Back round Report WPPSS-74-2-R2-A presented results of pressure response analyses and structural design basis information applicable to the shield wall base design.

The pressure response analyses were completed using the Burns and Roe computer program PEAK.

Results of analyses using 34, 50 and 60-node representations of the annulus were presented.

Blowdown mass and energy release rates from the primary system were based on a complete circumferential break of the 24-inch recirculation suction line and the GE analytical model presented in NEDO-10320.

The blow-down thus calculated was increased by 20% to account for the water inventory in the recirculation line.

Only about.

12%

of the total blowdown flow entered the annulus due to flow limiting doors built into the shield wall around the recircu-lation lines.

Using the approach outlined above, the pressure time history within each node and the total shear force and moment at the shield wall base as a function of time were calculated.

The results of the analyses indicated that the effect of increased nodalization on the shear force and moment becomes negligible after 50 nodes.

Using the input from the 60-node model, NRC performed similar pressure response analyses for the annulus using the RELAP-3 computer program.

The results of the NRC analyses were higher than those calculated by the PEAK computer program by about 10%

30% in each node.

In commenting on these findings, NRC noted that these differences could be attributable to flow inertial effects which are included in RELAP-3 'but are not considered in the PEAK code.

In summary, NRC concluded that in view of the results from the RELAP computer program, sufficient conservatism had not been demonstrated to support the shield wall base design.

NRC also provided peak differential pressure values from the RELAP computer program including a factor of 1.4 to account for uncertainties in the fluid dynamic phenomena.

In addition, NRC noted that" since the flow limiting doors are relied upon to substantially limit the amount of blowdown flow which enters the annulus, the structural capability of these doors to withstand a differential pressure of 1000 psi should be verified.

g I le

WNP-2 Discussion Upon receiving the NRC comments, it was concluded that addi-tional analyses should be completed using the RELAP-3 computer program.

These analyses were performed and confirmed the NRC results.

Structural analyses were completed using these RELAP-3 results, including a factor of 1.4 to account for uncertainties.

The resulting loads transmitted to the structure at the base of the shield wall were unacceptably,high.

E Consequently, a change in the flow limiting door design has been investigated.

It is concluded-that with certain changes in the door design the percentage of total blowdown which enters the annulus can, be reduced from about 12% to about 6%.

The major changes in the door design are an increase in the nozzle sleeve diameter and tightening of tolerances on the weir plate clearance dimensions.'he flow split is thereby changed from a ratio of'7.5:1 to 16.6:l.

In, addition, this

, revised design has been checked to ensure the capability to withstand a suddenly applied differential pressure of 1000 psi.

With this revised door 'design an additional computer analysis using the RELAP-3 computer program has been completed.

.The results are presented in the pressure time. histories for each node which are attached.

The pressure time histories have been prepared after applying a 1.4 uncertainty factor to the RELAP-3 results.

A structural analysis of the shield wall base design has been completed based on these results.

It is concluded th'at the design is acceptable and in accordance with Document, B, Structural En ineerin Branch Directorate Effects of High-Energy Pipe Breaks on Category I Structures Outside the Containment (June 1973),

and Document A, Structural Design Crxterza for Category I Structures Other Than Contain-ment (June 1974).

Conclusions a.

The pressure time histories given in the attached graphs provide a sufficiently

'conservative design basis for.establishing loads due to annulus pressure as a result of the postulated recirculation line break.

These graphs account for the deficiencies noted in previously submitted information (See letter W.R. Butler to J.J.

Stein trans-mitting request for additional information dated May 15, 1975, GI2-75-75).

WNP-2 b.

Additional investigation and analyses have been performed to allow completion of the construction of the reactor pedestal.

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f00 I DIFFiAChjTIAL 'I I I I I J f l I I I I I ~ ~ ~ -I I J l I i ~ l i SHIELD WALL DIFFERENTIAL PRESSURE (INCREASED BY 1.4 UNCERTAINTY FACTOR) 16 ~ 6 TO 1 FLQN SPLIT RATIO NODE 17 PRESSURE pFtS jO1 j I s. I ~ ,'f ] ~ ~ I ~I i ~ s f t J r j I t t, g ~ I I ~ ~ I ~ ~ ~ ~ I ~ J j ~ ~ ~ ~ I - j ~ ~ ~ I ~ ~ I I I ~ T II ~ I I I ~ I~ ~ I t I j j. I ~ I r ~ ~ I a -II: i I I I ~ ~ I g J I ~ ~- I W=- ~ XO ~ IO l ~ 0 0 I I l I t I I I l ~ ~ t I J I I I ~ I I ~It I - ~ - c-I =I ~ r i t ~ II j - ~.- < I !..ol...:...a. I i I ~ ~ j TIVE t.s3 O.l MASjfIKGTOKPUBLIC POljCR SUPPLY SYSTEjf SHIELD WALL DIFFERENTIAL KUCLEAR PIIMKCT KO. 2 FRESSVRE - NODE 17 FIGjjjjc tT
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l00 DIPFERZYITIRI-PRKSSQRE C PS}OH ~ I 1 1 } e -r e I I e -t ! --t ~ ~ \\ I. I t II I t r~ 1 e ~ ~ ~ I I 'r I.. i l r t ~ J j I 1 I I 'I 1 e I ~ 1 SHZELD WALL'IFFERENTIAL PRESSURE }INCREASED EY 1 4 UNCERTAINTY FACTOR) ,'6.6 TO 1 FLOW SPLIT RATIO . NODE 19 ~ e"! I - ~ I $0 ~ ~ 40 I '30 Z0 ~ e 1"I ~ ~ ~ ~ I I ~ ~ I I ~ 1 ~ ~ I i I l ~. r I t e L-1 I I l! l 1 j ~ I 1 -'t e ~ ~. 1 I I l ~ I l r ~ e -! e ~- ~ ~ ~ I - ~ = I t ~ i Ir \\ f I I ~ 'r e e' ~ .0+ T}ME }.Sl .os O,l OZ MASjjijjGTONPU}jLIC POMER SUPPLY SYSTEII jjUCLEAR PROJECT jjO. 2 SHIELD WALI DIFFERENTIAL PRESSURE - NODE 19 FIGURE 19
IOO DIP P C N EN Y'i'. PRKSf llRC C I'S I@3 ~ f f m ~ .~ ~ r ~ g; ~ I II i m ~ ~ Im ~ m ~ ~ ~ = 4.i-i ~ f I I I -= ~-+ I ll 1 I ll w ~ m i i ~r m I f m mi SHIELD WALL DIPPERENTIAL PRESSURE (INCREASED BY 1.4 UNCERTAINTY FACTOR) 16 6 TO 1 FIAXif SPLIT RATIO NODE 20 I m m I ir ~ f Ifl r m I m 1 f m ~ ~ tb IO O 0 ..OI
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QlfPCRINTtAL PRfssME'es Ivl ~ ~ ~ = t - \\ ~ 4 r ~ ~ ~ l 4 ~ r 4 1 I l i j.r-~ i ~ I i 4 li r ~ 4 II ~ ~ i ~ ~ I r i t 'I II l' I l Ii II t II ~- t ~ t ~: ~ ~ -I. ~ 4 4 4 ~ ~ ~ ~ = 1 r = t r ~ ~ ~ SHIELD WALL DIFFERENTIAL PRESSURE (INCREASED BI'r4 UNCERTAINTY FACTOR) 16.6 TO 1 FLOW SPLIT RATIO NODE 21 30 , ~ j. ~
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a. ~ ~ s a a =" -~ ~ a 2! SHIELD WALI DIFFERENTIAL PRESSURE 'INCREASED BY 1.4 UNCERTAINTY FACTOR) 16.6 TO 1 PLOW SPLIT RATIO NODE 24 ~ I' a" t a a a DIFFERENTIAL PRESSURE C PSID3 ~ ~ I I a s a ~- a = ~ j II - ~ ~ ~ a ~ \\ ~' ~ 2 = f t a r a i 2 a ~ .a I a a 2 --it ~ ~ I' j l a =2.- i >>[ s a a ~ 2-L 2 T 2 i t 2 a ~ a 2 t = a a ~ l I ~ ~ ,i + a a -2 'I ~ I ~ ~ i s t' i i -2 - ~- ~ a. ~ ~. a a ~ a ~ l 2. ~ i i i i a 2 a ~..2 ~ l l
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I00 D!I'HER'EN'YlhI~ PRESSQRC C FSIOl I 1 T I e = I- = I- -- --I-- ~ = ! = i" I I 1 ll I i ~ .w g I 1 I } I= ~ I II, g I I I I I I I \\ g ~ I I I = ~ ~ ~ ~ ~ ~ SHIELD WALL DIFFERENTIAL PRESSURE (INCREASED BY 1.4 UNCERTAINTY FACTOR) 16.6 TO 1 FLOW SPLIT RATIO NODE 26 ~ =- I,- I I I ~4 ~ I t -~ = o ~ 20 I ~ I I ~ I I I II I' I' I I - ~ 0 0 I.. .OZ TIlvl6'. t. Sl .03 O.I 0.2 MASHINGTON PUBLIC POMER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 SHIELD WALL DIFFER&iTIAL PRESSURE - NODE 26 PISUP. 26
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~ I I I ~ ~ ~ ~ t ~ I SHIELD WALL DIFFERENTIAL PRESSURE (INCREASED BY lt4 UNCERTAIh Y FACTOR) 16 6 TO 1 FL(Ã SPLIT RATIO NODE 28 DIPFEAENtlhL PRCSSURE C PSIOl ~ ~ I I ~ ~ ~ I t I I ~ l ~ I ~ v 40 30 t =! t t I i ~ ~ I ~ -I I ~ tI t I' I I t I I I I XO ~ ~ !D 1,, lJ I t v lv II I ~ 0 ~Dl !,....Dz 'TIAAe C,S3 .03 O.I 0.3 'MASHINGTON PUSLIC PNIER SUPPLY SYSTEH NUCLEAR PROJECT NO. 2 SHIELD WALL DIFFERENTIAL PRESSURE - NODE 28 FiGURE 23
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~ + ~ ~ s== I I l i SHIELD WALL DIFFERENTIAL PRESSURE (INCREASED BY 1.4 UNCERTAIhiY FACTOR) 16 ' TO 1 FLCW SPLIT RATIO NODE 29 I I DlfF[REIITIAI. FREOSII,RP C PSIO'3 50 It I I L, L ~ ~ l ~. .i I l =- ~ ~ I l I l ~ i ~ 20 ~ ~ i- ~ O .01 TIME CQ .03 al MASHIXGTN PUBLIC POWER SUPPLY SYSTEH XUCLEAR PROJECT XO. 2 SHIEFD WALL DIFFEREhiIAL PRESSURE - NODE 29}}

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