ML20246M570
| ML20246M570 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/31/1989 |
| From: | William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89646, NUDOCS 8909070192 | |
| Download: ML20246M570 (15) | |
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- Log # TXX-89646
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903.8 filELECTRIC h ?...
. WNumm J.CahiR,Jr.,
d' August 31, 1989 r
Executwe & Presulent s
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U. S.T Nuclear Regulatory Commission
-Atto: Document Cotstrol' Desk Washington, D.-C.: 20555 p
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SUBJECTi COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS 50-445 AND 50-446-o
-ADVANCE FSAR SUBMITTAL-LOADINGS AND STRESSES FOR CATEGORY I STRUCTURES v
. g Gentlemen:
This letter provides an advance copy of a change to be included in a future.
FSAR amendment.
This change adds information to Table 3.8-1, as requested in-0130.24 < to describe loading combinations and associated stress levels at key' locations..in Category I' structures.
In order to facilitate NRC Staff review of this change', the attachment is organized.as follows:
, 1.
Draft revised FSAR pages, with. change portions indicated by a bar in l-the margin, as they are to appear in a future. amendment.
g 2.
A detailed. description / justification for the change.
1
'3.
A copy of a related SER section.
4.
A page containing the title of a " bullet" which consolidates and U
categorizes similar individual changes by subject and related SER section.
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8909070192 890831 9
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' August. 31,=1989.
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Page:.'2 of.2 Si. The~ bold / overstrike version of.the revised FSAR pages referenced'
.by'the detailed description / justification'for the changes identified l
above. The bold / overstrike version facilitates review of the k
revision by highlighting each addition of new text in hold type font
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and overstrikir.g with n' slash (/) the portion'of the text that is deleted.
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. Sincerely,
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William J. Cahill,'Jr.
41 ' b By:
'l Roger 4. Walker Manager Nuclear Licensing CBC/dje Attachment U.
.c - Mr. R. D.: Martin, Region IV Resident Inspectors, CPSES (3)
Attachment to TXX-89646:
Pag,e;) of.13
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Attachment to TXX 89646 August 31, 1989 1
Advance FSAR Submittal Concerning Loadingt and Stresses for Category I Structures 11gm Sub.iect Paces 1
Draft Revised FSAR Pages 2 thru 4 2
Detailed Description / Justification for 5
Changes 3
Related SER Sectior 6 thru 9 4
Bullet Title 10 5
Bold /0verstrike Version of Revised FSAR 11 thru 13 Pages
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DETAILED DES @Q80 VION Dage 1
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V' i
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'FSAR Pepe (as amended)
Group Description L
N Table 3.8-1 2
See Sheet No(s):1 and 2 l
Provides summary of loading combinations and stresses
)
at key locations in the Category I Structures.
Correction:
Updates Table 3.8-1 to provide a summary of loading condition considered, the related stresses computed and their corresponding allowable stresses at key locations of each Category I structure in response to 0130.24.
The information provided in this table is subject to 1
change until design reconciliation activities have been q
completed.
1 FSAR Change Request Number: 89-584 L
Related SER Section; 3.8; SSER12 3.8 SER/SSER Impact: No 0
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, Attachment to TXX-89646 P' age 6 of 13 (2) an equivalent static lead method (3) the siepiffied dosip method The appiteent has indicated the analysis method used for each piping systas and has provided technical justification for use of the equivalent static lead and afsplified design methods. Both of these methods are based on static seismic analysis. The applied seismic leads correspond to accelerations aquel to at least the zero period acceleration of the appropriate floor response spectra.
The the seismic evstaff has revleued the applicant's procedures and concludes that aluation methods and precedures described by the applicant for nuclear stees agply system and nennuclear stees supply systes Seismic Category I piping systems and equipment are acceptable.
3.7.4 Setesic Ic3trementation progres The type, number, location, and utilizetten of strong-estian acceleregraphs to record seismic events and to provide data en the frequency, esplitude, ar.d phase mistianship of the seismic response of the containment structure comply with tagulatory Guide 1.M.
Supporting instrumentation is being installed on Category I structures, systems, and coepenants ~ts provide data for the verifica-tien of the seismic reopenses determined anstytteelly for such Category I
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items.
The installation of the specified seiselc tastroentatise in the reactor con-tainment structure and at other Category I. structures, systems, and components constitutes an acceptable program to recept data en safeste ground setten as well as esta en the frequency and amplitude relattenship of the response of major structures and systems. kpreept readout'of portfaaet date.et the control reos can be soported to yield sufficient informatten to pide the operator en a timely basis 1!sr the purpose eF.euelusting the settoic response in the event of an earthquehs. Data attained from such installed sefssic instr uentation will be, sufficient to detererles that the seissfc analysis assumptions and the eas1 teal endet used fee' tale design of the plast are adegustr and thetcall le stressee<are not emoseded under conditions where continuitst of operetten is 1standed. prowleton of east noismic instrumentation complies with tegulatory Qaide LM.
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Desias eflaissis Epiamary blematerns, 3.8 r
w; 3.8.1 Concrete Wausst-
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The reacter coolant system is enciesed in a steel-1tned, reinforced concrete centsimment structueer.This structure consists of a vertical cylinder and a hemispherical dems,.and is ogported en as essentia11y flat foundation met with a reacter esytty pit projection. The.eestainment structure uns desiped in accordance with Americes Concrete Isetitute (ACI)/ASE Code (ACI-309) and Regulatory Guides 1.30, 1.15, 1.18, 1.19, and 1.88. Verfees ceakinettens of dead leads. Ifve leads, envireestital leads (including those caused by wind, tornadoes, OBE, and $$t), and leads generated by the destp-basis accident (inc; Jing pressure, temperature, and aseeciated pipe rupture effects) were considered. The lead castigations used and presented in the ESAR are asse conservative than these specified in SRp Sectish 3.g.1.
3-17
[
. Attachment to TXX-89646
~
Page 7 of 13 Static anal is of the containeemt shell and bees is fen ded on methods pre-o viessly ied. Libowise, the liner desip for the containment esplays asthods Ier to these prwfously accepted by the staff.
The choice of materials,imilar to the a of anchers, the desip criteria evoluntad for previously liogneed, and the desip methods are s nucleer plants. Nuterials construction methods, and geslity assurance and quality centrol onesures ar,e covered in the FSAR.
In general, they are similar to those used for previously licensed facilities.
8efers the plant begins aperation$ e containment will he sub4ector' is anDur th acceptance test in encordance wtt 1
telde 1.38.
internal pressure will he 1.15 times fament desi p pressure.
The criteria used in the analysis desis,iand construction of the concreta containmentstructuretoaccountforantic leadfags and postulated conditions that say be tapeeed en the derin are in confermance with esteh11shed crite-fa, ester, g its service lifetiesstan specifications acceptable to the staff.
The use of these criteria (as defined by apptisekle eedes standards, seides and specifications); the leads and leedlas casMastions; Ihe design anl analys l
pmcoderes; the structural acceptance criteria; the motorials, gestity centrol progress, and special construction techniques; and tes testing and faservice surveillance requirements ide ressenable assuresee that, in the event of winds torendees, and verteus postwisted accidsets escuHas within, and outside the contain,annt, thy structase will withstand the Mffed design eendittens without isgisiement er structurel futegrfty or softty functions l
Confermance with these criteria constitutes an assep" table basis for satisfying, l
in part, the regoirementa of St 244, 38, and 90.
3.8.2 Concrete and Structurel Steel Islernet Structures The containment internal strestures are constructed primari ef reinfamed concrete and consist of tin flellowlag elementee shield us11-aperstiat fleer; refusites earttyti hees slah seile shields inler-mediate rieere$ resendkle stes and es11s;blar~ crane; sepp and supporta for reacter pressure veneel genersters,reactercoolank pimpo pressurisors, and leap p i 1Esoseencreteandsteelinternal strueluresaredes to real es esehteettees, of deed and live leads, and accident-1 1emis inci jet leads, and seismic leads, The appl 8uesh has vertfled,that ties 1 sIructures meet the desip require-monts steesd la FV Section 3.4.3.
The criterie esed is the desian anelnts, and construction of the containment faternal structures to essount for askicipated leading and postulated conditions that sur he tapeeed ges tem structures dorlog their sorrice lifetime, are in full conformance trttk estabifehed critoria, and with ceJes, standards, and specifications acesytable to *Jee staff.
The use of these criteria (as drffend by ass 11 cable codes, standards, and specifications); the 1eeds and leadfag cesMnettens; the desip and analysis precedures; the structeral acceptance criterie; the esterials, gestity centrol 3-18
. Attachment to TXX-89646
'P" age 8 of 13 programs, and special construction techniques; and the testing and inservice surveillance requirements provide reasonable assurance that, ' n the event of an earthquaka and various postulated accidents occurring within the contain-ment, ths. interior structures will withstand the-specif' ed design conditions without impaiment of structural integrity or the performance of required safety functions.
Confomance with these criteria constitutes an acceptable basis for satisfyi_ng, in part, the requirements of GOC 2 and 4.
3.8.3. Other Seismic Category I Structures The structural systems for all Category I structures except the outdeer setesic Category I tanks consist of reinforced concrete floor slabs, beans, sirders, walls, columns, and raft-type foundation asts.
tanks are circular reinforced concrete structures, with stainless steel,inersThe ou to provida leek tightness.
Fleer systems and walls are designed for vertical and lateral leads. Seismic, tornede, and other lateral leads applied to the total structure are resisted by the diaphrase action of the fleers and sheer walls and'are transmitted to the foundation ents.
Because the celuens have relatively law lateral stiffness, they are not assumed'te participate in resisting these lateral leads.
The tanks are designed to withstand all credible leadings and to maintain their integrity during operation.
These Category I structures were designed to resist various ceabinations of dead leads, live leads, environmental leads including these caused by winds, tornadoes OBE, and $$E of higir energy pipes suc;h as reaction and jet 'spinpent fortes, campartm pressure, and impact effects of selipptag pipes; and lydre $ namic leads caused by seismic effects of the containment f vid.
The ander code used in the design of concrete Catege7 I structures is ACI 31M1,
" Building Code Requirements for Reinforced Concrete.
For steel Category I structures, the AISC " Specification for the Design. Fabrication and Erection of Structural Steel of Sufidings" is used.
The applicant has verified that all of the other Category I structures anot the design requirements stated in S W 3.8.4.
The construction asterials and their fabrication, construction, and installation are in accordance with ACI 318-71, and the AISC " Specification,for Concrete and Steel Structures,"
respectively.
The applicant une requested to submit information en the use of assenry walls in Category I structures, including their location, design and analysis methods, piping, and egelpment supports.
In an earlier reply to IIAC, the applicant stated that sees assenry walls are located within Ca ry I structures but de not support safety components.
During the Structural insering Branch ($EB) audit, heuever, the applicant identif' ed specific walls that any affect safety coepenents.
The applicant identified in same detail the major safety-related assenry utils within the service water intake structure and the auxiliary building, and stated that safety-related assenry blocks are used as access blackouts, as required. The applicant has coeuritted that the major assenry walls will either be designed in confermance with "$ER Interie Criteria for Safety-Aclated Masonry tdall Evaluation," or seismically designed us11s of other meterials will be constructed in their places.
In addition, all absenry 3-19
. Attachment to TXX-89646 P' age 9 07 13 access blockouts will be supported by seismically designed steel supputs to
(
prevent the collapse of the blocks.
The staff agrees with the proposeddesign
\\
considerations. The details of the final designs will be suositted for staff review and acceptance before operation of the plant. liith the understanding the applicant will not change the current commitments, the staff considers this item resolired.
The use of these criteria as defined by applicable codes, standards, and specifications; the loads and loading combinations; the design and analysis procedures the structural acceptance' criteria; the material, quality control, andspecialconstructiontechniques;andthetestingandinservicesurveillance requirements provide reasonable assurance that, in the event of winds, torn 6does, earthquakes, and various postulated accidents occurring within the structures, the structures will withstand the specified design conditions without impeirment of structural inteprity or the performance of required safety functions.
Conformance with tasse criteria co anacceptablebasisforsatisfyIng, des, specifications,andstandardsconstitutes in part, the requirements of GDC 2 and 4.
3.8.4 Foundations Foundations of Category I structures are described in Section 3.8.5 of the FSAR.
The foundation est for the containment and internel structure is essentially a flat met approximately 12 ft thick, with a reactor cavity pit projection. The foundation est is covered with a steel liner that is an integral part of the containment liner systas, which is covered with a 39-in.-thick interior base slab. The foundations for other safssic Category.I structures e
are generally flat slabs that very in thickness from approxiestely 3 to 6 ft depending on the requirement for sheer and bending assent.
Reinforcingsteel (
is provided in two mutually perpendicular directions, at both the topend bottom faces.
Shear reinforcement is provided where required by the provisions of ACI 318 71, the principal code used in the design of these concrets foundations.
These concrete foundations are designed to resist various loads and )end combinations stated for each pertinent structure in Sections 3.8.1, 3.8.3, and 3.8.4 of the FSAR.
In addition, the applicant has considered in the design of thefoundationstheeffectsofoverturningInSRp3.8.5. sliding and floatation, and has adopted the miniaun safety factors stated The design and analysis procedures used for Category I foundations are the same as those approved on previously licensed facilities and in 1,
areinaccordancewithproceduresdelineatedintheACI318-hc
. The materials of construction their fabrication, construction, and installation areinaccordancewithACI318-71.
The criteria used in the analysis, design, and construction of all Catagery I foundations to account for anticipated oedings and postulated conditions that may be imposed upon each foundation during its service lifettee are in confor-mance with established criteria, codes, standards, and specifications acceptable to the staff.
The use of these criteria as defined by applicable codes, standards, and spuffications; the loads and loading con 61 nations the design and analysis procedures; the structural acceptance criteria; the; materials, quality con-trol, and special construction techniques; and the testing and inservice 3-20
n:-
- . ;A,ttachm
- nt to,TXX-89646
.Page 10 of 13 l
3.8 Desian of Cateaory I,$tructures 3.8.3
- 0ther Seisgie Catenery I Structures ESGB
- 10. The FSAR has added information to Table 3.8-1, as requested in i
0130.24, to describe loading combinations and associated stress levels at key locations in Category I structures. The information in the table also applies to the Concrete Containment and the Concrete and Steel Internal Structures.
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