ML20040F646

Forwards Requests for Addl Info for Application Review. Info Required Re Reactor Vessel Matl Surveillance Program, Reactor Internal Structures & Seismic Input Criteria for Structures,Sys & Components

ML20040F646
Person / Time
Site:	05000000, Limerick
Issue date:	07/20/1970
From:	Case E US ATOMIC ENERGY COMMISSION (AEC)
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
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References
FOIA-81-385 NUDOCS 8202100014
Download: ML20040F646 (13)

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JUL 2 01970 gj w.

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L Peter A. Morris, Director

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LIMERICE GENERATING STATION UNITS 1 AND 2 - DOCKET NOS. 50-352/353 n

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Adequate responses to the enclosed requests for additional information

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are required before we complete our review of the subject application.

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These requests; prepared by Division of Reactor Standards concern f

material concerning:

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(a) Reactor vessel material curve 111=nce program, leak detection, t(

missile protection, and ins' rvice inspection, as submitted in

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Section 4, 5, 7, and 12 of ae application.

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(b)

Reactor internal structures, reactor coolant pressure boundary, I'

and Clnss I equipment as submitted in Sections 1, 3, 4, 6, 14, f

and Appendices A and C of the application, i.

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a (c) Scismic input criteria for structures, systems, and components, r-and dynamic input criteria for reactor internals, as submitted in Section 2 and Appendices A and B.

(The enclosed list of thia 7

category supersedes the information requests forwarrded to DEL ;

C on July 1,1970.)

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j pnginal signed by E. G. Case Edson G. Case, Director y

Division of Reactor Standards E

69

Enclosure:

a Requests for Additional Information for Limerick 1 and 2 cc w/coc1:

Distribution:

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R. Eoyd, DEL D. Lange, DRS y

R. DeYoung, DRL J. Knight, DRS d p.

D. Skovholt, DRL F. Schauer, DRS f

R. Maccary, DRS A. Cluckmann, DRS h

A. Drowrick, DRS C. Arndt, DRS D. Knuth, DRL I;. Davison, DRS

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G. Lear, DRL jf M. Fairtile, DRS k

LJ Porse, DRS orrxtgg.Wichmany-DRS-- 3RS SgB.gl RS:SE

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V J.' Knight, DRS. Fairti fg A,,,,,, romerick itMa cary,, _,, E5 Case' SURNAME >

..Enight M. ev'e 7-/[--70 7-- Q,-70 7-1 9 -70 DATE> i

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LIMERICK GENERATING STATION UNITS NOS. 1 AND 2

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• hr6 DOCKET NOS. 50-352/353 y.

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Reactor Vessel Material Surveillance Program

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If dependence ~ is placed on residual elements (as specified in ASTM f,.

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.E-185-70 Section '3.1.3 3-lChemical Composition) in plates, heat-f>

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af fected weld zones,' and. velds (including control of copper and '

-4g vana'dium) to limi t the. expected inservice transition.temperatu're Y$ '

shif t,- specify the resulta.of the chemical tests of the vessel p.

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r.aterials in the beltline core region, including the residual ele-M' l

nont content in veight percent to the nearest 0.01%.

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Discuss plans to retain suf ficient " archive" material taken f rom y

^C excess beltline region material of the reactor vessel for the 4h purpose of preparing Charpy V-notch test specimens (for at leasti two material surveillance baskets) in the event that (a) additional

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b irradiation monitoring of vessel material are needed and (b) addi-4$

tional material specimens are required to monitor thermal annealing

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treatments if required to recover fractere toughness in the later years of vessel service.

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Lenk Detection l.

Discuss plans for improving the reactor coolant pressure boundary leak detection system inside of containment, including sensitivity and response time in detecting leaks and supplemental provisions m

for a redundant and more sensitive system employing techniques j

1:1 for detecting leaks other than monitoring Icvels in drywell sumps'.

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Describe' plans to provide leak detection systems 'for vital fluid-dl P sc-

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carrying systems 'beyond the. limits of the' reactor coolant. pressure h

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x boundary, such as. the HPCI system and core spray, system.

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Missile Protection -

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Amplify the material given in Section 5.2.6.6, of; the PSAR with; 3

x respect to a design criterion for '. interior #nissfle protection.1 j

'I5clude considerations of orientation of missile sources,"se'parat' on '

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. of vital redundant components,%se of missile. shields, protection.

2u of the containment liner, protection of the reactor coolant pressure 3_5 L-1 boundary, and protection of other vital systems inside the contain-if N.

ment.

Discuss proposed missile penetration analyses and formulas j.

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$r which vill be used in missile shielding design.

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In. regard to turbine missiles in the unlikely event of a turbine' d

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disc breakup, discuss the protection proposed for the primary

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~ control' room, and fuel pool. Describe the design provisions to maintain the plant in a condition of safe shutdown d,t D

l af ter a turbine disc breakup.

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Inservice Inspection f

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Describe plans for monitoring the rate of corrosion on the inside j

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of the nonclad closure head of the reactor vessel in lieu of the k'*

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exa=ination of patches of cladding required by the ASWE Section II l

Code.

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t LIMERICK CENERATING STATIO :' UNITS NOS.1 AND 2 t,.

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Reactor Coolant Pressure Bounda k '. '

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g, j Identify the editions of.the applicable codes s,the code ' addenda,

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and the code cases which irill be applied to pressure vessels,. piping, o'

g valves, and pumps which are part of the reactor coolant pressure W

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Provide additional information with respect to the potential for the 3

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(during fabrication f

development of sensitized stainless steel parts N

crection, and asserbly in the field) which are intended for pressure j

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containing components of the reactor coolant pressurc boundary or

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for load-bearing members vital to the structural integrity of. the reactor vessel and core.{.In aldition,, identify (a) any stainless j

47 steel *.ype 304 or 316 components of the reactor coolant pressure eW boundary for which the. addition of nitrogen has been allowed to enhance 9

-S the strength of the material, (b) the cooldown method specified for j

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austenitic vrought materials elevated to the solution heat treatment

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.i sensitization during velding operations and (c) veld procedures 7

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components and piping in order to minimize sensitization at the veld i

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If the process of electroslag velding will be'used in the Yabri-h,9 Q.

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d' cation of components within the reactor coolant pressure. boundary,

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describe ;the process specifications, variables, and the-quality

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. control procedures appiled to) achieve de material properties in 4 -

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s s-the base metal, heat' affected' zone, and welds.

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If any compon.ent within the reactor coolant boundary will be designed 4.

_p and/or fabricated in a foreij;n country, identify the manufacturer l,

y and describe his qualification and experience in the manufacture.of' k.e g.,

.. e nuclear power plant components, including any experiences in furnish-p

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int co ponents for nuclear power plants in the U.S.

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Reactor Internals fp.

Specify the. stress, deformation,- and strain. limits which will be.

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included in the design. criteria for reactor vessel internals which p

are not covered by' applicable codes. Describe the loading conditions 4x to which these limits will apply.

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Identify the reactor from which vibration test data vill be appli-

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cable to evaluate the adequacy of the Limerick core support structure -.

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s to withstand vibrations, and describe the vibration confirmatory k

testing program which will be applied to the Limerick design to denonstrate comparable ~ performance.

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Othar Safety Related Systems and Components '"

With respeet 'to seismic : ground motion and-dif ferential' relative'

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settlement,' describe the design criteria which will be employed..,

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containment structure and for the situatlo'ns where this piping'

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enters the v'arious structures..

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The seismic design of a nuclear power plant represents one of, -.

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the more complex pkoblems involving design. interfaces between design 4,

y organizations. To provide us with information to assess whether the 3y r'f seisnic designs bases are correctly translated into the required

.yl epecifications, drawings, procedures, and instructions so that the j

n necessary structures, systems, and components can withstand seisnic loads combinedsith the other4propriate concurrent 1oads,' furnish.

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the folloding information:

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Describe the design organizations that are involved in the seismic h

N design of all structures, systems, and cecponents of the plant R*

that are related to safety.

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Describe the responsibilities of the involved design organizations II]

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in connection with the seismic design and the extent to which.

these responsibilities have been promulgated to the organizations in writing. Identify' the design organization that has been assigned overall responsibility for the adequacy of the seismic e

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design.

.eThis information request 1ncludes que'stions submitted by DRS Seismic Design

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consultant, N. M. Newmark and.v. J. - Hall (June 18; 1970).

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.f' 94 Describe 'the. doc =*nted procedures that. have, been or vill -be *

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' nformation and -changes thereto and the coordinati6n of.' the ? '. ~

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Describe -the manner by which. you assure that the design. pro ' ~

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cedures described in c. above have been or are being followed.

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Describe the design control measures that have been or vill be instituted to ve.rify or check the adequacy of the seismic

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design and by whom they will be performed. Describe the design Y,,

procedures. that have been'or will.be yromulgsted to provide,for -

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these measures.

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Describe the requirements.that-are or,will be included in the 7f n

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that this equipment is adequately designed to withstand and can

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function under the' seismic design conditions.'

-Describe the

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to permit the purchaser to verify that these requirements are s atis fied..

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g; ADDITIONAL INFORMATION REOUEST h[.

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S tructures, Sys'tems, and Co:nponents W

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The proposed TlD seismic design spectra produce a peak amplification gf:.

factor of approximately 2.2 for 2:: '

111storic seismic records H

damping.

-n have resulted in amplificat-lon factors in the range of 2'.5 to 4.5.

Ib Provide a more' appropriate seismic design -basis by considering either jk fi.s of the following approaches:

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Seismic. design spectra for the site which include a more M

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f'K appropriate a:splification factor and the effects on the pre-l_

m dominant periods in defining acceptable seismic design spectra Til:;

51 of distance between the seismic disturbances and the isite, or

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The selection of appropriate damping factors'to be used with

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Q the TID spectra taking into consideration the relation of 4

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these factors to the associated constructicn code allowable y

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I design stress limits which will be used in designing structures'

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systems, and components for the Design Basis Earthquake (DBE).

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Provide the criteria which will be used to deternine the time his-

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tory (ies) associated with the seismic design spectra of the site, l

and specify the tirne histories utilized and the enveloping technique g

enployed.

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List all Category I (specified as Clssa I in PSAR) stru' tures, M

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systems, and components and the ' associated method of seismic analysis.

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(modal analysis response jspectira,* nodal analysis. time-history.

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..-y-j equi. valent, static load..etc.) or empirical (tests) analysia which.

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willbe.employedin'thedesignof:the,listeditems,'includin(appl 1.*~

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cable atress or deformation criteria. - Provide-a brief -description f'

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of all methodsthat' are used for seismic analysis..' :,.

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The classification of all piping having f requencies greater than 20 hz y

under seismic ex6f tation, as appropriate for design as ri;;id systens,

'ie may not provide sufficient conservatism in some cases. Provide 1

the basis for the selection of 20 hz value by demonstrating that the 6

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- earthquakes specified 'for the sf te and building. response character-

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--2, istics either filter or preclude higher freq'uencies.-

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• 5 The use of constant vertical load factors in lieu of a combined vertical

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and horizontal unitiMs dyn==4 c analysis may not be sufficiently

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U conservative. Provide the basis for determining the combined vertical y

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.e and horizontal response. loads for structures, systems, and 'ecaponents.

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Equipment and floor response spectra for various locations within y

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the building structures are.not directly obtainable from the modal

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1 response spectra culti-mass seismic systen method of analysis. Provide!

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the basis for and the conservatism in the use of this method, either

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by demonstrating equivalency to a multi-mass time history method of 9

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These additional information requests have been submitted by DRS seismic design consultants., N. M. Newmark and W. J. Hall (June 18..1970).

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by submitting other theoretical or experimental justification.

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• Provide the basis for consideration of. the differential movement.

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Provide the criteria to.be used to, compute shears, moments, stresses;

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deflections and/or accelerations for each seismic-excited mode as.

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well-as for the combined total response,1 including the criteria for-

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the coabining closely.-spaced anodal frequencies.

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The proposed static seismic design an'alysis for Class I seismic 8.

f structures mainly or entirely below site grade may not always be 1

suf ficiently conservative. Justify the use of this method by i

demonstrating equivalency to a multi-mass dynamic rethod of design analysis'. -

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f spectrum, curve in the seismic design of piping may not always be p

I sufficiently conservative. Provide justification.that -the tase of l

this peak of the spectrum curve includes the contribution of all

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'l significant piping dynamic modes of response under seismic '

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excitation.

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Reactor Vessel Internals

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With respect to the reactor vessel internals a static design analysis 1.

is proposed which may not necessarily be sufficiently conservative..

Justify the use of this method by demonstrating equivalency to a multi-mass dynamic method of design analyse's or ;other experimental

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data whieb considers Jthe following individual dynamic responsest.

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(a) Seise.ic vertical and horizontal loadings of the Design Basis fl

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conditions.

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LDERICK GENERATING STATIO!!' UNITS 1 AND 24

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3 ADDITIONAL CONSULTANTS', OUESTIONS (STRUCIURAL'l E, u'....

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g 18(7) If there aie Class I systems or components' located within; Class.II 4

structures, indicate the manner by which protection is provided l

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the Class I featuras to-ensure that they~ can ' function, properly *:. ~._.... _ ' -

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even in the event of fmilure - of the Chas, II struct. ur.e.s..<.

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i 19(10) Expand the discussion in Section C2 of Appendix C, of the Stress 3'

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limits that will be employed for steel and concrete structures f

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and the basis for the selection of these stress levels.in the

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light of the margin of safety that will be inherent in the design 7

by their use. Show whether.the limiting atress levels.that.are,....

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_,z planned to be used for steel elements and for concrete elements 7

s under the DBE are such.as to lead to essentially equivalent margins 4

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of safety with regard to' behavior.

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