ML20011A554
| ML20011A554 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, Sterling, 05000484  |
| Issue date: | 07/28/1978 |
| From: | Sihweil I Office of Nuclear Reactor Regulation |
| To: | Parr O Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20011A456 | List:
|
| References | |
| NUDOCS 8110130549 | |
| Download: ML20011A554 (13) | |
Text
- [y flUCLEAR REGULATORY COMM2sslON c
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Docket Nos: STN 50-432/483/484/485/485
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MEMORANDUM FOR:
- 0. D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management FROM:
I. Sihweil, Chief Structural Engineering Branch Division of Systems Safety
SUBJECT:
TECHNICAL ASSISTANCE REQUEST-DESIGN CRITERIA FOR SNUPPS PLANTS CONTAINMENT STRUCTURE (TAC:5007) (SES:1241),
In response to your memo to R. J. Mattson dated July 12,1978, we have reviewed the request submitted by the SNUPPS utilities by letter dated May 3,1978.
The SNUPPS letter requests that we modify our position regarding the maximum reinforcing steel cover tolerance in the SNUPPS con-tainment structure for certain special cases as described in the SNUPPS letter. The areas in question ant adjacent to the two electrical penetration banks which are located on the containment structure between the third and sixth lifts adjacent to' the aux-iliary building.
Our evaluation of the issue of maximum and min-j..
imum tolerances for the reinforcing steel cover on the SNUPPS
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containment structu'.'e was provided in our memorandum to you dated r
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March 6,1978.
With recard to our position on maximum cover we stated that "The staff will consider special cases on this requ-1rement where necessary wall blockouts may require local variations to the maximum depth to face reinforcing."
The area in question is not large and is located in a region where the stresses are due largely to membrane action.
Furthermore, the l
containment is prestressed which provides assurance that if any j
cracking did exist it would be quite localized.
Therefore, we conclude that the proposed exception on maximum cover meets the intent l
of our original position and can be approved for the penetration i
banks on all SNUPPS containments.
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I. Si weil, hi f Structura] Engineering Branch
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Division of Systems Safety ror cc's see j
attached sheet 9110130549 811007 PDR ADOCK 05000483 G
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R. Mattson H. Thornburg D. Vassallo J. Knight D. Jeng
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9 ATTACHMENT 9
SNUPPS 3.8.1.6.2 Reinforcing Steel and Splices
.s 3.8.1.6.2.1 Materials Reinforcing bars for concrete are deformed bars meeting the requirements of the Specification for Deformed and Plain Billet-Steel Bars for Concrete Reinforcement (ASTM A 615),
Grade 60.
For each heat or mill shipment, whichever is a
less, certified copies of the material test reports covering the chemical and mechanical properties of the reinforcing bars are obtained.
Mechanical splices, when used, consist of T-series and B-series Cadweld-type splices.
Tubing used for splice sleeves conforms to the Specification for Seamless carbon
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and Alloy Mechanical Tubing (ASTM A519), Grades 1018 or 1026.
Certified copies of material test reports showing the results of the chemical e.nd mechanical tests of material from each lot of splice sleeves are obtained.
In addition, certification is obtained for each lot showing for each lot that the chemical composition of the powdered metal and the chemical and mechanical preperties of the resulting filler material conform to the manufacturer's standards.
3.8.1.6.2.2 Examination
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During fabrication and construction, reinforcing steel and
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mechanical splices are regularly sampled and tested to ensure quality control.
The examination methods, frequency, and acceptance standards in Regulatory Guide 1.10 for mech-anical splices and Regulatory Guide 1.15 for reinforcing steel are used.
Refer to Appendix 3A for a description of the extent of compliance with these regulatory guides.
3.8.1.6.2.3 Erection Tolerances
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The reinforcing steel is placed in accordance with the tolerances specified in Paragraph 7.3.2 of ACI 318, except as noted below:
I a.
Inplace reinforcing steel cover tolerances shall be within the following limits:
Base slab
-0", +1\\"
Exterior walls
-0",
+1h" Dome
-1", +1" l
Exterior wall tolerances are maintained, except for local areas adjacent to some recesses on the exterior surface where a gradual sweep of the continuous l
reinforcing steel to clear the recesses could i
result in these cover tolerances being exceeded.
I 3.8-15
SNUPPS However, the resulting cover is within the design allowable specified in BC-TOP-5-A, Appendix C, 6$
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cept for the two electrical penetration banks.
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ex-electrical penetration banks, centered at azimuth 222*-30', El. 2035'-3" and azimuth 319'-30', El.
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2035'-3" have the outside face of concrete recessed 8 inches.
The two banks are approximately 15 feet (vertical) by 48 feet (horizontal) and 15 feet by 39 feet,.respectively.
The transition zone where the continuous reinforcing sweeps gradually inward to clear the recess extends as much as 16 feet-8 inches away from the outside edge of the recess.
Although the reinforcing steel in this area is generally within the limits indicated above, there are a few instances where, including placing toler-ances, the cover can be as much as 13-3/4 inches.
b.
Cadwelds and other connectors are not considered as reinforcing steel.
I In no case is the cover reduced by more than one-third c.
of the minimum specified design cover, d.
Minimum splice lengths and minimum embedment lengths are maintained to a tolerance of minus 2 inches.
These minimum lengths may be exceeded without limit, provided that the other, requirements for gE[
cover and clearances are not violated.
05:
The variation in spacing is 2 bar diameters, 1
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except that the minimum clear distance specified in Paragraphs 3.3.2 and 7.4 of ACI 318 is maintained.
The total number of bars in any nominal 10-foot segment is maintained.
f.
For longitudinal location of bends and ends of bars that are mechanically spliced, a tolerance of minus 2 inches at the discontinuous end of the member in which the splice occurs is acceptable.
Conversely, e
the cover for this situation may be increased by 2 inches.
3.8.1.6.3 Prestressing System
' 3.8.1.6.3.1 Materials The prestressing system consists of lotd carrying and non]oad carrying components.
The load carrying components include the prestressing wires which make up the tendons, and anchor-age components composed of bearing plates, anchor heads, and shims.
Nonload carrying components include the tendon sheathing (including trutpet assemblies, couplers, vent and i=ge
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3.8-16 I
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l ATTACHMENT 10
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~20 n..An:c'.L so.: CC-?53A Suticacer tTei No.
Y ?o sum r.CT Mini-- - Cenere:e Ccver JOINT COMit. lita: 30 S/C lb ITEM NO.
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- SCURCC Cl CON! MENT: 3r:.m & 2 cot OLPV CCSIM. ITEM NO.
DATt IN m ATto: 6/22/76 INCCIRY:
ATTACllED C '
ACl ASMI. TECHNICAL CCMMIT EE CM CONCRETE PRESSURE COMPCNENTS NOT ATTAC!fCD C FOR NUCLEAR SERV!CE AES:GNCD SU;;CRCC?: SG :esign PRCPCSCD AC;ON AND l'EASON I.c t er incuirf. Itspense.:
CC 353!. covers are absolute ~4-3~~s and =ay not be further redu:ad by the Designer in his ccnst uccion Specification.
Cnly (-) colerounces are alle.ed.
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VOTING F"SULTS ATTACHMENTS Y;5ll50 TOTAL MCM3;RS.
RC.! ARKS NEG. VCTE I rtESOLUTI:
CCN3 O; RATION DAT~
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'AIIENIION:
Richard E. K g 3
SUM ICT:
Reinforcing S:ca'ASX2 I!!, Divisica 2; Tolerances en C 1
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oncrete Ccver for
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ar Mr. Koppe:
2 Subpc.:cgraph CC-333!. of the Code cen:
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that tole:cnces en pl:.ce ent ofcover to be p cvided for rei
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en =inize reinfcrcing, steel be specified by the concrenc
. Designer in the Ccast: ction Specification namely, plus c: cinus 1/4 inch for 11;h: vill spec In nes:
- cases, e :o those se:
the Designer or ninus 1/2 inch fe heavier ac=b,ers.
strue: ural :.c bars up cc plusfer:h In in:e:p:cting the inten:
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t minin-concecte cove: =ay be reduced as icf :he Code, is it recsona the Constructicn Specifica:ica ar cn; as placing :cle:cnces in
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the Ceccents:y cr. ACI-?l3 appear i
e act e::ceeded ?
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Pc:c,crcphi7.3.2 of pernissible p:cvided th :
the original specified c cuntcoverage is nc;est th2such reduc:iccs e reduced by more tiisn cacacc third Please cdvise if we are incorrect in
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cu: interpreta:1on o:H.
Very'truly ycurs,
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the Code.
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!ir. T. H. Gamen
- g Quality Assurance Manager Brown and Root, Inc.
P. O. Box 3 Houst:n, Texas 77001
Dear 11. Gamon:
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Reference is made to your letter dated June 22, 1975, GE-SQ-XX-0134.
It is the opinion of the ccmmittee that the minimum concrete cover i
requirements Of Subparagraph CC-3534 are absolute minimumt and may not be reduced as a function of placement tolerance.
In rela.icn to the minimum spacing given in CC-3534, only plus tolerances are permitted.
As a practical matter, minimum cover given in the applicable specffications should include a margin for minus placement tolerances so that minimum
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values of CC-2534 are no: violated.
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.s-Cuestion:
Is it the inten:
Steel Cover and !; acing Require =ents, that the Desiof Section II are less than the nini=cm Ccde require =ents listed i ng aragraph cc 4342) that Eeolv:
subparagraph ec 3534.17 It is the intent of Section III, Division 2 that th specified in ec 3534.1 nay not be further reduced by the D e =ini=un tolerances where a ninus toleranca would cause the sini==n toleran esignes :La cases 3534.1 to be further reduced, only plus tolerances =
ce require ents of ay be specified.
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1112 77 13,1112 77 14
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interpre:stion: 11!:-77 13
Subject:
See:ien III, Dinsion 2;CC-3534 i
Date Issued:
C::ober 21,1977 i
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fee:
, NI.77 303 t.' 7G-#f2 t
Question: Dces See:ica III, Di.ision 2 &w :he mi:dmum eene:ete cover to be redu:ed as lcng as l
pts:ing tolersnees in the Constru:::en Specin:stion are not exceeded? Paragrapn 7.3.2 of the Commentary l
on ACI-318 sppears to suggest that such redue: ions are permissible prodded thsi coverage is not reduced by =cre than one third is cripasi spe:ined amount.
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Re;Iy: The minimum cene:ete :over :equirements of CC 3534 ve act to be reduce:i as a fune:ir et f
pls:ement :cle:sn=e. In re!stion to the minim m sps:ing sven in CC 3334, eniy plus :clerances 2:e pc m. -
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ted. As 2 prs::ical matter, minimum cover pven in the applic:ble spe:in:stions shoul3 in:!ude a margin for j
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- nnus pls:e=ent ::lersnees so that minimum values of CC-3534 are not vscisted.
r-ei Interpreis. ion:
III.0-77-14 I
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Sectica III,Dinsica ;C3/CC-4400,Tenden Assemblies h
t Date Issued:
December 9,1977 f
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rue:
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(1) Can a Material 31snufs::urer ef tend:n assemblies perictm bu::en hesding cf wires in the shop aze=bly of tendens in 2::ct-isnee with Se: tion III, Dinsion 2, C3 CC4430.3W;(1)?
(2) Can :he M2:en21 Manuis::u :: of bearing pistes and trun.:ets perform :he seal weld of the
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trumper to the besnag piste in 2:::rdanet with Secuen 111. Dinsion 2. C3/CC4331.l?
i (3) Can acnicsd :st ying :endon du::s. trutnpets, and transition eenes be :ensidered form work in j
8:: : dane with See:!cn !!I, Dinsica 2, C3/CC-5250?
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Replies:
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(!) It is permissible for a M2:ensi Manufs::urer of tenden assemblies to perform butten heading cf wire dunng shop smm:iy of tendens to the requirements of See:ica III. Dinsten 2, C3/CC :432 3(c)(1).
l (2) It is permissible for 2 M:tensi Manufse:urer to pericrm trumpe: :o ber.ng piste ses! weiding prended :re weids 2:e recutre.1 :c estry no Icsd and are sciely for the purpose of maintsuung relative posi-
- ion,2::d :o prevent intrusien cicen :ete ducing subsequent piscing.
(3) Tendon da::s. ::umpets.snd transition :snes may be cor:sidered form work under :he recuire-f t.ents ci See: en !U Oivision :, C3/CC s:50 previde:!:he ms:eris1:eqmrements of C3/CC 2241 are met.
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f UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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BEFORE THE 3.TOMIC SAFETY AND LICENO "3 BOARD In the Matter of UNION ELECTRIC COMPANY Docket Nos. STN 50-483 OL (Callaway Plant, Unit.1)
)
CERTIFICATE _OF SERVICE I hereby certify that copies of NRC STAFF MOTIONS FOR
SUMMARY
DISPOSITION OF JOINT INTERVEN0RS' CONTENTIONS II-A(1), I-A, I-B(2), I-B(1) AND I-D along with LETTER TO KENNETH M. CHACKES, ESQ.
in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Commission's internal mail system, this 7th day of October,1981, and where indicated by double asterisk, by hand delivery the 8th day of October, 1981.
James P. Gleason, Esq., Chairman Administrative Judge Barbara Shull Atomic Safety and Licensing Board Lenore Loeb 513 Gilmoure Drive League of Women Voters of Missouri Silver Spring, MD 20901 2138 Woodson Road St. Louis, M0 63114 Mr. Glenn 0. Brignt*
Administrative Judge Atomic Safety and Licensing Board Marjorie Reilly U.S. Nuclear Regulatory Commission Energy Chairman of the League of Washington, DC 20555 Women Voters of Univ. City, MO 7065 Pershing Avenue Dr. Jerry R. Kline*
University City, M0 63130 Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Gerald Charnoff, Esq.
Washington, DC 20555 Thomas A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge Mr. John G. Reed 1800 M Street, N.W.
Rt. 1 Washington, DC 20036 Kingdom City, MO 65262 Dan I. Bolef Treva J. Hearne President, Board of Directors Assistant General Counsel for the Coalition for the Environment, Missouri Public Service Commission St. Louis Region P.O. Box 360 6267 Delmar Boulevard Jefferson City, MO 65101 University City, MO 63130
Donald Bollinger, Member Rose Levering, Member Missourians for Safe Energy Crawdad Alliance 6267 Delmar Boulevard 7370a Dale Avenue University City, MO 63130 St. Louis, MD 63117 Mr. Fred Luekey Kenneth M. Chackes**
Presiding Judge, Montgomery County Chackes and Hoare Rural Route Attorney for Joint Intervenors Rhineland, MO 65069 314 N. Broadway St. Loais, Missouri 63102 Mayor Howard Steffen Chamois, M0 65024 Professor William H. Miller Mr. Earl Brown Missouri Kansas Section, School District Superintendent American Nuclear Society P.O. Box 9 Department of Nuclear Engineering Kingjom City, MO 65262 1026 Engineering Building University of Missouri Mr. Samuel J. Birk Columbia, MO 65211 R.R. #1, Box 243 Morrison, MO 65061 Mr. Harold Lottman Presiding Judge, Dasconade County Robert G. Wright Rt. 1 Associate Judge, Eastern District Owensville, M0 65066 County Court, Callaway County, Missouri Eric A. Eisen, Esq.
Route #1 Birch, Horton, Bittner and Monroe Fulton, M0 65251 Suite 1100 1140 Connecticut Avenue, N.W.
Atomic Safety and Licensing Washington, DC 20036 Board Panel
- U.S. Nuclear Regulatory Commission Docketing and S'rvice Section*
Washington, DC 20555 Office of the Secretary U.S. Nuclear Regulatory Comission Atomic Safety and Licensing Washington, DC 20555 Appeal Board
- U.S. Nuclear P.egulatory Commission Washington, DC 20555 F,0y P. Lessy g Deputy Assistant Chief Hearing Counsel L
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