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{{Adams
{{Adams
| number = ML12216A010
| number = ML13350A289
| issue date = 10/31/1976
| issue date = 11/30/1975
| title = Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments
| title = Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments.
| author name =  
| author name =  
| author affiliation = NRC/RES, NRC/OSD
| author affiliation = NRC/OSD
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.103, Rev 1
| document report number = RG-1.103
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 4
| page count = 4
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY
{{#Wiki_filter:U.S. NUCLEAR REGULATO                                                            COMMISSION.
COMMISSION
 
REGULATORY
November 1975 REGULkizORY GUIDE
GUIDE OFFICE OF STANDARDS  
  OFFICE OF STANDARDS DEVELOPMENT
DEVELOPMENT
                                                                                            REGULATORY GUIDE 1.103 POST-TENSIONED PRESTRESSING SYSTEMS
REGULATORY  
                                            FOR CONCRETE REACTOR VESSELS AND CONTAINMENTS
GUIDE 1.103 POST-TENSIONED  
PRESTRESSING  
SYSTEMS FOR CONCRETE REACTOR VESSELS AND CONTAINMENTS
Revision 1 October 1976


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion
to provide a rel'erctice io some plants for %,'hich tile sysvetns in Table A have been proposed o, approved. The
1, "Quality Standards and Records," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires that structures, systems, and components important to safety be designed, fabricated, and erected to quality standards commensurate with the importance of the safety func-tions to be performed.
        (;General Design C(riteriun I. "Quality Standards and                                                               ex:amples cited are not intended to *indicote any Records" of Appendix A. "'General Design Criteria for                                                                     testriction or prel'evence in size of the tendot for a given Nuclear I(oiver PlanIs." to 10 C(FR Part 50. *'Licensing                                                                 system. Nor is this -uide intended 'to discourage the if Prodlucion. and Utilization Facilities.'- ,equires. in                                                                developmtent of refinements of curr.ent systems or the part. that structures. systems. and components im-                                                                        development of new prestressing systems or concep)ts.


This guide identifies the post-tensioned prestressing systems that have been reviewed and approved by the NRC staff for use in concrete reactor vessels and containments.
lporlani to safety be designed. fabricated, and erected to (tllality standards commensurate with the importance of                                                                            "hte quatliflcat ions dhat a post-tensioied piestnessitig Ihe saflcy luncliotins to be performed. This guide identi-                                                                s'.stem should meet in order td ibe acceptable to tie ties Ithe post-tensioned pcstressing systems Iltat hiave                                                                  NRC st-a Tare iden~ified in tlicaiegulatowv positioti. Rock been reviewed and ai.rovcd by the NRC staff for use in                                                                     anchorage systems are..not covered by this guide.


It also describes qualifications acceptable to the NRC staff for new post-tensioned prestressing systems.
concrete reactor vessels and containmnents and also describes qualifications acceptable to the NRC slafr for new post-tcnsioned prestressing system
 
====s. Types of Systems ====


==B. DISCUSSION==
==B. DISCUSSION==
A post-tensioned prestressing system is composed of a prestressing tendon combined with a method of stressing and anchoring the tendon to the hardened concrete.
STlhie type tof tendon selected usually diclates the choice of stressing eqluipment and also affects the choice A oims-tensioned prestressing system is composed ofa'                                                              ,of end .atchorages.
 
prestressing tendon combined with a method of sira.sing and anchoring the tendon to thie hatrdened coz.crete.Th.e                                                                          Basically. post-tensioued prestressing systenis can be word "symeste                    is commonly associated                                      ith the. dif-"                separated into Ihree general categories by Ihe types oh fercni proprietary post-tensioned prestrcssing.systenl oil                                                                  terndon in use: wire, strand. and bar systems. lEtnd Ihe market and is understood to include                                                            .the.type of            anchorages for these tendons are based ott either wedge tendon, anchorage device, and stressing equlipment                                                                          or direct-bearing p.inciples: sometimes a combination of associated with a given systemi.-.                                                                                          ihe two is used. A description is presented below ot post-tensioned prestressing systems in ternis or types tit It is not practical ito discussthe details or all of the                                                            tendons and end anchorages.


The word "system" is commonly associated with the differ-ent proprietary post-tensioned prestressing systems on the market and is understood to include the type of tendon, anchorage device, and stressing equipment asso-ciated with a given system.It is not practical to discuss the details of all of the many post-tensioned prestressing systems available in the United States. Moreover, new post-tensioned prestressing systems are being developed, and existing ones are being modified.
many post-tensioned:.irestressilng sysiems available in the United States. Nlore)ver.'"inw pidit-tensioned prestressing                                                                       Wire Systems. Wire systents employ a tumber ot systems are being: devclopod, and existing ones are being                                                                   parallel wires grouped to form a tetndon. Wires modified. F-6r                                      "te nsreas.  the descriptions in this                                  manufactured in the United States conforni to ASTMt guide are Ii*u16 to -systnis listed in Table A. all of                                                                      Specification A-421. "Uncoated Stress.Relieved Wire for which havbeel used or proposed for use.                                                                                    FPrestressed Concrete." This specification provides for wires of two types (BA or WA). depending on w\hetite Some examples of use are presented in order to                                                                        tltey are to be used with buttons or wedge.type identify iiore specifically thie system being discussed and                                                                  anchorages.


For these reasons, the descriptions in this guide are limited to systems listed in Table A, all of which have been used or proposed for use.Some examples of use are presented in order to identify more :specifically, the system being discussed and provide a reference to some plants for which the systems in Table A have been proposed or approved.
USNRC REGULATORY GUIDES                                                                          C,,,nierr-ns should be sent to the Secretarv of the Commiss*,on.          U S Nuclear AreqUlallor    Conui'I*,Ison.  Wasin~l~gtoni.    D C  M56  Alttention Docketing ando Regulatory Galde* ire i*,sued to desc*ibe and otike aviddh*le to Ihe Iyith.                                                  Seulit SeCtion                .A
  methods acceptatle" o thtf NRC ftill tot rmpim enmrtingspecific par                                                the        rf    Se Coninti.,5on I reguajutions. 10 delineatei techniques used by th" tiltl an ttvalu                                            lb. qutirmtesate    issued in Iharfollowing ton brand divisionh Chirq itspi'ct c rutalems, or vustl.fle~d .Atc~dnlel. or to Iriovad. g lsani.nI,, itpli cants ARguldiriao Guidesi at.e not subslitults fot regulations. and Conipli*lhco                                            I Powser Reactors                              6 Products with them inot retjtlleii Miridb dint                    SnIu        Illto- fIoent front lhose set (,,ii itt                  2 flese'rch and Yost Reacit%                    7 Transtproation th: gui*de* wit: he 'uptih*lt*te it th              provide v'y        a t        fit tie ht,,% fandings requisite to               3 hueldsandMa*terl*1,Faciltes                  8a Occuptilonl Heoalth the islsum            Illo  itlt!tte      . ii1  rt tir ticrmnei*ihthe ICunmnmisiOn                                        4 Ern-tioninientland Siting                    9 Antitrust Reirew C(rrrriietlsfl1 trait+Stiajleslilis 1,14111IiiLVitullill11t5 ii ttlhlse ajiantaits                  itlt.    rielt            lateri.rts l        aild PIrItMPiolec*irn        tO Genet a lt ii          , . Jtt11 q        wil"itt1i. l ,l      a iI      t aIaiiiI . t-1lu  ,ict..ill.....l..late ;oin, MGMlls rid,1tIa iiltte,'.t -ew it..I-li.iiiiiii            t..(uial      r              -- ý c ...
                                                                                    l..irvi


The examples cited are not intended to indicate any restric-USNRC REGULATORY
====t.  ian====
GUIDES tion or preference in size of the tendon for a given system. Nor is this guide intended to discourage the development of refinements of current systems or the development of new prestressing systems or concepts.The qualifications that a post-tensioned prestressing system should meet in order to be' acceptable to the NRC staff are identified in the regulatory position.
                                                                                                            .i1rntt...1it.  C(i:;aie of tulAtished guides rtadyble olbtainld lIv written request aidacating the INis iju li1.. ii tem .itm (l artaila ,it Iii      t        1a1111m1la .Ilrer O      , as,i i.'.
                                                                                its                    .,il tie iPa          divisions desired to the UtS Nucltear Regultatuor Commission. W a~shtng lor . 0 C
tImulai ly usef ll iii      t    hli llillii 'niri. l .ti .t....i.. y IV.,..a....  IOt2                                            5, Allen tion D lte . lol. Office of ,SlandaidiDeveltopm ent


Rock anchorage systems are not covered by this guide.Types of Systems The type of tendon selected usually dictates the choice of stressing equipment and also affects the choice oi end anchorages.
The BBRV system, developed in Switzerland by                 The VSL strand system was.developed in Switzerland.


Basically, post-tensioned prestressing systems can be separated into three general categories according to the types of tendon in use: wire, strand, and bar systems.End anchorages for these tendons are based on either wedge or direct-bearing principles;
Birkenmaier. Brandestini. Ros. and Vogt. is a wire          This system employs a wedge anchorage for strands.
sometimes a combina-tion of the two is used. Post-tensioned prestressing systems are described below in terms of types of tendons and end anchorages.


Wire Systems. Wire systems use a number of parallel wires grouped to form a tendon. Wires manufactured in the United States conform to ASTM Specification A-421, "Uncoated Stress-Relieved Wire for Prestressed Concrete."'l This specification provides for wires of two types (BA or WA), depending on whether they are to be used with buttons or wedge anchorages.
system used in both concrete reactor vessels and              Each strand is drawn through the openings of both the containments built in the United States. The main            bearing plate and the anchor head and is held by a feature of this svstenz is the. use of cold.lormed            two-piece split cone wedged tightly against the inner buttonheads for direct bearing at each end of the wire.      surface of the anchor head. As an example. the conttainmnent of the Rancho Seco Nuclear Generating Tie prestressed concrete reactor vcssel (PCRV) of the    Station* in California employs the VSL system with Fort St. Vrain station in Colorado employs the B3BRV          tendons consisting of 55 strands. each tendon developing system with 169-wire tendons developing approximately        2250 kips capacity.


The BBRV system, developed in Switzerland by Birkenmaier, Brandestini, Ros, and Vogt, is a wire system used in both concrete reactor vessels and*Copies of this and other ASTM specifications referenced in this guide may be obtained from the American Society for Testing and Materials, 1916 Race Street, Philadelphia, Pennsylvania
2000 kips capacity each. A number of 2-ontainnienls utilizing the BBRV system with 90, 163. 16). 170. and            The Stressicel S/Il multistrand systemi was developed
19103.Comments should be gent to the Secretary of the Commission.
  186 wires per tendon have been built in the United          in the United States during 1967-1968 by Stressicel Slates. The wire diameter is 1/4 inch (6.35 imm) in all      Corporationi in cooperation with llovwlett Machine cases except fur the 163-wire tendon, which uses 7-mm        Works. The system is characterized by a three-piece
(0.28 inch) wire.                                            slotted wedge cone that grips three strands in its serrated teeth, with a number of wedges in a single anchor plate Strand Systems. Strand systems employ a number of        making up a ittllistrand lendon of the desired size.


U.S. Nuclear Regulatory Guides awe issued to describe and make available to the purlicico section.methods acceptable to the NRC sauff of Implementing specific peas of the Commission's regulations.
"'strainds" that are bundled into a tendon. A strand is made tip tof a number of factory-twisted wires.                  As at, example. the conlainment of the Three Mile Stress-relieved strand is made in two forms. The first is    Island Nuclear Station Unit No. 2 in Pennsylvania the seven-wire strand. which conforms to ASTM                employs the St resstecl S/Il multistrand system coisisLing Specification A-416. *'Uncoated Seven-Wire Stress.            of tendons with 54 1/2-inch. Grade 270K. 7-wire strands Relieved Strand for Prestressed Concrete.- The second        per tendon, each tendon developing 2230 kips capacity.


to delineate techniques used by the staff In evalu- The guides arc slauad In the following ten broad divisons: ating specific problems or postulated acckdents, or to provide guidance to appli-cants. Regulatory Guides ere not substltutes for regulations, and compliance
forni consists of larger strands Iltat are made of larger individu al wires anid may consist of more thian seven            The Freyssinet systemn was naimted after (ie French wkires per strand. vhe larger strands are not covered hy      engineer Eugene Freyssinet. who itivented the anchorage ASTM spicifications and have not been used for the           device in I939. The original anchorage device was for a construction of nuclear power plants in lhe United            wire system only, This is a comn monly used commercial Slates.                                                      system. The anchorage consists of a male conical plug and a female conical recess. The plug. with the wires Strand systems have been introduced in the construc-      spaced evenly around ils perimeter, anchors tile wire by tion of nuclear power plants by Strand-Wrap, N'SL.            wedge action.
1. Power Reactors .Products with them Is not required.


Methods and solutions different from those set out in Z Research and Test Reactors 7. Transportation the guides will be acceptable if they provide a badis for the findings requisite to 3. Fuels and Materials Facilities S. Occupational Health the issuance or continuance of a permit or icense by the Commisslon.
(Vorspann System Losinger). Stressteel. Freyssinet. and SEEE (Societe d'Ettides et diEqtiipments d'Enterprises).          As a result of market requiremenmts and subsequent The last two systems were considered but have not yet          developments. the Freyssinet system now also has been used in the United States in nuclear power plants.        available anchorages for strand tendons and other shapes Both the Freyssinet and SEEE systems have been used in        of anchorage devices different fron the original one. The Europe on concrete reactor vessels.                          swame wedge principle for ancho*ring the tendon is retained, however. Concrete reactor vessels have becn The Strand-Wrap system has been reviewed and             built in Europe using the Freyssinet strand system with a approved only for applying hoop prestressing 1o soine          maximum tendon capacity of abouw 2000 kips.


4. Environmental and Siting S. Antitrust Review Comments and suggestions for Improvments In those guides are encouraged
PCRVs in the Ltnited States. The basic principles of applying ltoop prestressing to the PCRV by the                    The SlEHk system was developed in France by Societe Sirand-Wrap system are the same as those for                 d'Etudes Ce d'Equipnments d'Enterprises. The system conventional prestressed concrete tanks and circular          features threaded anchorage fittings extruded onto the liquid containers ithat have been built using wire-winding    ends of a group of strands. An anchoring nut is then machines. Steel-lined circumferential precast concrete        threaded onto the anchorage fitting and turned tightly channels are anchored to the outer cylindrical surface of    against (lte bearing plate. A tendon is composed of one the vessel by reinforcing bars extending radially inward      or several such anchorage fittings on a common bearing from the precast channels. The strand is anchored at one      plate.
5. Materials and Plant Protection
10. General at all times. and guides will be revised, as appropriate, to accommodate com-ments and to reflect new information or experience.


This guide was revwid as a Copies of published guldes may be obtained by written request Indicating the result of subetantive comments received from the public and edditional staff divisions desired to the U.S. Nuclear Regulatory Commission, Weshington.
end by means of a tapered wedge grip in the rib between adjacent channels and then wound around the vessel at              Bar Systems. Bat systems employ a number of ihe design tension for a number of turns and anchored in      high-tensile-strength steel bars that are bundled into a the next adjacent rib. Each band of circumferential prestressing consists of multiple layers of strand wound onto these channels. Each layer consists of one              *The Irey-yinet. SI-l-,       and VSL systemsl were formally contittuottis length of strand. A maximum hoop                  prt.m-niled is allternatives to Ile previomstiy approved IItIRV
prestressing force of about 6600 kips per linear foot of        system. ThmeV'SL syteim was chosen by Mhe applicant.


D.C.review. 2M. Attention:
Consequently. the Freyssinel and SIE systems were not vessel height is being used in the design of the PCRV          rnvicwed by the NRC starf with regard to their acceptability for head region of the Dehmarva Summit Power Station.               use in nutclear power plant Containments.
Director.


Office of Standards Development.
1.103-2


containments built in the United States. The main feature of this system is the use of cold-formed buttonheads for direct bearing at each end of the wire.The prestressed concrete reactor vessel (PCRV) of the Fort St. Vrain station in Colorado uses the BBRV system with 169-wire tendons developing approximately
M
2000 kips capacity each. A number of containments using the BBRV system with 90, 163, 169, 170, and 186 wires per tendon have been built in the United States.The wire diameter is 1/4 inch (6.35 mm) in all cases except for the 163-wire tendon, which uses 7-mm (0.28 inch) wire.A wire-winding system was used to provide hoop prestress for the Hartlepool PCRVs in England. This method of providing hoop prestress is similar to that for conventional prestressed concrete tanks.Strand Systems. Strand systems use a number of"strands" that are bundled into a tendon. A strand is made up of a number of factory-twisted wires. Stress-relieved strand is made in two forms. The first is the seven-wire strand, which conforms to ASTM Specifica- tion A-416, "Uncoated Seven-Wire Stress-Relieved Strand for Prestressed Concrete." The second form consists of larger strands that are made of larger individual wires and may consist of more than seven wires per strand. The larger strands are not covered by ASTM specifications and have not been used for the construction of nuclear power plants in the United States.Strand systems have been introduced in the construc-tion of nuclear power plants by Strand-Wrap, VSL, (Vorspann System Losinger), Stressteel, Freyssinet, and SEEE (Societe d'Etudes et d'Equipements d'Enter-prises). The last two systems were considered but have not yet been used in the United States in nuclear power plants. Both the Freyssinet and SEEE systems have been used in Europe on concrete reactor vessels.The Strand-Wrap system has been reviewed and approved only for applying hoop prestressing to some PCRVs in the United States. The basic principles of applying hoop prestressing to the PCRV by the Strand-Wrap system are the same as those of a wire-winding system. In one of the design methods, steel-lined circumferential precast concrete channels are anchored to the outer cylindrical surface of the vessel by reinforcing bars extending radially inward from the precast channels.
tendon.   "l Ie bars    are mnade    front an alloy steel      been easier 1o acco inplish tltough lite use olftngrouted conformiug to ASTM Specifications A-322 and A-29.                 tendolns.


The strand is anchored at one end by means of a tapered wedge grip in the rib between adjacent channels and then wound around the vessel at the design tension for a number of turns and anchored in the next adjacent rib. Each band of circumferential prestressing consists of multiple layers of strand wound onto these channels.
A-322 is a general specificalion that covers only the chemical composition of many grade dcsignatioi., of alloy steel bars. and A-29 is a specification for generl                         


Each layer consists of one contin-*Lines indicate substantive changes from previous issue.uous length of strand. A maximum hoop prestressing force of about 6600 kips per linear, foot of vessel height was to have been used in the design of the PCRV head region of the Delmarva Summit Power Station.**
==C. REGULATORY POSITION==
The VSL strand system, which was developed in Switzerland, uses a wedge anchorage for strands. Each strand is drawn through the openings of both the bearing plate and the anchor head and is held by a two-piece split cone wedged tightly against the inner surface of the anchor head. As an example, the containment of the Rancho Seco Nuclear Generating Station in California uses the VSL system with tendons consisting of 55 strands, each tendon developing
requirements for hot-rolled and cold-finislted cat bun and alloy sled bars. No ASTM specinication covers the                      This regilatory !!tuide .*ovcfs the generic qualificatiors ininimuni mechanical and physical requtirementlls for the          otf po*st-tisiiolned prestcissih*g systenis lised in colnclete prestrcssing bars after processing. as in the case (if' wires      reactor vessels and conlainrlieits. with Ilo) atlerlmi to (A-42I ajnd strands (A-416) and it is for this reason that        extenid its scope to design aspecis. The accepiahility ol a speciticati )i* was written by tre Prestressed Concrete        any posil-ellsiolled prestre.Nsirig syslelm ill conjunction Institute.                                                        with a specific structute design woitld lhave to bie evaluated on a case-by-case basis. Any proposed system Bars are cold-stretched and also stress-relieved by heat      submitted for NRC approval should consider tile treatmenu Ito produce the prescribed mechanical                    following:
2250 kips capacity.(The Freyssinet, SEEE, and VSL systems were formally presented as alternatives to the previously approved BBRV system. The VSL system was chosen by the applicant.
properlies. Bolih defornied bars and smooth bars with threaded ends are available. hut only sinooth bars have                    1. Post-tensiuned prestressitig systeirs that have been used for unclear plower plant conStructioll in tihe          beell approved in previous nuclear powcr plailt license United Slates.                                                    applications are regarded as accepted systems. See Table A for idcntification. When tie clain is nade by ail The Stressicel Corporation in the United States              applicant that tile prestressing sysienr proposed is ail employs a bar system. The bars are stressed by mneans of           accepted systei., sufficient int'[rination shouttld be pro- an hydraulic jack that consists of a coupler and pulling          vided with each iipplication to demonstrrtc that tile bar. The normal commercial tech tiique for anchoring              system proposed is the samne as tile on*e that was uses anchor nuits. During stressing. t[le anchor nuts are          approlJd iii !.ý'\vious muclear powel plant license ;ipplica continuously screwed down on washers and bearing                  iions. Pri:,-r approval of any system does Inol relieve tile plates. and the prestressing force is then transferred to          applicanm of the responsibility for demonstrating that its tile anchorage assembly by releasing the force in tihe            svslenli leets all tle requirementIs of thle ('*Lc for jack. Wedge atn' grip-nut anchorages are also available to        Concrete Reactor Vessels and Containmenls.41 anchor the bar; they possess tile advantage of being able to grip the bar at any point along its length.                              2. Changes in prestressiig element materials or in aichorage items of previously accepted systems that The containment structure of H1.B. Robinson Unit              may require replieatig the., system peritrtnance tests are No. 2 in ilartsville. Soutlh Carolina. employs lie                identified in Subsections ('11 and CC, Article 2406 of the Stresstecl bar system anchored with Howlett Grip Nuts.             Code for Concrete Reactor Vessels and Containmntetils.


Consequently, the Freyssinet and SEEE sys-tems were not reviewed by the NRC staff with regard to their acceptability for use in nuclear power plant containments.)
The tendon. comuposed of six I-3/8-inch-diatnuter Stressleel bars,. develops a cap',:ity of 1428 Kips.                       3. Any new post-tensioned prestressing sysreiri should meet the requiremenls set fo7rth in tile Code to, Concrete Reactor Vessels and Containments.
The Stressteel S/H multistrand system, which was developed in the United States by Stressteel Corporation in cooperation with Howlett Machine Works, is charac-terized by a three-piece slotted wedge cone that grips three strands in its serrated teeth, with a number of wedges in a single anchor plate making up a multistrand tendon of the desired size. As an example, the contain-ment of the Three Mile Island Nuclear Station Unit No.2 in Pennsylvania uses a Stressteel S/H multistrand system consisting of tendons with 54 1/2-inch, Grade 270K, 7-wire strands per tendon, each tendon develop-ing 2230 kips capacity.The Freyssinet system was named after the French engineer Eugene Freyssinet, who invented the anchorage device in 1939. The original anchorage device was for a wire system only. This is a commonly used commercial system. The anchorage consists of a male conical plug and a female conical recess. The plug, with the wires spaced evenly around its perimeter, anchors the wire by wedge action. As a result of mjjket requirements and subsequent developments, the Freyssinet system now also has available anchorages for strand tendons and other shapes of anchorage devices different from the original one. The same wedge principle for anchoring the tendon is retained, however. Concrete reactor vessels have been built in Europe using the Freyssinet strand system with a maximum tendon capacity of about 2000 kips.The SEEE system was developed in France by the Societe d'Etudes et d'Equipements d'Enterprises.


The system features threaded anchorage fittings extruded onto the ends of a group of strands. An anchoring nut is then threaded onto the anchorage fitting and turned**The Delmarva Summit Power Station has been canceled.1.103-2 tightly against the bearing plate. A tendon is composed of one or several such anchorage fittings on a common bearing plate.Bar Systems. Bar systems use a number of high-tensile-strength steel bars that are bundled into a tendon.'The bars are made from an alloy steel conforming to ASTM Specifications A-322 and A-29. A-322 is a general specification that covers only the chemical composition of many grade designations of alloy steel bars, and A-29 is a specification giving general requirements for hot-rolled and cold-finished carbon and alloy steel bars. The mechanical and physical requirements for the pre-stressing bars are covered by ASTM Specification A-722,"Uncoated High-Strength Steel Bar for Prestressing Concrete." Bars are cold-stretched and also stress-relieved by heat treatment to produce the prescribed mechanical proper-ties. Both deformed bars and smooth bars with threaded ends are available, but only smooth bars have been used for nuclear power plant construction in the United States.The Stressteel Corporation in the United States uses a bar system. The bars are stressed by means of a hydraulic jack that consists of a coupler and pulling bar.The normal commercial technique for anchoring uses anchor nuts. During stressing, the anchor nuts are continuously screwed down on washers and bearing plates, and the prestressing force is then transferred to the anchorage assembly by releasing the force in the jack. Wedge and grip-nut anchorages are also available to anchor the bar; they have the advantage of being able to grip the bar at any point along its length.The containment structure of H.B. Robinson Unit No. 2 in Hartsville, S.C., uses the Stressteel bar system anchored with Howlett Grip Nuts. The tendon, which is composed of six 1-3/8-inch-diameter Stressteel bars, develops a capacity of 1428 kips.Grouted and Ungrouted Tendons All of the concrete reactor vessels and containments designed and built in the United States use ungrouted tendons except for H.B. Robinson Unit 2 (bar tendons), Three Mile Island Unit 2 (strand tendons), and Forked River (strand tendons), all of which were designed for grouted tendons. On none of these, however, has design credit been given for any bond of the grouted tendons.Whether grouted or ungrouted tendons are used, a means of determining the functional capability of the structure during its lifetime should be available.
Grouted and Ungrouted Tendons
                                                                            4. The use of any post-tc*sioned prestressing system should permit the applicatio            of ail iriservice All of the concrete reactor vessels and containments inspection program that will verify the continued designed and built in tie United Slates use ungroited functional capability of tile structure. Implemenlation tendons except for H.B. Robinson Unit 2 (bar tendons),
                                                                  of this program should not degrade the quality aid Three Mile Island Unit 2 (strand tendons), and Forked reliability of the post-tensiorled prestressing system.


This results in a need for reliable quality assurance procedures for the tendon installations and in a need for a reliable structural inservice inspection program.C. REGULATORY
River (strand tendons), all of which were designed for Regu.latory Guides 1.35. "'tisetvice Inspection ill UnIli.
POSITION This regulatory guide covers the generic qualifications of post-tensioned prestressing systems used in concrete reactor vessels and containments, with no attempt to extend its scope to design aspects. The acceptability of any post-tensioned prestressing system in conjunction with a specific structure design would have to be evaluated on a case-by-case basis. Any proposed system submitted for NRC approval should address the fol-lowing: 1. Post-tensioned prestressing systems that have been approved in previous nuclear power plant license applica-tions are regarded as accepted systems. See Table A for identification.


When the claim is made by an applicant that the prestressing system proposed is an accepted system, sufficient information should be provided with each application to demonstrate that the system pro-posed is the same as the one that was approved in previous nuclear power plant license applications.
grouted tendons. On none of these, however. has desigin grouted Tendons iin Prestressed Concrete Containumen credit been Oven for any bond of the grouted tendons.


Prior approval of any system does not relieve the applicant of the responsibility for demonstrating that its system meets all the requirements of the Code for Concrete Reactor Vessels and Containments.*
Strulctures.' and I.90. "Inservice Inspection *f' Pre- stressed Concrete Containnient Structures with (Grouted Whether grouted or ungrouted tendons are used, a              Tendons." should be consulted for recommiendations means of determining ile functional capability oif [lie            concerning the use of ungrouted and grouted concrete structure during its lifetime should be available. This            contlainrents, respectively.
2. Changes in prestressing element materials or in anchorage items of previously accepted systems that may require repeating the system performance tests are identified in Subsections CB and CC, Article 2466 of the Code for Concrete Reactor Vessels and Containments.


3. Any new post-tensioned prestressing system should meet the requirements set forth in the Code for Concrete Reactor Vessels and Containments.
results in a need for reliable quality assurance procedures for t[le tendon installations and a need for a reliable structural inservice inspection program. To date, this has
                                                                  "ASME Boiler and t'ressure Vessel ('ode. Section Itt. Division 2 (tile latest version, plus addenda, as endorsed by t(ie Nuclear
""(;uide Specification for Post-Tunsioning Materials," PCI Post-    Regutatory Commission). This Code is currently under review Tensioning Manual. Prestressed Concrete institute, 1972.          f'or endorsement by the NRC staff.


4. The use of any post-tensioned prestressing system should permit the application of an inservice inspection program that will verify the continued functional capa-bility of the structure.
1.103-3


Implementation of this program should not degrade the quality and reliability of the post-tensioned prestressing system. Regulatory Guides 1.35, "Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures," and 1.90, "Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons," should be consulted for recommendations concerning the use of ungrouted and grouted concrete containments, re-spectively.
D. IMIVPLEMENTATION                                    porilons of't ile Ct ininlission'~s reglIluc ions. tile Ilethod dec~ribed hecrein %%ill be used inl tile evaluationt of suhbmittals for const ruction permit applicatiouns do cketed TheI. purIpos OfL    r 1 iSisNC I io is ito provide ii tort u (on        after J1Liie 30, 1976).
(o alpp ic amus autd li elscees regard ing tie staff's phlans for using~l this regullatory - title.                                                   I all applicant %%ishles wouse this repuiit:Iory lideill.'h developing submnittals tku applicat:ions docketed til or
      "*c      itlt lhoste cCases ill which theileaplicalt proposes          bel'ore JuIte 30. 1976. the pertinemn portlnuls oi tlie aft;dernaltive metho)d fotr co*mplyin,, %%ith spec.ified application \Mi] lhe evailaied oin the basis ol" this puide.


*ASME Boiler and Pressure Vessel Code, Section III, Division 2 (the latest version, plus addenda, as endorsed by the Nuclear Regulatory Commission).  
TABLE A
This Code is currently under review for endorsement by the NRC staff. Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y.10017.1.103-3
                                                  STATUS OF SYSTEMS AS OF MAY 11975 use(/
                                                                                                                                In US. A'tich'ar i
                                                                    IRr        i~ c iv i; iahl it
                                                                            ,e',s                            A'RC                1'oivvr I'lants
                          1Por I. iccnlsh~ii Revi'it'                                                      staff                 7',) Dim,
                                      .x                                      x                                                        x
00, 1w), 170.


==D. IMPLEMENTATION==
t,ý(. Wiles
The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.ing with specified portions of the Commission's regula-tions, the procedure described herein is being and will continue to be used in the evaluation of submittals for construction permit applications until this guide is revised as a result of suggestions from the public or additional staff review.This guide reflects current NRC staff practice.
(1/4 ill. r0)
163 W i 10s VS L.                                 x                                      x                              x                        x
      ( 'sranlds)
St re~sscel                            N                                    x                              x                        x sti ra nuls)
                                      x ist rall ()
                                        x
(5stratid)
strcssicel                              x                                      x                              X                        x
(6 1-.3X it.


There-fore, except in those cases in which the applicant proposes an acceptable alternative method for comply-TABLE A STATUS OF POSTTENSIONED
I
PRESTRESSING
POW'R      Strand.                    x                                      x                              x WVrap UNITED STATES
SYSTEMS AS OF MAY 1976 Submitted For Licensing Review Reviewed For Licensing Acceptabii, .v Approved By the NRC Staff Used In U.S. Nuclear Power Plants To Date System BBRV 90, 169, 170, 186 Wires (1/4 in 0)163 Wires (7 mm i)VSL (55 strands)Stressteel S/H (54 strands)Freyssinet (strand)SEEE (strand)Stressteel
NUCLEAR REGULATORY COMMISSION
(6 1-3/8 in.bars)PCRV Strand-Wrap X X X X X X X X X X X X X X X X X X X X X 1.103-4}}
            WASHINGTON. 0. C. 20555 POSTAGE AND rccs    PAID
              OFFICIAL BUSINESS                                                                    U.S. NUCLCEAR RCGULATORY
    PLNALTY FOR PRIVATE USE. S300                                                                        COMMISSION
                                                                        1.103-4}}


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Latest revision as of 00:18, 20 March 2020

Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments.
ML13350A289
Person / Time
Issue date: 11/30/1975
From:
NRC/OSD
To:
References
RG-1.103
Download: ML13350A289 (4)
v • d • e


U.S. NUCLEAR REGULATO COMMISSION.

November 1975 REGULkizORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.103 POST-TENSIONED PRESTRESSING SYSTEMS

FOR CONCRETE REACTOR VESSELS AND CONTAINMENTS

A. INTRODUCTION

to provide a rel'erctice io some plants for %,'hich tile sysvetns in Table A have been proposed o, approved. The

(;General Design C(riteriun I. "Quality Standards and ex:amples cited are not intended to *indicote any Records" of Appendix A. "'General Design Criteria for testriction or prel'evence in size of the tendot for a given Nuclear I(oiver PlanIs." to 10 C(FR Part 50. *'Licensing system. Nor is this -uide intended 'to discourage the if Prodlucion. and Utilization Facilities.'- ,equires. in developmtent of refinements of curr.ent systems or the part. that structures. systems. and components im- development of new prestressing systems or concep)ts.

lporlani to safety be designed. fabricated, and erected to (tllality standards commensurate with the importance of "hte quatliflcat ions dhat a post-tensioied piestnessitig Ihe saflcy luncliotins to be performed. This guide identi- s'.stem should meet in order td ibe acceptable to tie ties Ithe post-tensioned pcstressing systems Iltat hiave NRC st-a Tare iden~ified in tlicaiegulatowv positioti. Rock been reviewed and ai.rovcd by the NRC staff for use in anchorage systems are..not covered by this guide.

concrete reactor vessels and containmnents and also describes qualifications acceptable to the NRC slafr for new post-tcnsioned prestressing system

s. Types of Systems

B. DISCUSSION

STlhie type tof tendon selected usually diclates the choice of stressing eqluipment and also affects the choice A oims-tensioned prestressing system is composed ofa' ,of end .atchorages.

prestressing tendon combined with a method of sira.sing and anchoring the tendon to thie hatrdened coz.crete.Th.e Basically. post-tensioued prestressing systenis can be word "symeste is commonly associated ith the. dif-" separated into Ihree general categories by Ihe types oh fercni proprietary post-tensioned prestrcssing.systenl oil terndon in use: wire, strand. and bar systems. lEtnd Ihe market and is understood to include .the.type of anchorages for these tendons are based ott either wedge tendon, anchorage device, and stressing equlipment or direct-bearing p.inciples: sometimes a combination of associated with a given systemi.-. ihe two is used. A description is presented below ot post-tensioned prestressing systems in ternis or types tit It is not practical ito discussthe details or all of the tendons and end anchorages.

many post-tensioned:.irestressilng sysiems available in the United States. Nlore)ver.'"inw pidit-tensioned prestressing Wire Systems. Wire systents employ a tumber ot systems are being: devclopod, and existing ones are being parallel wires grouped to form a tetndon. Wires modified. F-6r "te nsreas. the descriptions in this manufactured in the United States conforni to ASTMt guide are Ii*u16 to -systnis listed in Table A. all of Specification A-421. "Uncoated Stress.Relieved Wire for which havbeel used or proposed for use. FPrestressed Concrete." This specification provides for wires of two types (BA or WA). depending on w\hetite Some examples of use are presented in order to tltey are to be used with buttons or wedge.type identify iiore specifically thie system being discussed and anchorages.

USNRC REGULATORY GUIDES C,,,nierr-ns should be sent to the Secretarv of the Commiss*,on. U S Nuclear AreqUlallor Conui'I*,Ison. Wasin~l~gtoni. D C M56 Alttention Docketing ando Regulatory Galde* ire i*,sued to desc*ibe and otike aviddh*le to Ihe Iyith. Seulit SeCtion .A

methods acceptatle" o thtf NRC ftill tot rmpim enmrtingspecific par the rf Se Coninti.,5on I reguajutions. 10 delineatei techniques used by th" tiltl an ttvalu lb. qutirmtesate issued in Iharfollowing ton brand divisionh Chirq itspi'ct c rutalems, or vustl.fle~d .Atc~dnlel. or to Iriovad. g lsani.nI,, itpli cants ARguldiriao Guidesi at.e not subslitults fot regulations. and Conipli*lhco I Powser Reactors 6 Products with them inot retjtlleii Miridb dint SnIu Illto- fIoent front lhose set (,,ii itt 2 flese'rch and Yost Reacit% 7 Transtproation th: gui*de* wit: he 'uptih*lt*te it th provide v'y a t fit tie ht,,% fandings requisite to 3 hueldsandMa*terl*1,Faciltes 8a Occuptilonl Heoalth the islsum Illo itlt!tte . ii1 rt tir ticrmnei*ihthe ICunmnmisiOn 4 Ern-tioninientland Siting 9 Antitrust Reirew C(rrrriietlsfl1 trait+Stiajleslilis 1,14111IiiLVitullill11t5 ii ttlhlse ajiantaits itlt. rielt lateri.rts l aild PIrItMPiolec*irn tO Genet a lt ii , . Jtt11 q wil"itt1i. l ,l a iI t aIaiiiI . t-1lu ,ict..ill.....l..late ;oin, MGMlls rid,1tIa iiltte,'.t -ew it..I-li.iiiiiii t..(uial r -- ý c ...

l..irvi

t. ian

.i1rntt...1it. C(i:;aie of tulAtished guides rtadyble olbtainld lIv written request aidacating the INis iju li1.. ii tem .itm (l artaila ,it Iii t 1a1111m1la .Ilrer O , as,i i.'.

its .,il tie iPa divisions desired to the UtS Nucltear Regultatuor Commission. W a~shtng lor . 0 C

tImulai ly usef ll iii t hli llillii 'niri. l .ti .t....i.. y IV.,..a.... IOt2 5, Allen tion D lte . lol. Office of ,SlandaidiDeveltopm ent

The BBRV system, developed in Switzerland by The VSL strand system was.developed in Switzerland.

Birkenmaier. Brandestini. Ros. and Vogt. is a wire This system employs a wedge anchorage for strands.

system used in both concrete reactor vessels and Each strand is drawn through the openings of both the containments built in the United States. The main bearing plate and the anchor head and is held by a feature of this svstenz is the. use of cold.lormed two-piece split cone wedged tightly against the inner buttonheads for direct bearing at each end of the wire. surface of the anchor head. As an example. the conttainmnent of the Rancho Seco Nuclear Generating Tie prestressed concrete reactor vcssel (PCRV) of the Station* in California employs the VSL system with Fort St. Vrain station in Colorado employs the B3BRV tendons consisting of 55 strands. each tendon developing system with 169-wire tendons developing approximately 2250 kips capacity.

2000 kips capacity each. A number of 2-ontainnienls utilizing the BBRV system with 90, 163. 16). 170. and The Stressicel S/Il multistrand systemi was developed

186 wires per tendon have been built in the United in the United States during 1967-1968 by Stressicel Slates. The wire diameter is 1/4 inch (6.35 imm) in all Corporationi in cooperation with llovwlett Machine cases except fur the 163-wire tendon, which uses 7-mm Works. The system is characterized by a three-piece

(0.28 inch) wire. slotted wedge cone that grips three strands in its serrated teeth, with a number of wedges in a single anchor plate Strand Systems. Strand systems employ a number of making up a ittllistrand lendon of the desired size.

"'strainds" that are bundled into a tendon. A strand is made tip tof a number of factory-twisted wires. As at, example. the conlainment of the Three Mile Stress-relieved strand is made in two forms. The first is Island Nuclear Station Unit No. 2 in Pennsylvania the seven-wire strand. which conforms to ASTM employs the St resstecl S/Il multistrand system coisisLing Specification A-416. *'Uncoated Seven-Wire Stress. of tendons with 54 1/2-inch. Grade 270K. 7-wire strands Relieved Strand for Prestressed Concrete.- The second per tendon, each tendon developing 2230 kips capacity.

forni consists of larger strands Iltat are made of larger individu al wires anid may consist of more thian seven The Freyssinet systemn was naimted after (ie French wkires per strand. vhe larger strands are not covered hy engineer Eugene Freyssinet. who itivented the anchorage ASTM spicifications and have not been used for the device in I939. The original anchorage device was for a construction of nuclear power plants in lhe United wire system only, This is a comn monly used commercial Slates. system. The anchorage consists of a male conical plug and a female conical recess. The plug. with the wires Strand systems have been introduced in the construc- spaced evenly around ils perimeter, anchors tile wire by tion of nuclear power plants by Strand-Wrap, N'SL. wedge action.

(Vorspann System Losinger). Stressteel. Freyssinet. and SEEE (Societe d'Ettides et diEqtiipments d'Enterprises). As a result of market requiremenmts and subsequent The last two systems were considered but have not yet developments. the Freyssinet system now also has been used in the United States in nuclear power plants. available anchorages for strand tendons and other shapes Both the Freyssinet and SEEE systems have been used in of anchorage devices different fron the original one. The Europe on concrete reactor vessels. swame wedge principle for ancho*ring the tendon is retained, however. Concrete reactor vessels have becn The Strand-Wrap system has been reviewed and built in Europe using the Freyssinet strand system with a approved only for applying hoop prestressing 1o soine maximum tendon capacity of abouw 2000 kips.

PCRVs in the Ltnited States. The basic principles of applying ltoop prestressing to the PCRV by the The SlEHk system was developed in France by Societe Sirand-Wrap system are the same as those for d'Etudes Ce d'Equipnments d'Enterprises. The system conventional prestressed concrete tanks and circular features threaded anchorage fittings extruded onto the liquid containers ithat have been built using wire-winding ends of a group of strands. An anchoring nut is then machines. Steel-lined circumferential precast concrete threaded onto the anchorage fitting and turned tightly channels are anchored to the outer cylindrical surface of against (lte bearing plate. A tendon is composed of one the vessel by reinforcing bars extending radially inward or several such anchorage fittings on a common bearing from the precast channels. The strand is anchored at one plate.

end by means of a tapered wedge grip in the rib between adjacent channels and then wound around the vessel at Bar Systems. Bat systems employ a number of ihe design tension for a number of turns and anchored in high-tensile-strength steel bars that are bundled into a the next adjacent rib. Each band of circumferential prestressing consists of multiple layers of strand wound onto these channels. Each layer consists of one *The Irey-yinet. SI-l-, and VSL systemsl were formally contittuottis length of strand. A maximum hoop prt.m-niled is allternatives to Ile previomstiy approved IItIRV

prestressing force of about 6600 kips per linear foot of system. ThmeV'SL syteim was chosen by Mhe applicant.

Consequently. the Freyssinel and SIE systems were not vessel height is being used in the design of the PCRV rnvicwed by the NRC starf with regard to their acceptability for head region of the Dehmarva Summit Power Station. use in nutclear power plant Containments.

1.103-2

M

tendon. "l Ie bars are mnade front an alloy steel been easier 1o acco inplish tltough lite use olftngrouted conformiug to ASTM Specifications A-322 and A-29. tendolns.

A-322 is a general specificalion that covers only the chemical composition of many grade dcsignatioi., of alloy steel bars. and A-29 is a specification for generl

C. REGULATORY POSITION

requirements for hot-rolled and cold-finislted cat bun and alloy sled bars. No ASTM specinication covers the This regilatory !!tuide .*ovcfs the generic qualificatiors ininimuni mechanical and physical requtirementlls for the otf po*st-tisiiolned prestcissih*g systenis lised in colnclete prestrcssing bars after processing. as in the case (if' wires reactor vessels and conlainrlieits. with Ilo) atlerlmi to (A-42I ajnd strands (A-416) and it is for this reason that extenid its scope to design aspecis. The accepiahility ol a speciticati )i* was written by tre Prestressed Concrete any posil-ellsiolled prestre.Nsirig syslelm ill conjunction Institute. with a specific structute design woitld lhave to bie evaluated on a case-by-case basis. Any proposed system Bars are cold-stretched and also stress-relieved by heat submitted for NRC approval should consider tile treatmenu Ito produce the prescribed mechanical following:

properlies. Bolih defornied bars and smooth bars with threaded ends are available. hut only sinooth bars have 1. Post-tensiuned prestressitig systeirs that have been used for unclear plower plant conStructioll in tihe beell approved in previous nuclear powcr plailt license United Slates. applications are regarded as accepted systems. See Table A for idcntification. When tie clain is nade by ail The Stressicel Corporation in the United States applicant that tile prestressing sysienr proposed is ail employs a bar system. The bars are stressed by mneans of accepted systei., sufficient int'[rination shouttld be pro- an hydraulic jack that consists of a coupler and pulling vided with each iipplication to demonstrrtc that tile bar. The normal commercial tech tiique for anchoring system proposed is the samne as tile on*e that was uses anchor nuits. During stressing. t[le anchor nuts are approlJd iii !.ý'\vious muclear powel plant license ;ipplica continuously screwed down on washers and bearing iions. Pri:,-r approval of any system does Inol relieve tile plates. and the prestressing force is then transferred to applicanm of the responsibility for demonstrating that its tile anchorage assembly by releasing the force in tihe svslenli leets all tle requirementIs of thle ('*Lc for jack. Wedge atn' grip-nut anchorages are also available to Concrete Reactor Vessels and Containmenls.41 anchor the bar; they possess tile advantage of being able to grip the bar at any point along its length. 2. Changes in prestressiig element materials or in aichorage items of previously accepted systems that The containment structure of H1.B. Robinson Unit may require replieatig the., system peritrtnance tests are No. 2 in ilartsville. Soutlh Carolina. employs lie identified in Subsections ('11 and CC, Article 2406 of the Stresstecl bar system anchored with Howlett Grip Nuts. Code for Concrete Reactor Vessels and Containmntetils.

The tendon. comuposed of six I-3/8-inch-diatnuter Stressleel bars,. develops a cap',:ity of 1428 Kips. 3. Any new post-tensioned prestressing sysreiri should meet the requiremenls set fo7rth in tile Code to, Concrete Reactor Vessels and Containments.

Grouted and Ungrouted Tendons

4. The use of any post-tc*sioned prestressing system should permit the applicatio of ail iriservice All of the concrete reactor vessels and containments inspection program that will verify the continued designed and built in tie United Slates use ungroited functional capability of tile structure. Implemenlation tendons except for H.B. Robinson Unit 2 (bar tendons),

of this program should not degrade the quality aid Three Mile Island Unit 2 (strand tendons), and Forked reliability of the post-tensiorled prestressing system.

River (strand tendons), all of which were designed for Regu.latory Guides 1.35. "'tisetvice Inspection ill UnIli.

grouted tendons. On none of these, however. has desigin grouted Tendons iin Prestressed Concrete Containumen credit been Oven for any bond of the grouted tendons.

Strulctures.' and I.90. "Inservice Inspection *f' Pre- stressed Concrete Containnient Structures with (Grouted Whether grouted or ungrouted tendons are used, a Tendons." should be consulted for recommiendations means of determining ile functional capability oif [lie concerning the use of ungrouted and grouted concrete structure during its lifetime should be available. This contlainrents, respectively.

results in a need for reliable quality assurance procedures for t[le tendon installations and a need for a reliable structural inservice inspection program. To date, this has

"ASME Boiler and t'ressure Vessel ('ode. Section Itt. Division 2 (tile latest version, plus addenda, as endorsed by t(ie Nuclear

""(;uide Specification for Post-Tunsioning Materials," PCI Post- Regutatory Commission). This Code is currently under review Tensioning Manual. Prestressed Concrete institute, 1972. f'or endorsement by the NRC staff.

1.103-3

D. IMIVPLEMENTATION porilons of't ile Ct ininlission'~s reglIluc ions. tile Ilethod dec~ribed hecrein %%ill be used inl tile evaluationt of suhbmittals for const ruction permit applicatiouns do cketed TheI. purIpos OfL r 1 iSisNC I io is ito provide ii tort u (on after J1Liie 30, 1976).

(o alpp ic amus autd li elscees regard ing tie staff's phlans for using~l this regullatory - title. I all applicant %%ishles wouse this repuiit:Iory lideill.'h developing submnittals tku applicat:ions docketed til or

"*c itlt lhoste cCases ill which theileaplicalt proposes bel'ore JuIte 30. 1976. the pertinemn portlnuls oi tlie aft;dernaltive metho)d fotr co*mplyin,, %%ith spec.ified application \Mi] lhe evailaied oin the basis ol" this puide.

TABLE A

STATUS OF SYSTEMS AS OF MAY 11975 use(/

In US. A'tich'ar i

IRr i~ c iv i; iahl it

,e',s A'RC 1'oivvr I'lants

1Por I. iccnlsh~ii Revi'it' staff 7',) Dim,

.x x x

00, 1w), 170.

t,ý(. Wiles

(1/4 ill. r0)

163 W i 10s VS L. x x x x

( 'sranlds)

St re~sscel N x x x sti ra nuls)

x ist rall ()

x

(5stratid)

strcssicel x x X x

(6 1-.3X it.

I

POW'R Strand. x x x WVrap UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON. 0. C. 20555 POSTAGE AND rccs PAID

OFFICIAL BUSINESS U.S. NUCLCEAR RCGULATORY

PLNALTY FOR PRIVATE USE. S300 COMMISSION

1.103-4


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