ML19242A625

Forwards Request for Addl Info,Including Questions 231.4-231.20,re Reactor Fuel.Forwards Question 371.10 Re Hydrology,Which Was Discussed During 790523 Site Visit

ML19242A625
Person / Time
Site:	Waterford
Issue date:	06/11/1979
From:	Baer R Office of Nuclear Reactor Regulation
To:	Aswell D LOUISIANA POWER & LIGHT CO.
References
NUDOCS 7908030250
Download: ML19242A625 (12)

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gw UNITED STATES y 7,s,.y i NUCLEAR REGULATORY COMMISSION

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A, N 1 : sg Docket No. 50-382 Mr. D. L. Aswell Vice President, Pcwer Production Louisiana Power and Lign: Ccmpany 142 Delaronde Street New Orleans, Louisiana 70174

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATICN Enclosed is a request for additional information that includes Questions 231.4 through 231.20 ccncerning the reactor fuel.

Please advise us of the date you expect to provide respcnses to these questicns.

Also, during the May 23, 1979 site visit by our staff, an adcitianal question on hydrology was discussed informally with your staff and consultants. We have since developed a formal question which is included in the Enclosure as Question 371.10.

You should include your respcnse to that question with those to the other hydrology questions that were sent to you witn my letter of April 26, 1979.

Si nce rely,

Ok j,&DM Rcbert L. Baer, Chief Lignt Water Reactors Brancn 5c. 2 Divisicn of Project Manage en:

Encl;s ures :

1 Accitional Hycrci:gy Cuesticn 2.

First Round Guestions For Waterford 3 Ccs n/ enclosures:

See next ;a;e il 908059% o

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Mr. D. L. Aswell s --

JUN 1 1 579 Vice President, Power Procuction Lcuisiana Power 3 Lignt Ccmpany 142 Delaronce Street New Orleans, Louisiana 70174 l'

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W. Malcolm Stevenson, Esq.

Monroe 3 Lemann 1424 Whitney Building New Orleans, Louisiana 70130 Mr. E. Bl ake Shaw, Pittman, Potts and Troworidge 1800 M Street, N. W.

Washington, D. C.

20036 Mr. C. B. Lester Production Engineer Lcuisiana Power 3 Light Company 142 Delarende Street New Orleans, Louisiana 70 174 Lyman L. Jones, Jr., Esq.

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Gillespie & Jones

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910 Security Homestead Building

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4900 Veterans Memorial Boulevard Metairie, Louisiana 70002 Luk e Fontana, Esq.

Gillespie & Jones 824 Esplanade Avenue New Orleans, Louisiana 70116 Stephen M. Irving, Esq.

One American Place, Suite 1601 Baton Rcuge, Louisiana 7082-

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JUN 1 1 1975 ENCLOSURE 1 ADDITIONAL HYDROLOGr QUESTION s

371.10 See also Ques tion 371.04.

For the NPIS the highest flood level (2.4.3.7) would result from a levee failure when the river stage is 30 feet, MSL. This river condition could occur with a ficcd larger than the Levee Project Cesign Flood (also referred to as Hypo flood 58A) but smaller than the Probable Maximum Ficod.

It could.also occur as a result of wave action concurrent with the Probable Maximum Hurricane coincident with Hypo flood 52A. Accordingly, provide your analyses and evaluations of One effects on the NPIS of the nearly instantaneous failure of the levee with a river stage of 30 feet, MSL.

Include in your response the water level conditions assumed to exist on the plant site at the time of the levee failure, your bases for selecticn of the water levels and substantiation that they are conservative.

Also provice details of the topography and structures that will be along the patnway of the flood wave.

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.u. s 231.0 Reactor Fuels Section, Core ?er# r acce Brancn 231.4 The WSES-3 FSAR states tha: tne pre ic:ed ECL fuel (4.2.1.2.1) red pressures are less tnan :ne ?ri.rary cociant pressure. This design consiceraticn shculd :e stated as an a.x i's-i.

'. "s e l ..a.e-i n, m c s-i a.

r'

' i. i.. i. n... c.

ia

...s.

231.5 Section 4.2.1.2.2.1 (d, e, and f) and section a.2.3.2.7(0)

(' a. ?. I..'. ?. I )

discas2 *. a.

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s *..- =. n..', ". l *. '. -..a '. a.

2. r a...,.'., a..."

s.

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and uniform tensile strain of unieradia ed and irracia ed (4.2.3.2.7)

Zircalcy-4 The reference (CESSAR ?SA.R) fr:m..nicn these r-"ee r. i. a. s.= ra. * = k =.q

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• a.

r. - =...v

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correia:icns as a function of service tercerature and fast neutron fluence.

Please provide sucn :;rrela-icns.

t i n u-a.

...a "se s-#,

i r. a d i..= *..= d.

.i r. a '<

.v - r... a... ', s. a ~.=.v

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2, os.

2.

su.

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• 4. - e. s a.e. e e.c.

• a.a.

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.s e s.

" s a.d.

a ". ~d.-'...2.

. w... c.

'.- * '. ". i.$ '. 2 d..' r. c '.." 3..:

2 ".o.

2 a.n a e

• c./ g =. 4../ o.

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...ar Cen.4 a e c.

a. e c..r. e..am e.

.es. e. n e 4. ~ =. 4.m e. ;.

• m s.

r.e*,

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w.

.r

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....., ; e 7. i.... 't,.

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i t

• e. a. i., =,J p,a..

4..r e.~ w. s e.

=,.,,.3 r J, ;., c. e. y. a 4

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...2,-. a-2.

d u C. 4. ' '...v. A 'S

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231.7 The WSES-3 FSAR states tha: the varta:icn cf JO mel:1ng (4.2.1.2.4.1) coint and thermal conductivity with curnu: is discussed in "section 4.4."

We believe na: "section 4.4" is a printing error. Please confirm and a. mend -he :S?R as neces s a ry.

231.8 We note tha: :ne equation given for :ne specific heat (4.2.1.2.4.4) of U0, at temperatures greater than or equal :c 222C*:

contains several printing errors. Please conf rm and amend the FSAR as necessary.

231.9 The staff has stated (D. ~ Acss letter :: A. E.

(1.2.1.2.5)

Scherer, "Fissicn Gas Release fecm Fuei 3: dign Surnu:"

January 13, 1973) tnat the effects of enhanced fission gas release should te consicered in the safety analysis of fuel design limits.

State new :nese effects, uni:n l c..

.,0. 3 s. s. r 5. a s.

i.,.... a.:- :

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.e,,

.w/a.. a. a. c.

.. a.. a.. =..a a,.

ycur safe y 'nai sis.

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ro. s s-e n e a.

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a. u s. a# *...1 "-*a..a.?.'.'..'

2. 2. s. e.

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.=

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r,,;,,,,'j

.a c s. - : r.=~.'.=.*..a.

3.. e i. s u -v a. d. 'i '. 2.. s =..r.c-..=om

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w fuel surve t i l arce # cm :ne A rx 3: s as 'Ac' ele Cne,

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facility.

Please confirm tnat the specific cetatis of the WSES-3 PIE program will be include; in a fu:ure amencment to the FSAR.

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231.11 The generic topical report CENPD-225, " Fuel ar.c ? ison

( 4. 2. 3.1. ;,'

Red Scwing, is referencec in the WSES-3 FSAR.

We and celieve that the FSAR should be amended to reflect (4.2.3.2.5) the current status of this topical raport as 1: relates to the WSES-3 FSAR a plication.

During the s:af# review of CENPD-225, C-E was re uestec (letter ' rec 0. 3.

'lassallo to A. E. Scherer, June 12,1978) to revise the rescr: because of cmitted considera:icas, wnica affect the predicted rod bcwing magnitudes.

Consequent-ly, C-E stated (letter from A. E. Scherer Oc R. L. Baer August 15,1973) that a succle en t0 CENPD-225 would :e submitted about Oct::er 1973.

We nave no: ;.e: receivec

nis supplement.

The staf', ncwever, has interim cri eria for :ne evaluation Of tre efre: of r c Ocwing :n :ne cecar ure fr c nuclea:e :ci'i 7, and Onese cr":eria :an Ce uSec ?ri2r 50 aOOPOval Of a C-E fererig mCce

' ese

riteria are a lica: t *: :ne eval;a-ion 2e :re 35E3 3 00re Oesign anc are con aine i

ne 3.1'3 re;ce., '0evi;ec Interi7 3afety Evalua 'Cn ieCar* On :30 Ef#ects 0 # ~;ei soc 3cWing r IhermaI Pargin Cal:Ula:i0ns f;r.ign:.-ia *. e e n

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Reactors" (memorandum frca D. F. Ross and D. 3. Ei senru to 3. 3. 'lassallo and K. R. Go11er, Fecruary 15, '9 77).

The applicant should provide (or reference) in section '.2 cf the WSES-3 FSAR tne correla:icn for the curnuc-cecend-ent prediction of rod bcwing magnitudes corres;orcing ic the WSES-3 fuel cesicn.

231.12 The discussion on irradiation-induced growth of Zircaloy (4.2.3.1.4) components references CENPD-198, "Zi rcaloy Growth In-Reactor Dimensional Changes in Zircaloy-4 Fuel Assemblies."

Please provide the ECL axially-averaged fast neutron ex-posures calculated for the WSES-3 highest fluence fuel rod and for the fuel assembly having the maximum predicted discharge burnup.

Confirm that these exposures are within tne data bases used in CENPD-198.

If tne WSES-3 predicted exposures exceed the present C-E growtn strain data case, justify the use of the growth correlations discussed in CENPD-198 for this extended curnua regime.

Also, please cescrite or reference tne conservative manner :na is discussed as ensuring adequace fuel assemcly axial anc iateral growtn margins to interference.

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Jl JLH 1 1 :379 231.13 In accordance with Revision 1 of Section 4.2 of the (4. 2. 3. 2.3 )

Standard Review Plan, please amend the discussion on crud to include:

(a) chemical composi tion of potential crud deposi'ts, (b) assumptions and analytical techniques used to estimate crud buildup, and (c) any relevant data supporting the thickness and porosity of crud deposits anticipated for the WSES-3 core.

231.14 The response to question numoer 231.1 on CEA guide tube (4.2.3.2.4) wear stated that descriptions of design modifications and associated safety analyses of the resolution to this issue would be submitted for staff review before June 1980.

In light of our present review schedule, hcwever, we suggest that Louisiana Power and Light strive to advance the June 1980 senedule as mucn as possible.

Also, we suggest that the FSAR discussions on fretting corrcsion, autcclave vibration tests, and dynamic 'lcw tests be amended to properly reflect C-E 12:cratcry and inpile experience on guice tube near.

231.15 The WSES-3 FSAR states that a Fe::ruary 1973 amencrent (4.2.3.2.3) will address cladding creep collapse. We note nat this amendment has not yet been received.

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14c JUN I ; ;g73 when the amendment is subai tred, please provice tne numerical result of the analysis (i.e., time to collapse for the worst-case fuel rod).

231.16 The following questions relate to the discussion on (4.2.4) testing and inspection to provide assurance that quality control on fuel assemblies is maintained.

(a) What are tne permissible tolerances on assembly spacer grid dimensions?

(b) Are all grids checked and, if so, at what specific points in the fabrication process?

(c)

Is there any minimum acceptable fue' rod channel spacing?

(d) Are any channel spacings measured, and, if so, at what specific points in the fabrication process?

(e) What is the range of acceptable grid leaf spring forces?

(f) Are any grid leaf spring forces measured and, if so, at what specific points in tne f a rication process?

231.17 In accordance witn Section 4.2 of Revisicn 1 to :ne Standard Review plan, please ;rc e ce (cr reference) the Zircaloy/ water reacticn rate correla:icn used for ncn-LCCA apolicaticns.

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JUN 1 1 399 -

231.13 Please provide the follcwing inf:rmaticn that is neeced for staff audit calculations:

(a) fuel r0d cladding ID roughness, 2

(b) fuel pellet dish and chamfer di. Tensions, (c) fuel rod internal void volume, (d) fuel red scrbed gas c:mocst:icn and content, (e) :ermissible tolerance en length of finisned fuel red

cladding, (f) SCL cold snculcer gap (axial spacing betalen fuel rcd tops and lower plate of assemoly up;er end fitting),

and (g) fuel assencly span lengths (axial distances between the centers of each spacer grid).

231.19 In accordance with the guidance given in Revision 1 Oc section 4.2 of the Standard Review 3l aa, the a5E3-3

~5AR shculd te amenced Oc provice (or reference) :Me analysis of the effects of L:CA-incuced 'uel rcc cali:cn-irg anc ructure. The discussion sncula descri:e ;ce ccels for :ne claccing ru;;ure tem:eratu e, ::accimg ru: ure strain, and resJItant asset 0lf #Icw : :c(33e.

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. J'M i 1 T9 231.20 Provide numerical values of the steady-state ccerating conditions used in demonstra:ing compliance w::h ycur fuel design limits.

This information shculd be ;rovided as a function of burnup and shculd include the ccwer history of the limiting rod.

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