ML20147B748

Responds to 780406 Request for Addl Info Re Resumption of Oper of Getr

ML20147B748
Person / Time
Site:	Vallecitos File:GEH Hitachi icon.png
Issue date:	10/06/1978
From:	Darmitzel R GENERAL ELECTRIC CO.
To:	Stello V Office of Nuclear Reactor Regulation
References
NUDOCS 7810110165
Download: ML20147B748 (39)

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7'hc Tn/ vers /ty'O[Oh/ahoma 202 West Boyd, Room 107 Norman, Oklahoma 73019 (405) 325-2621 College of Engineering off.ce of tne Dean October 6, 1978 United States Nuclear Regulatory Commission ATTH: Mr. Steve Ramos Operating Reactors Branch #4 Division of Operating Reactors Washington, D.C. 20555 Docket No: 50-112 Gentlemen:

In accordance with 10-CFR-2.109, we are requesting a 20-year extension /

renewal of our NRC License #R-53 of our AGN-211 Reactor. The current license expires on December 29, 1978.

Supporting documentation wilI be submitted by mid-November.

1 Sincerely, '

// Y fn./(R ,w Wm.R.Uther(ve Dean l

WRU/mb cc: Charles W. Terrell Johnny D. James Martin C. Jischke l

~7 7/$Ii$lGT y 80A0l5 1

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,/ p F Ve co VIRdlNI A ELECTRIC AND POWER COMP ANY, RICHMOND, VIRGINI A 23261 October 4, 1978

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bir. Ira Dinitz Serial No. 551/092278 Indemnity Specialist Ins./BGF:bjo i Antitrust 6 Indemnity Group Docket Nos. 50-338, 50-339 Nuclear Reactor Regulation Agreement No. B-80 United States Nuclear Regulatory ,

l Commission Washington, D. C. 20555 I

Dear hfr. Dinitz:

We are enclosing ten (10) copies each of our Advance Premium Endorsement for the year 1978 and Endorsement Number 15 and 18 to our Nuclear Liability Policy Number NF-240.

This vill comply with your request of September 20, 1978.

We have arranged with our insurance broker to have these sent to you in the future. This will be standard procedure.

l Thank you for calling this to our attention.

Sincerely, l a

E. A. Baum Executive bianager Licensing 8 Quality Assurance

&iclosures

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4-Nuclear Energy Liability insurance -

NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION

1) ADVANCE PREMIUM AND STANDARD PREMIUM ENDORSEMENT

( 2) CHANGES IN SUBSCRIDING COMPANIES AND IN THEIR PROPORTIONATE LIABILITY ENDORSEMENT

, Calendar Year 1978 la. ADVANCE PREMIllM: It is agreed that the Advance Premium due the companies for the period-~ designated above is: $ B6,962.50 a

b. STANDARD PREMIUM AND RESERVE PREM[Uti: In the absence of a change in the Advance Premium indicated above, it is agreed that, subject to the pro-visions of the Industry Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Premium is: $ 41,377.25

2. It is agreed that with respect to bodily injury or property damage caused, during the effective period of this endorsement, by the nuclear energy hazard:

a. The word " companies" v4erever used in the policy means the subscribing companies-listed on the reverse side of this endorsement.

h. The policy shall be binding en such companies only.

c. Each s,uch company shall be liable only for its proportion ys of any obligation assumed or expense incurred under the i policy because of such bodily injury or property damage 4

as designated on the reverse side of this endorsement.

3. It is agreed that the effective period of this endorsement is from the beginning of the ef fective date of this endorsement stated below tc the close of December 31st of the Calendar Year designated in the caption above, or to the time of the termination or cancellation of the policy, 3

if sooner.

(0ver) l Effective Date of January 1,1978 this Endorsement To form a part of Policy No NF-240 12:01 A.M. Standard Time issued to tirninia Electric & Power Company Date of issue December 20. 1977 For the su' scribing co panies

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• By A/ 1 General Manager

. Eridctsement flo 1 '

Countersigned by hdb /

P-\..~,h NE-35(1/1/78) ;m .;m . o, .: .c N u c "*. C.

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Nuc! car Energy Liability insurance NUCLEAR ENERG'/ LIABILITY INSURANCE ASSOCIATION

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ADVAtlCE PREMIUM AtiD STATDARD PREMIUM EllDORSEMENT CALEllDAR YEAR 1978 It is agreed that Items la. and Ib. of Endorsement ilo. 18 are amended to read:

la. ADVANCE PREMIUM: It is agreed that the Advance Premium due the companies for the period designated above is: $ 167,56l .59 ,

lb. STAtlDARD PREMIUM AND RESERVE PREMIUM: In the absence of a change in the Advance Premium indicated above, .

it is ' agreed that, subject to the provisions of the Industry f4 ',) Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Premium is: $125,021.80 .

/ ddi tional. Premium: $1l0,599.09

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$*j'ja,'sl$cn't January 1,1978 To form a part of Policy No 1201 A.M S andard Time issued to Virginia Electric & Power Company Date of issue M4CCh 16 2 l#)78 For the suNcribing co panies ry I

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By____ j k( Gpn?ral M anager l

' Endorsement tio 20 g '

NE-3o- (/ R .. w.t JOHNSON & H10 GINS OF IMC, VIRGINIA

g R C

uclear Ener 'ab y n Insurance Q '

NUCLEAR ENERGY IL h/ IN ANCE ASSOCIATION 7tlL k. \T DE tof!DITI0fl 4 l

Afl0 AMEt, i : t f I . 977 $UBSCRIBIflG COMPAtlIES AtlD Ifl THEIR <<000P.TI0flATE LI ABILITY Et'DORSEf1ErlT I

l It is agreed that:

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1. with respect to bodily injury y property damage caused af ter the offective date of this endorsement by the nuclear energy hazard, the figure $96,875,000 stated in Condition 4 of the i policy is amended to reaa $108,500,000. j l

2. the listing of subscribing co,apanies and their proportionate i liability for calendar year 1977 shown on the reverse side of the Advance Prer.iium at<d Standard Premium Endorsement for i Calendar Year 1977 is replaced by the listing on the reverse '

side of this endorsement. ,

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9 YELLOW COPY AGEilT/ BROKER 1

PIftK COPY SUBMITTIliG COMPAtlY l

dor ment danuary l, l977 To f orm a part of Policy No U-240 t e 12:01 A.M. Standard Time issued to Vir"ig y Elactric r Io'.ier Conanav J a n mry_3._la.1977 For the sujmcribing co pa it Date of issue l

By .. __ _..

General Manager Endorsement No _

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NE-430(1/1/77)  ::;T ,g

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GENERAL $. ELECTRIC ENGINEERING e

GENERAL ELECTRIC COMPANY, P.O. BOX 460, PLEASANTON. CALIFORNIA 94666 DIVISION October 6, 1978 a

4 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Attention: Mr. Victor Stello, Director Division of Operating Reactors

Subject:

RESUMPTION OF OPERATION 0F THE GENERAL ELECTRIC TEST REACTOR (GETR), DOCKET 50-70

Reference:

Request for Additional Information, R. W. Reid (NRC) to i R. W. Darmitzel (GE), April 6,1978

Dear Mr. Stello:

The attached information contains formal responses to the 18 questions contained in the reference. Please note that almost all of the l questions have been answered in submittals made by General Electric j in the period since April 6, 1978.

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^~6F FICI AL Sincerely, VIP.GINIA C. C A"Cf W 7 NOTARY FUOLIC C/UTORNtA b pfer1 e pl c5 A 8, l'.Cl y lwm ~ ~ = -

R. W. Darmitzel, Manager '

Irradiation Processing Operation Nuclear Energy Engineering Division Enc 1:

l Dolo S 3}40  ;

ll GENER AL $ ELECTRIC D

. AFFIRMATION 1

i The General Electric Company hereby submits formal responses to the eighteen questions requested by R. W. Reid (NRC) April 6,1978.

1 To the best of my ' knowledge and belief, the information contained herein is accurate.

. m .g__. 3_ s *" .E By:

n OFFICIAL I "

h R. W. Darm.'tzel , Manager chcDph viRamn/s c.cA W 3RO Irradiation Processing Operation

,.c.pfy;fltj yg NOTARY PUEUC - CAU/CRN:A A'.A.MEDA CCU:JTY dW t'y comm. epires MAR e, IS31 j

, w -%--w m-m Submitted and sworn before me tMs AN day of October,1978, 2+~.w O b6,tuvA , Notary Public in and for the County of 1 Ala,meda, State of California.

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GENER AL$ ELECTRIC Mr. Victor Stello October 6, 1978 cc: E. A. Firestone Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plata.

19f30 N. California Boulevard Walnut Creek, California 94596 G. L. Edgar, Esq.

Morgan, Lewis & Bockius 1800 M Street, N.W.

Washington, D.C. 20036 Friends of the Earth 124 Spear Street San Francisco, California 94105 Attn: W. Andrew Baldwin Congressman Ronald Dellums Representative - 7th District 201 - 13th Street Oakland, California 94604 Attn: Ms. Nancy Snow Dr. Harry Foreman, Member Atomic Safety & Licensing Board Panel Box 3950 Mayo University of Minnesota Minneapolis, Minnesota 55455 Gustave A. Linenberger, Member Atomic Safety & Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Edward Luton, Member

. Atomic Safety & Licensing Board Panel 1 U. S. Nuclear Regulatory Commission l Washington, D.C. 20555 i l

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RESPONSES TO USNRC REQUESTS FOR ADDITIONAL INFORMATION REQUEST N0. 1 Given that a seismic event and the resulting surface displacement at the hypothetical Verona fault could initiate a major seismic event at the Calaveras fault, evaluate first the effects of the surface displace-ment on the containment structure, and then subject the resulting structure to the effects of the maximum vibratory motion. Clearly identify the parameters used in your. analysis, and provide a summary of the stresses at the critical sections of the structure and the foundation. Also provide the available margins against sliding and overturning of the foundation unless it can be shown that the conse-quences are acceptable. Include any preliminary results which are available.

Response to Request No. 1 The effects of surface displacement and vibratory ground motion on the containment structure are discussed in the General Electric Company (GE) 26 July 1978 responses to the United States Nuclear Regulatory Commission (USNRC) request for ' additional information on the Phase 2 report (EDAC 117-217.03).

The parameters used in the analysis of the reactor building and results of the analysis, including forces at critical locations and maximum rotations and sliding displacements, are given in the Phase 2 report.

REQUEST N0. 2 Consider'a variation in the soil spring stiffnesses to account for inaccuracies in the assumptions utilized to derive these springs including changes in depth of embedment under vibratory motion.

Response to Request No. 2 The effects for possible variations in the soil spring stiffnesses due to depth of embedment and other soil parameters are discussed in the Phase 2 report.

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REQUEST N0 d State the peak broadening criteria utilized for the response spectra.

Response to Request No. 3 The criteria used to develop the floor response spectra are discussed in the 26 July 1978 GE responses to the USNRC request for additional information on the Phase 2 report.

REQUEST NO. 4 Verify that the approach utilized for the seismic analysis of the water storage tanks and fuel pool are conservative, especially in their low frequency energy content, considering that fluid sloshing is a low frequency phenomena. Also verify this for the analysis of the reactor building if pool sloshing is significant.

Response to Request No. 4 The results of the analysis of the fuel flooding system reservoirs is given in Engineering Decision Analysis Company, Inc. (EDAC) report EDAC 117-217.08.

This report verifies that the analysis performed is conserv.ative.

The effects of water in the pool on the response of the reactor building are discussed in the 26 July 1978 GE response to the USNRC requests for additional information on the Phase 2 report.

REQUEST NO. 5 Provide quantitative justification to substantiatt the claim that parametric studies of the reactor building considering possible variations of fault parameters are not necessary. For example, look at the consequences of two extreme angles of faulting.

Response to Request No. 5~

The justification for not considering variations of the fault parameters is given in the Phase 2 report.

5 i REQUEST N0. 6 Justify not calculating factors of safety against sliding and especially overturning of the reactor building foundation.

Response to Request No. 6 Results of the nonlinear analyses for tilting and sliding are given in the

. Phase 2 report. It was found that the computed rotations and disp'lacements, based on conservative assumptions for the model, were very small and that the stability of the safety-related concrete in the reactor building would not be affected if the maximum postulated earthquake occurred.

REQUEST NO. 7 The action to be taken in the event of low water level alarm for the reservoirs should include making a detennination of the cause of a low water level in the reservoirs in addition to taking immediate action to refill the reservoirs.

Response to Request No. 7 General Electric agrees with this request and the operating procedures will include a determination of the cause of low water level in the reservoirs.

REQUEST NO. 8 State the frequency at which water samples from the reservoirs will be analyzed and the allowable impurity limits.

Response to Request No. 8 Information on water sample. frequency and impurity limits is provided in the Updated Response to the USNRC Order to Show Cause, submitted to the USNRC on 20 July 1978.

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t REQUEST NO. 9

- . Verify that penetrations through the containment building will retain their integrity under.a seismic event to the extent that they will not impair. the flow of cooling water.

Res'ponse to Request No. 9' The results of'the analyses of the penetrations in the containment shell

, through which'the Fuel Flooding System (FFS) lines enter the reactor building g are discussed in EDAC report EDAC-117-217.03 and in the 26 July 1978 GE responses to the USNRC requests for additional information on the Phase 2 report.  ;

These analyses show the_ penetrations will retain their-integrity.

REQUEST NO. 10

t Will a dropped cask affect the integrity of the fuel storage canal?

If so, what are the effects on any safety related equipment?

' Response to Request No. 10

, The results of the investigation of pctential cask drop impact on the canal fic-ar slab are given in EDAC report EDAC 117 217.04. To protect the fuel storage' tanks from cask impact, a canal impact pad will be installed. This pad is discussed in the submittal to USNRC dated 20 July 1978. I REQUEST N0. 11 f Provide the basis for the coefficient of friction between the fuel storage racks and the canal floor.

I Response to Request-No. 11  :

The basis for the coefficient of friction is discussed in General Electric .

report #DSAR-77-4 entitled "GETR Fuel Storage Tank Sliding Analysis" dated [

June 1978. A copy of this report is attached (Attachment 1). l l

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REQUEST NO.'12-

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i Verifythatthetjmehistoryresponsecomputedforrackslidingand uplift displacements are conservative. Address the possibility of utilizing several time histories to calculate conservative values for o these responses.

Response to' Request No. 12

.The input acceleration time histories at the base of the GETR reactor building canal were supplied by EDAC (see' Attachment 1). Two different time histories f

b- have been selected for the present analysis. Both time histories correspond to a soil shear modulus ~ of 1000 ksf, an area of contact of 75% between the

{ base slab and the supporting soil, and an effective peak ground acceleration of 0.89 However, the first time history has no . modal damping cut-off (i.e. ,

4 uses the most realistic reactor building model' parameters), whereas the second time history was generated with a maximum modal damping of 35 percent. The t maximum floor acceleration for the latter time history is 13% larger than that obtained from the former time history; thus the computed response of the fuel storage system is conservative.

REQUEST NO. 13 Provide the maximum value of K which will be maintained by the fuelstoragerackdesignboth8boreandafterthepostulatedseismic events.

Response to Request No. 13 The maximum value of Keff which will be maintained by the fuel storage rack design is 0.564. .The Technical Specifications for the GETR allow Keff I 0.85.

I. REQUEST N0. 14 Discuss in detail the GETR procedures for performing and reviewing safety analyses for proposed modifications to the facility. Describe 1 how these procedures will assure that objects or equipment to be hung i g on theliner/ wall 1will not effect the leak tight'. integrity of the pools.

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a h Response to Request No. 14 A Standard Operating Procedure exists at the GETR which governs the adminis- ,

i tration.of facility modifications. This procedure requires that a " Change ,

Authorization" be generated anc reviewed for all proposed " changes" to the facility. A " change" is defined as follows:

Change  !

Any addition, alteration, deletion or substitution which adds a new capability; performs a different function; changes the philosophy of operation; modified performance characteristics or introduces safety considerations not previously analyzed.

The Reactor Analyst is responsible for assuring that " Change Authorizations" are completed for all proposed facility changes. Any equipment to be hung

on the liner / wall would require implementation of a " Change Authorization".

The " Change Authorination" is a document which contains a coi.plete description of proposed facility changes, a safety analysis of the proposed change, and review and approval signatures as required by Title 10 of the Code of Federal Regulations, Part 50, Paragraph 59.

The safety analysis contained in the Change Authorization must demonstrate <

that all documented safety criteria and license conditions are satisfied.

Credible off-normal conditions, accidents, malfunctions and personnel errors must be considered. These include such things as the evaluation of the effects of sitie seismic criteria on the design.

The Change Authorization is generated by the responsible engineer, and is reviewed by the following personnel:

- responsible engineer's manager Manager - Plant Engineering & fiaintenance Reactor Analyst j

. Manager - GETR Operations Manager - Nuclear.' Safety

-- External reviewers as requested by the Reactor Analyst

- Vallecitos Technological Safety Council when requested by the Manager - Nuclear Safety i

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Response to Request No. 14 - continued Afterthefabovereviewsarecompleted,theManager,ReactorIrradiations

. reviews and a'pproves the Change Authorization.

REQUEST NO. 15

. Define:themarimum.tornadoexpectedatthesiteanddiscussthecogse-quences of its occurrence. A probability of occurrence of 6 x 10'

. is not sufficiently low to' disregard this event. Discuss the conse-quences of the occurrence of this event.

Response to Request No. 15 The maximum tornado is not an issue contained within the NRC Shcw Cause Order and should therefore not be under current consideration.

REQUEST NO. 16

' For the reactor vessel tiottom head penetrat'.on tubes provide the s following and indicate the probability of their non-mechanistic

failure

a). Peak stresses under normal and seismic loading conditions b) NDT temperatures for materials involved c) Lowest ambient temperature at that point i 4

d) Materials involved e) Describe the. types of welding present and the materials utilized for welding.

f) Fluence level the materials have been subjected to

.g) The NDE that has been performed on the welds. Include a description of the techniques and the results.

Response to Request No. 16 l The reactor vessel bottom head and associated penetration tubes are all made of type 304 stainless steel. The welds are a combination of groove and full

-penetration wel'ds, and were all made in conformance with Section VIII of the ASME code. The final assembly was-successfully hydrotested at 225 psig, which is 1.5 times the' design pressure. The Manufacturing Data Sheet and E

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,Rasponse to Request No. 16 - continued

... Certificate'of Inspection for the pressure vessel, top and bottom heads, and associate'd penetration nozzles is attached (Attachment 2). The peak neutron fluence:(all energies) is approximately 1 x 109 nyt at the bottom

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4 head.; This fluence level is insignificant in terms of known and accepted ,

damage thresholds for 304 stainless steel. Type 304 stainless steel does not

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exhibit brittle fracture characteristics,'and NDT is not a consideration for

- this material in this application. In any case, the. actual ambient temperature the bottom head and associated penetrations would ever be exposed.to ranges from a low of approximately 50 F to a high of 180 F during the normal life of the plant. These temperatures are, of course, very nominal.

The peak stresses in the bottom head (control rod) penetrations during normal and seismic loading conditions are listed in Table 4-6 of EDAC report i

EDAC 117-217.05. The allowable stress valuer for reactor components (including 304 stainless steel) are listed in Table 3-3 of EDAC 117-217.05. The actual i

stresses-(during normal and seismic conditions) are only a small fraction of the allowable stress values.

. I r. conclusion, the bottom head penetrations were designed, fabricated and tested in accordance with ASME Section VIII requirements, the materials involved see a very nominal stress, temperature and radiation environment, and are not subject to brittle fracture. The probability of penetration

, failure during a seismic event is considered to be zero.

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REQUEST NO. 17 ,

t Indicate your intent to qualify the critical valves and valve O; operations by testing unless a . detailed justification is provided and the qualification is performed by analysis.

Response to Request No. 17 The qualification of. the safety-related valves is given in EDAC report EDAC 117-217.09, submitted to the NRC 20 July 1978.

REQUEST NO. 18

-Rather than utilizing the response spectra. located at the highest point on each piping system in the analysis of the corresponding system, the envelope of the response spectra for all anchor points of a piping system should be utilized in its analysis. In addition, relative seismic anchor movements must be considered in the analysis.

Response to Request No. 18 The floor response spectra used in the analyses of the safety-related structures, systems and components envelope the computed response spectra 4

at all anchor points in the reactor building. The basis for not including relative anchor movements in the analyses is discussed in the 26 July 1978 i

responses to the USNRC requests for additional information on the Phase 2 report.

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. i 1 ATTACHMENT 1 GETR FUEL STORAGE TANK SLIDING ANALYSIS O

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GENER L@ ELECTRIC ~ ,

NUCLEAR ENERGY DIVISJCN gy 0 TITLE GETR Fuel Storage Tank Sliding Analysis DYNAMIC LOADS TECHNOLOGY DYNAMIC AND SEISMIC ANALYSIS i

l DSAR-78-4 June, 1978 Prepared by: D

N . Y eh '

Dynamic & Seismpc Analysis Verified by: M<' /sv/ /' 4A-R. W. Wu Dyn i & Seismic Analysis l

Approved by: ~

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[/J. D. Gilman, Mngr.

Dynanic & Seismic Analysis l

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GENERAL @ ELECTRIC **

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NUCLEAR ENERGY OLVISION MEV 0 I. INTRODUCTION This report' describes the methods used and the results of the GETR fuel

. storage tank sliding due to maximum seismic excitation.

1 II.- INPUT EXCITATION The input acceleration time histories at the base of the GETR reactor building canal were supplied by EDAC (References 1 and 2). Two different time histories have been selected for the present analysis. Both time histories correspond to a soil shear modulus of 1000 ksf, an area of contact of 75% between the base slab and the supporting soil, and an effective peak ground acceleration of 0.8g. However, the first time history has no modal damping cut-off; whereas the second time history was generated with a modal damping cutoff of 35 percent. Also, for the second time history, a multi-plication factor of 1.333 has been applied at the time history supplied as instructed in Refarence 2.

III. METHOD OF ANALYSIS A plan view of the fuel storage system is shonen in Fig.1.

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su w. 4 GEN ER AL@ ELECTRIC NUCLEAR ENERGY DIVI &lON MEV 0 The free body diagram of the fuel storage tank is shown in Fig. 2.

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JN Fig. 2 The governing equation for the system subject to the ground excitation can be written as; 4

m0 = -af6g -AN if 0 > 0 (1) mU = -m'Ug +# N if U 4 0 where U is the acceleration of the system relative to the. support base.

Ug is the base acceleration

/1 is the coefficient of f riction N is the normal force m is the total mass (structural mass + hydrodynamic mass)

m'is the total mass with the ef fect of hydrodynamic couplP' accounted for.

The computer program SEISM 01 (Reference 3) was used to calculate the sliding displacement of the fuel storage tank. Four cases have been analyzed:

(1) x-direction, maximum fuel stored, (2) x-directien, minimum fuel stored, ,

(3) Y-directior , maximum fuel stored and (4) Y-direction, minimum fuel .

stored.

The coefficients of friction between the tank and floor used are 0.5 for the analysis with the first time history and 0.349 (Reference 4, 5, 6) for the analysis with the second time history.

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GEN ER Al.@ ELECTRIC 3 REV NUCLEAR ENERGY DWISION O a

4 IV. HYDRODYNAMIC WATER MASS CALCULATIONS i

l The WATER 01 computer program (Reference 3) is used to calculate

the hydrodynamic mass of the storage tank immersed in the GETR canal.

The calculated hydrodynamic masses per unit axial length of the system are:

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{ 1X Body lY Body 2X Body 2Y Body i 11.40021 -0.09741 -12.06862 0.08416 I -0.08741 4.56344 0.12617 -5.26588

-12.06862 0.12616 14.31788 -0.10558 0.08416 -5.26588 -0.10558 7.47361 Unit = lb - sec /in Table 1 l

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where body 1 represents the tank and body 2 represents the canal wall.

The hydrodynamic mass matrix derived in WATER 01 program is valid for infinitely long objects. In the case where the object is of finite length, all the fluid 12 not forced to move around the object. Some fluid transf er takes place along a longitudinal path. As a result, the relative tangential velocity and hence, the hydrodynamic mass, is reduced. To account for this reduction, the following " length correction factor" is used.

Q=1- ' tanh (2) where 7 = mean radius L = Length of Cylinders rn this analysis, r will be a/2 in X-direction and b/2 in y-direction, L is 5'-3" = 63".

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HEN ER AL@II.ECTRIC May 0 su so. 6 NUCLEAR ENERGY OlVISION Y

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/ X A. f '. 'Q In X-Direction 45 63 NL x = I ~ es fanh 45 = I - c. 6 5 2 4 = c,3 g 7g In Y-Direction 39 yLY l 65 lanh 39 = I ~ 0. 5 7 2 ~ 0 4 2 8 '

Reduced hydrodynamic mass in both X and Y directions are calculated as follows- .

X-Direc tion:

M ,,x - K u x M,',x = o 3676 * " 4 "" 4 '9 "d'%"ir te"*r" H,2x = - M,,x - J' C A rea o f hun K = ( 78")( 90"))

= - 4.19 - o. 66 = - 4. 6 5 M Ass /vu, r L ENG TH wHERE P: THE WATER PEMiT Y M2n = - M,zx + .? ( Anea of pool = z2 6 8 sa. ox )

= 4. 8 5 + 2. I 2 3 = 6. 9 73 M^ss/un,7 igge,7g Y -c i rec t ion :

M i,y = X cy x M,', y = o.42 s x 4. 5 6.5 = I. 9 53 HA55/vu;rt. sue,ru M ,2 r = - I.9 5 3 - c. 66 = - 2,61 s MA**/v w r i.gs c,7g M22Y" 2.615 + 2.12 5 = 4.7 3 6 MAS %u,7 g447g

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= =. 7 G'EN ER AL@ ELECTRIC NUCLEAR ENERGY 04 VISION MV o s

' Based on the length effect corrected hydrodynamic masses of the system and the structural mass and entrapped fluid mass of the tank, the total mass used in Equation 1 are shown in the following table.

For the X-direction motion For the Y-direction motion Max. Fuel Min. Fuel Max. Fuel Min. Fuel i Stored Stored Stored Stored M (1b-sec2

/in) 343.421 340.005 202.49 199.074 2 37.87 34.46 K'(1b-sec /in) 37.87 34.46 N (lbs) 26115 25575 26115 25575 i

Table 2 V. RESULTS OF ANALYSIS ,.

The sliding displacement time histories of the fuel storage tank are shown in Figure 3, 4, 5 and 6 for the analysis with the first time history and coefficient of friction of 0.5. Resulty by using the second time history and a coef ficient of f riction of 0.349 are shown in 11gs. 7, 8, 9 and 10.

The maximum sliding displacements are as follows:

X-Direction Y-Direction i

Max. Fuel Min. Fuel Max. Fuel Min. Fuel The first time his tory ,

and coef. of friction = 0.005 in. 0.001 in. 0.006 in. 0.001 in. l u 0.5.  !

l The second time history and coeff of friction = 0.1 in. 0.06 in. 0.16 in. 0.1 in.

l-l 0.349.

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r m m. 8 GEN ER A1.@ El.ECTRIC ggy NUCl.IAR ENERGY DIVISION 0 s

Since the minimum gap between the fuel storage system and the canal wall 4

is 2 in. ,the tank will not impact with the canal wall.

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',W DISPLACEME.NT TIME-HISTG5Y OF GETR -

. FEBRURRY 25. 1978 8 i I i i DIShoEMir.T CF FRICTIC! CONTACTS l X-Di?.ECTI*N (Max. fuel, no modal damping cut off, coefficient of friction = 0.5) ,

2

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O O O .

DISPL.9 CEMENT TI:-:E-HISTORY OF GETR P. ARCH 2tl. 1978

-1200 l l

, 0;SFi_FiCE:ENT CF FRICTIG : CCNTACTS j X-DIRECT i;.N (Mini. fuel, no modal damping cut off, j coefficient of friction - 0.5) i

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_ pp. 4 p, w

~

DISPLACEMENT TIME-HISTORY OF GETR MARCH 211. 1978 i i DISPLRCEFENT CF FRICTIC:1 CONTRCTS l Y-DIRECTI ON (Max fuel, r'io modal damping cut off, l '

I coefficient of friction = 0.5_) -

n .

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DISPLACEMENT TIME-HISTORY GF GETR MRRCH 211. 1978 1200 ' l DISPLRCEFENT OF FRICTICp CCNTE:'TS Y-DIRECT 10N (Mini, fuel, no modal damping cut off, ,

coefficient of friction = 0.5) 800 u,

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DISPLACEMENT TIME-HISTORY OF GETR  :

f1PSIL 26. 1978

~~ ~ ~

DISPLRCEl-aT OF FRICTIC:J CONTRCTS '

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4 1 DISPLACEMENT TIME-HISf0RY OF GETR APRIL 26. 1978

~ OISPLRCE ENT OF FRICTIQU CONTACTS

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coefficient of friction = 0.349) i

(

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DISPLACEMENT TIME-HISTORY OF GETR

~

nar es, 1978 200 -

~

DISPLACEFENT OF FRICTIO!4 CONTACTS Y-DIRECTION (Max. fuel,koffriction='0.349) coefficien modal damping cut off = 35%

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s DISPLflCEMENT TIME-HISTORY OF GETR HRY 03. 1978 f I DISPLRCEFENT OF FRICTIO!1 CONTRCTS Y-DIRECTICN (Min. fuel,d of friction coefficie ='0.349)' modal damping cut off = 35%

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! in uo.17 GENERAL @ ELECTRIC-NUCLEAR ENERGY OlVISJON MEV n

~i

+

REFERENCES

1. EDAC Memo from H. Kamil to Dr. L. K. Liu, " Time Histories of Floor Accelerations at the Bottom of the Canal of the GETR Reactor Building for Usa in the Storage Rack Sliding Analysis", dated 2/22/78, attached.

2. EDAC Memo from E. Kamil to Dr. L. K. Liu, " Time History of Floor s Acceleration at the Bottom of the Canal of the GETR Reactor Building for Use in the Storage Rack Sliding Analysis", dated March 31, 1978, '

attached.

3. Levy, S. & Wilkinson, J P.D., The Component Element Method in Dynamics, McGraw-Hill, Inc. 1976

4. Letter from P. Sun to N. Yeh, dated April 26, 1978, attached.

5. E. Rabinowicz, " Friction Coefficient Values for a High Density Fuel Storage System", Sept. 26, 1977, GE VPF No. V5455, 1-3-78.

6. Letter, from C. C. Herrington (GE) to M. Voth (Northern States Power Company) "HDFSS License Matter" Paragraph 4.3.3.6, letter No. CCH-67, 11/17/77.

1 l

1 3.

\

ss. no. 18  !

RE V. 0 l ENG' NEE *NS oECislON ANALYSTS COMPANY. INC. .

] ) 483 CAL 6oRNIA AVE SUITE 30! PALO ALTO CAllF 94306

[ PMoNE 415 '326 0383 I

22 February 1978 '

l l I I Dr. L. K. Liu, Manager of Dynamic Analysis l Nuclear Engineering Division

) General Electric Com;:any 1850 South 10th Street, Room 505 i

{

San Jose, California 95112 i

Subject:

Time Histories of Floor Accelerations at the Bottom of the -

Canal of the GETR Reactor Building for Use in the Storage Rack Sliding Analyses

EDAC Project No. 117-216

Dear Dr. Liu:

t t

Please find enclosed card decks for the time histories of floor acceler-ations in the horizontal direction at the bottom of the GETR Reactor Building Canal for use in the storage rack sliding analyses. These time histories correspond to an effective peak ground acceleration of 0.8g.

Plots of these tirne histories and the corresponding response spectra 1

(O for a eemnias retio of zero percent ere elso eaciosed. Tae time histories l

were generated for the following cases:

Area of Contact I i

Between the Base l Slab and the

, Soil Shear Modulus Supporting Soil F Case -

(ksf) *

(% of total area) Comments i 1 1,000 75 -

2 3,000 100 -

3 1,000 50 - i

, 4 1,000 75 A modal damping cutoff of 15%

was used Please note that Case 1 has been considered to be the most realistic case in the GETR Reactor Building analyses. It is, therefore, reconr. ended that the time history corresponding to Case 1 above should be used as the main time history for the storage rack sliding analyses.

O lI e

--__a _ _ _ -

_-___T_*..--.-__=__,_________-___.__--_-_____.---_

_. - - - - _ _ - _ - _ - - - - _ . _ _ _ _ _ - _ _ _ _ _ _ . - - _ - 2

sn. no. 19, .

[ ne v. 0 k.

!O Dr. L. K. Liu 22 February 1978 Page Two If.you have any questions regarding these time histories, please contact .

Dr. John. Reed or me.

Very truly yours, t.

fp Nf- ; e Hasan-Kamil "

Manager of Technical Development HK:jkh Enclosures

=

cc: Mr. Doug Hoggatt w/o enclosure Mr. Tom Hall w/o enclosure t

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9 FIGURE 2 RESPONSE SPECTRUM CORRESPONDING TO TIIE TIME HISTORY IN FIGURE 1 g

- FOR'ZERO PERCENT DAMPING ,

SH. NO. 22 -

EBEC .

" " ~

ENG; NEE A:N3 DECIStoN ANALYSIS COMPANY. INC.

480 CALIFoANIA AVE sylTE 301 PALO ALTO CAUF.94306 PHONE 4t5/326 0383 ,

)

31 March 1978 Dr. L. K. Liu l Manager of Dynamic Analysis 1 Nuclear Engineering Division General Electric Company 1850 South 10th Street, Room 505 San Jose, California 95112

Subject:

Time History of Floor Acceleration at the Bottom of the Canal of the GETR Reactor Building for Use in the Storage Rack Sliding Analysis  :

EDAC Project No. 117-216

Dear Dr. Liu:

[ -Please find

• enclosed a deck of cards for a time history of floor acceler-

- ations in the horizontal direction at the bottom of the GETR Reactor A Building Canal for use in the storage rack sliding analyses. As per our  ;

._v telephone _ conversation yesterday, this time history corresponds to a soil shear modulus of 1000 kips per square foot, an area of contact between the base slab and the supporting soil of 75 percent, and a modal damping cutoff of 35 percent. Please also note that the time history was devel-oped for an effective _ peak ground acceleration of 0.69 . A multiplication

~

factor of 1.333 will therefore have to be used if the analyses are to be  !

perfomed for an effective peak, ground acceleration of 0.8g. A plot of '

this time history is also enclosed.

1 If you have any. questions regarding this time history, please contact l Dr. John Reed or me, 1

Sincerely yours, i o 1 e u s_ ,

f#tsan Kainh' tianager of Technical Development msw l l

p- Enclosures  !

cc: Mr. Doug Hoggatt (without enclosure) -

Mr. Tom Hall (without enclosure) p _~ g

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