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#REDIRECT [[LIC-15-0142, Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements]]
| number = ML15363A042
| issue date = 12/23/2015
| title = Fort Calhoun, Unit 1 - Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements
| author name = Cortopassi L P
| author affiliation = Omaha Public Power District
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000285
| license number = DPR-040
| contact person =
| case reference number = CAC MF6676, LIC-15-0142
| document type = Letter, License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 108
| project = CAC:MF6676
| stage =
}}
 
=Text=
{{#Wiki_filter:Omaha Public Power District444 South 1 6'h Street MallOmaha, NE 68102-2247LIC-15-01 4210 CFR 50.90December 23, 2015U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555Fort Calhoun Station, Unit No. 1Renewed Facility Operating License No. DPR-40NRC Docket No. 50-285Subject: Supplement of License Amendment Request 15-03; Revise Current Licensing Basisto Use ACI Ultimate Strength RequirementsReferences: 1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk),"License Amendment Request 15-03; Revise Current Licensing Basis to UseACI Ultimate Strength Requirements," dated August 31, 2015 (LIC-15-0077)(ML1 5243A1 67)2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi), "Fort CalhounStation, Unit No. I -Supplemental Information Needed for Acceptance ofRequested Licensing Action RE: Revise Current Licensing Basis to useAmerican Concrete Institute Ultimate Strength Requirements (CAC NO.MF6676)," dated December 15, 2015 (NRC-I5-i104) (ML15341A224)In Reference 2, the U.S. Nuclear Regulatory Commission (NRC) notified the Omaha PublicPower District (OPPD) that OPPD's License Amendment Request (LAR) (Reference 1)proposing to revise the current licensing basis to use American Concrete Institute (ACI) ultimatestrength requirements was not acceptable as additional information was needed. As noted inReference 2, and subsequent teleconferences with the NRC, OPPD is providing thissupplement to supersede the Reference 1 LAR in its entirety. The enclosure to this letter hasbeen revised to address the information request of Reference 2.This License Amendment Request (LAR) proposes to revise the FCS Updated Safety AnalysisReport (USAR) to change the structural design methodology for Class I structures at FCS withseveral exceptions. The exceptions are the containment structure (cylinder, dome, and basemat), the spent fuel pool, and the foundation mats. No change to the current licensing basiscode of record is proposed for those structures. Specifically, this LAR proposes the followingchanges:1. Replace the working stress design (WSD) method with the ultimate strength design (USD)method from the ACI 31 8-63 Code for normal operating/service conditions associated withClass I structures other than the containment structure, the spent fuel pool, and thefoundation mats.Employment with Equal Opportunity U. S. Nuclear Regulatory CommissionLIC-15-0142Page 22. Replace the original specified value (i.e. 4000 psi for Class B concrete) with the actualcompressive design strength based on original 28-day test data which meets the strengthtesting criteria within ACI 318-63 (i.e. not age hardening).3. Use higher reinforcing steel yield strength values for the containment internal structure (CIS)that includes the reactor cavity and compartment (RC&C) and CIS beams, slabs andcolumns.4. Use the limit design method for evaluating the concrete in the RC&C walls includingdynamic increase factors (DIE) for impulsive loads.5. Minor clarifications include adding a definition of control fluids to the dead load section.The enclosure contains a description of the proposed changes, the supporting technicalanalysis, and the significant hazards consideration determination. Attachment I of theenclosure provides the existing USAR Sections (i.e. Sections 5.2 & 5.11) marked-up to showthe proposed changes. Attachment 2 of the enclosure provides the retyped (i.e. clean) USARSections. The proposed changes have been reviewed and approved by the Fort CalhounStation Plant Operations Review Committee (PORC) and by the Nuclear Safety Review Board(NSRB). The amendment will be implemented within 90 days of approval.Although this LAR is neither exigent nor emergency, prompt staff review is requested withapproval by June 1, 2016 in order to resolve design basis issues with Class I structures. Thereare no new regulatory commitments contained in this submittal.In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being providedto the designated State of Nebraska official. If you should have any questions regarding thissubmittal or require additional information, please contact Mr. Bill R. Hansher at (402) 533-6894.I declare under penalty of perjury that the foregoing is true and correct. Executed onDecember 23, 2015.Louis P. CortopassiSite Vice President and CNOLPC/JAC/mleEnclosure: OPPD's Evaluation of the Proposed Changec: M. L. Dapas, NRC Regional Administrator, Region IVC. F. Lyon, NRC Senior Project ManagerS. M. Schneider, NRC Senior Resident InspectorDirector of Consumer Health Services, Department of Regulation and Licensure,Nebraska Health and Human Services, State of Nebraska LIC-15-0 142EnclosurePage 1QPPD's Evaluation of the Proposed ChangeSupplement of License Amendment Request (LAR) 15-03;Revise Current Licensing Basis to Use ACI Ultimate Strength Requirements1.0 SUMMARY DESCRIPTION2.0 DETAILED DESCRIPTION3.0 TECHNICAL EVALUATION4.0 REGULATORY EVALUATION4.1 Applicable Regulatory Requirements/Criteria4.2 Precedent4.3 No Significant Hazards Consideration4.4 Conclusions5.0 ENVIRONMENTAL CONSIDERATION6.0 REFERENCESAttachments: 1. Markups of USAR Section 5.2 and USAR Section 5.112. Retyped ("Clean") USAR Section 5.2 and USAR Section 5.11 LIC-15-0 142EnclosurePage 21.0 SUMMARY DESCRIPTIONLicense amendment request (LAR) 15-03 proposes to revise Renewed FacilityOperating License No. DPR-40 to address design basis issues associated with Class Istructures at Fort Calhoun Station (FCS), Unit No. 1. Specifically, this LAR proposes torevise Updated Safety Analysis Report (USAR) Section 5.11, "Structures Other ThanContainment" (Reference 6.1), and USAR Section 5.2, "Materials of Construction"(Reference 6.2), which discuss the design and evaluation of Class I structures at ECS.USAR Section 5.5, "Containment Design Criteria" (Reference 6.3) also containsinformation describing the original design criteria for Class I structures at ECS; however,no changes to USAR Section 5.5 are necessary or proposed.USAR Sections 5.5 and 5.11, describe the original design criteria for reinforced concretestructures at ECS. This LAR proposes to apply the alternate design methodology usingthe ultimate strength design method (USD) provided in the ACI 318-63 Code to newdesigns or re-evaluations of existing Ciass I structures at ECS.The USD method will be applied to all Class I structures at FCS except the containmentstructure, the spent fuel pool (SEP), and the foundation. The containment structure,SEP, and the foundation mats will continue to utilize the most conservative requirementsof the current license basis (CLB) obtained by comparing the results of threeindependent methods of design including the working stress design (WSD) method ofthe ACI 318-63 Code. As noted in Amendment No. 155 (Reference 6.4), OPPD'sstructural analysis for the SEP demonstrates the adequacy and integrity of the poolstructure under full fuel loading, thermal loading, and safe shutdown earthquake (SSE)loading conditions and thus no change to the methodology for analyzing the SEP isproposed.Prompt NRC approval of this LAR will allow OPPD to proceed in an optimum, safe, andeffective manner. The proposed methodology changes are an integral part of theanalyses necessary to restore the design basis of the containment internal structures.The analyses ensure that any physical modifications necessary to resolve this issue areproperly engineered and constructed. With limited clearance inside the containmentbuilding, it is essential that any additional structures placed in the building be optimized LIC-1 5-0142EnclosurePage 3and provide tangible safety benefits. These structures will have significant mass and theact of maneuvering them into position has the potential to harm plant structures,workers, and/or the nuclear steam supply system (NSSS) or other safety-relatedequipment if an accident were to occur. New structures may also impede access toplant equipment necessary for plant operation and/or maintenance activities particularlyduring refueling outages.The proposed change consists of the following items described in detail in Section 2.0:1. Replace the working stress design (WSD) method with the ultimate strength design(USD) method from the ACl 318-63 Code for normal operating/service conditionsassociated with Class I structures other than the containment structure, the spentfuel pool, and the foundation mats.2. Replace the original specified value (i.e. 4000 psi for Class B concrete) with theactual compressive design strength based on original 28-day test data which meetsthe strength testing criteria within ACI 318-63 (i.e. not age hardening).3. Use higher reinforcing steel yield strength values for the containment internalstructure (CIS) that includes the reactor cavity and compartment (RC&C) and CISbeams, slabs and columns.4. Use the limit design method for evaluating the concrete in the RC&C walls includingdynamic increase factors (DIE) for impulsive loads.5. Minor clarifications include adding a definition of control fluids to the dead loadsection.2.0 DETAILED DESCRIPTIONPlanning for the construction of FCS began in 1966. The plant was designed andconstructed in accordance with the methodologies of the ACI 318 Building Code, 1963edition (i.e. the Code of Record (COR, Reference 6.5)). Facility Operating License No.DPR-40 was issued to the Omaha Public Power District (OPPD) on August 9, 1973. Byletters dated January 9 and April 5, 2002, (References 6.6 and 6.7 respectively), theOmaha Public Power District (OPPD) submitted a license renewal application (LRA) forFCS requesting renewal of the FCS operating license for a period of 20 years beyondthe previous expiration of midnight, August 9, 2013. In November 2003, RenewedFacility Operating License No. DPR 40 was issued (Reference 6.8), which expires at LIC-1 5-0142EnclosurePage 4midnight, August 9, 2033.In 2012, two latent engineering errors were discovered during preparations for a plannedextended power uprate of FCS. The first discrepancy is in calculation FC01421 wherethe steel reinforcement area in the calculation (design basis) is higher than the steelreinforcement area installed per the construction shop drawing. The seconddiscrepancy is the reaction from beam B-64 onto beam B-59. The calculation containsan error where the reaction on B-59 was low by a factor of 3.6. A detailed extent ofcondition concluded that several concrete beams in the ClS do not meet the currentdesign basis. An operability determination was completed demonstrating that the 01S isoperable. The operability determination was supported by several calculations thatspecified the criteria and methodology, performed a thorough review of dead loads, andexecuted a complete modeling analysis. As noted in Reference 6.9, the operabilitydetermination was conducted with computer software assessing the capability of the CISwith the USD method.The purpose of this LAR, is to update and clarify the CLB described in USAR Sections5.2 and 5.11 regarding the codes and standards used for the analysis of Class Istructures at FCS. For normal service conditions, the USAR requires the C1S to meetthe ACl 31 8-63 working stress design criteria. The USAR specifies the USD method forno loss of function conditions. This LAIR proposes methodology changes that will restorethe design basis of the Class I structures and maintain sufficient design margin to ensurethat the structures and the safety-related equipment inside them are adequatelyprotected during design basis accidents and natural events. Each of the Class Istructures has been evaluated and is operable.Overall characterization of the changes are adjustments to the CLB for application of theCOR,. These adjustments include using USD replacing WSD and use of actual strengthsfor applicable materials within the OCRP. The changes include adding state of the artmethods where the OCOR is silent.
LIC-1 5-0142EnclosurePage 5A description of the Class I structures discussed within this LAR is as follows:ContainmentThe containment building is a partially prestressed, reinforced concrete, Class I structurecomposed of a cylindrical wall and domed roof (i.e. shell) and a foundation mat. Thefoundation mat is common to both the containment structure and the auxiliary buildingand is supported on steel piles driven to bedrock. The mat incorporates a depressedcenter portion for the reactor vessel. The containment building has an internal carbonsteel liner.The containment building houses a substantial amount of safety-related and non-safetyrelated mechanical and electrical equipment and there are many mechanical piping andelectrical penetrations through the cylindrical wall.Containment Internal StructureThe CIS is an independent, multi-story, reinforced concrete structure located inside thecontainment structure. The CIS is isolated from the containment structure by a shakespace that permits the distribution and dissipation of any internal differential pressureduring postulated accident events. The CIS is composed of 269 structural elements(135 reinforced concrete beams, 32 reinforced concrete column sections, and 102reinforced concrete slabs) with an internal core consisting of the RC&C that physicallysupport safety related components -including the reactor coolant system, emergencycore cooling system piping, and the reactor components.Auxiliary BuildingThe auxiliary building is a multi-floored, reinforced concrete, Class I structure. From thebottom of the foundation mat to the roof elevation, the structure is of box-typeconstruction with internal bracing provided by vertical concrete walls and horizontal floorslabs. The spent fuel pool is contained within the auxiliary building and consists of astainless steel lined concrete structure. The control room is also contained in theauxiliary building. The auxiliary building masonry walls in the area of safety-related LIC-1 5-0142EnclosurePage 6equipment have been reinforced to provide protection for Class I equipment andcomponents located nearby.Intake StructureThe intake structure is a multi-floored Class I structure. From the bottom of thefoundation mat to 7 feet above the operating floor, the structure is a box-type reinforcedconcrete structure with internal bracing provided by concrete walls and floor slabs. Themat foundation is supported on steel pipe piles driven to bedrock. Above the reinforcedconcrete structure to the roof, the structure is a braced steel frame clad with aggregateresin panels. The multi-layered built-up roof is supported by metal decking spanningbetween open web steel joists. The intake structure houses and protects both safety-related and non-safety related systems and components.SummaryTo summarize, this LAR proposes to replace the working stress design method with theultimate strength design method for "Normal Operating/Service Conditions (OperatingBasis Earthquake OBE)". This change does not affect the two other conditions whichinclude "No Loss of Function (Design Basis Earthquake DBE)" and "Accident Conditions(high differential pressure and temperature plus DBE)." This methodology change willbe applied to all Class I structures except the containment structure, the SFP, and thefoundation mats as discussed previously. This methodology is commonly used at othernuclear plants (See Section 4.2). Load combinations are developed based on applicablecodes and equations for accident conditions currently defined in USAR Section5.11 .3.6.a.
LIC-1 5-0142EnclosurePage 7The following sections discuss each change separately in terms of the CLB, theproposed licensing basis (PLB), the plant structure impacted by the proposed change,design margin impacts, and finally, the consequences of the proposed change.2.0.1 Concrete normal/service condition design (change from WSD to USD) -See Section 2.1 for Additional InformationThe LAR proposes to replace the working stress design method with the ultimatestrength design method for "Normal Operating/Service Conditions (Operating BasisEarthquake OBE)".Table 1 -WSD to USD SummaryCurrent Three sets of load combinations are used to evaluate concrete forLicensing Class I structures:Basis 1) normal service conditions,2) no loss-of-function (i.e. design basis loads), and3) under special cases, accident high pressure and temperatureconditions.Normal service condition load combinations are based on WSDmethodology. USAR Section 5.11 currently permits the USDmethodology only for items 2 and 3.Proposed The proposed licensing basis (PLB) change is to normal serviceLicensing conditions where the USD method will replace the WSD method. TheBasis no loss-of-function and special cases load combinations (i.e. Items 2and 3 above) are unchanged and continue to utilize the USD____________methodology.Where All Class I structures (except the containment structure, spent fuelApplicable pool (SFP), and the foundation mats).
LIC-1 5-0142EnclosurePage 8MarginUSD Methodology provides adequate margin by requiring the use ofload factors and strength reduction factors as identified in ACI 318-63for concrete and reinforcement steel.USD methodology is covered in ACl 318-63 which is the currentlicense basis and is used for no loss of function and accidentconditions. USD methodology for normal service conditions will beused going forward and will meet the requirements of the ACI 31 8-63code.The load combination equations are developed for the USD methodreplacing WSD in the normal service conditions. These are factoredload combination equations based on standard use of the factoredload combinations (1 .4D plus 1 .7L). The current license basis is usedas the basis for the load combinations that include earthquake andwind loads. The load combination equations are considered tomaintain margin per the requirements of the ACI 318-63 Codeprovisions. These load combinations are similar to those used as partof the design basis for other nuclear power plants.4ConsequencesThis proposed change when combined with the change for actualconcrete strength described below is expected to eliminate the needto install a significant number of new columns. This minimizes thepotential for harm to structures, safety-related equipment, orpersonnel caused by the installation of these columns insidecontainment where siQnificant interferences exist.v LIC-1 5-0142EnclosurePage 92.0.2 Use of Actual Concrete Compressive Strength (Based on Original TestData) -See Section 2.2 for Additional InformationThe PLB for concrete strength is to use compressive strength based on original 28-daytest data for design basis. This LAR does not propose to use age hardening.____________ Table 2 -Concrete Strength SummaryCurrent Concrete is currently evaluated using the design value from theLicensing original construction specifications (i.e. 4000 psi for Class B concrete).Basis ______________________________Proposed When the plant was built, three (3) test samples were obtained,Licensing specifically a set of cylinders were prepared for, each 100 cubic yardsBasis or less of concrete placed on a given placement day. The PLBreplaces the original specified value (i.e. 4000 psi for Class Bconcrete) with the actual compressive design strength based onoriginal 28-day test data which meets the strength testing criteriawithin ACI 31 8-63 (i.e. not age hardening). Original test data showsthat the actual compressive strength of the concrete exceeds theoriginal design value (i.e. 4000 psi for Class B concrete). The methodfor determining the actual concrete compressive strength is discussedin detail within Section 2.2.Where As shown in Table 7 in Section 2.2.ApplicableMargin Adequate design margin is maintained in following the criteria forstrength testing of concrete as required within ACI 318-63 Section504. This method is discussed in detail in Section 2.2 below. Thetests completed during construction of the plant in the early 1970sshow the concrete is stronger than what was specified in the originaldesign, which indicates higher structural capacity. The PLB takesadvantage of the increase in capacity and revises the design basisvalue to the actual concrete strength while meeting the testing___________requirements withinACI_318-63.Consequences See 2.0.1 above.
LIC-1 5-0142EnclosurePage 102.0.3 Use of Actual Reinforcing Steel Yield Strength (Use original test data fordesign basis) -See Section 2.3 for Additional InformationThe proposal for reinforcing steel yield stress is to use a statistical increase from 40 ksito 44 ksi. The use of test data for steel was included in the operability calculations andreviewed during the 2012 inspections.Table 3 -Reinforcing Steel Yield Strength SummaryCurrent Concrete reinforcement is evaluated using the design value from theLicensing original construction specifications (i.e. 40 ksi).BasisProposed This PLB change replaces the design value from the originalLicensing construction specifications (40 ksi) with a conservative value (44 ksi)Basis derived from plant construction data.Where CIS (RC&C, columns, beams, and slabs).ApplicableMargin Adequate design margin is maintained because original test datashows that the mean yield strength with 95% confidence level_____________supports the increased in yield strength to 44 ksi.
LIC-1 5-0142EnclosurePage 11ConsequencesThis PLB change in combination with the changes discussed above(i.e. WSD to USD, actual concrete strength etc.) minimizes the needfor physical modifications to 01S and is anticipated to eliminate theneed for a significant number of columns. This minimizes thepotential for harm to structures, safety-related equipment, orpersonnel caused by the installation of these columns insidecontainment where significant interferences exist.ACl 31 8-63, the current COR, uses the inverse of a phi factor of 0.9and 0.85 applied to the load. This number is used to account fordesign inaccuracies, future changes, reliability of material strengths,dimension variations, etc., (Reference 6.5 Commentary Section1504). The design is accurate and all changes are evaluated. Thereis a high level of confidence in the material strengths. The PLBchanqe will continue to use the phi factor as prescribed by the COR.v * , 2.0.4 Use of Dynamic Increase Factors (DIF) and Limit Design for RC&C -SeeSection 2.4 for Additional InformationThe LAR proposes to allow use of dynamic increase factors (DIE) and limit designmethod for analysis of the RC&C.Table 4 -DIE and Limit Design Method SummaryCurrentLicensingBasisACI 318-63 Code does not provide Limit Design Methodology. TheCLB is silent on the use of DI~s.
LIC-1 5-0142EnclosurePage 12Proposed The PLB adopts the application of DI~s when appropriate for theLicensing RC&C and limit design method. The DI~s will be utilized as specifiedBasis in ACI 349-97, C.2.1 and will not be used if dynamic load factors(DLF) are less than 1.2. ACI 349-97, Appendix C is a commonlyaccepted design code used in the nuclear industry.The application of limit design method for RC&C walls includesdeformation limit equations in ACI 349-97 Commentary on AppendixC Section C.3The proposed application is similar to the guidance in Bechtel PowerCorporation, Topical Report BC-TOP-9A, "Design of Structures forMissile Impact," Revision 2, approved for use in the evaluation oftornado missile impacts at ECS by Amendment No. 272. The BechtelReport contains methods, including dynamic increase factors thatevaluate how missiles impact structural elements. Although OPPDproposes a slightly different application, the use of DIE for missiledynamic events has been approved at ECS. However, instead ofmissile impacts, the RC&C will be evaluated using DIE forcompartment pressurization.Where RC&C portion of the ClS.ApplicableMargin Adequate design margin is maintained in using the limit designmethod and DI~s by the conservatism in the load combination____________equations for short-term high differential pressure.Consequences The limited clearances available in the RC&C make the placement ofadditional concrete structures in that area extremely difficult. Use ofthe proposed changes significantly reduces or eliminates the need formodifications in the RC&C. The safety benefit that would be gainedby the installation of additional concrete structures in this area is smalland has the potential to damage the nuclear steam supply system(NSSS) or harm workers if an accident were to occur during______________ installation.
LIC-15-01 42EnclosurePage 132.0.5 Clarification of Hydrostatic Load in the USAR -See Sect. 2,5 for AdditionalInformationThe LAR proposes changes that include adding the definition of controlled fluids.____________Table 5 -Hydrostatic Load Clarification SummaryCurrent The CLB has no discussion of hydrostatic load from controlled fluidsLicensing (i.e. fluid in tanks).BasisProposed The PLB adopts controlled fluids as a dead load.LicensingBasisWhere All Class I structures.ApplicableMargin This change is considered clarifications that does not impact designmargin. It is called out here because it is incorporated in theproposed USAR change, but otherwise does not require NRCapproval. The PLB treatment of controlled fluids is consistent withindustry standards in accounting for the load from fluids stored invessels such as tanks.Consequences This change supports the distribution of loads for controlled fluids andhas minimal impact on restoration of the design basis of CIS or the____________ auxiliary building.In summary, the changes described in sections 2.0.1 through 2.0.5 have several partsthat along with anticipated physical modifications to a limited number of structures will beessential to the restoration of the design basis for CIS. The changes are not universallyapplied; application is limited to the specific areas described in this LAR.
LIC-15-0142EnclosurePage 142.1 Replace WSD with USD for Normal Operating/Service ConditionsFor normal operating/service conditions, the WSD load combinations, ACl 318-63 designmethods, and allowable stresses are replaced with equivalent USD factored loadcombinations and ACl 318-63 USD methods. The design loads are not changed,however, definitions for soil pressure (H) and controlled hydrostatic loads and theirinclusion into load combinations are added to the USAR for better clarity of the designmethod.The strength reduction factors (¢) are used in the required ultimate strength capacity (U)for use in normal operating/service conditions remain consistent with those alreadyaccepted for use in the USD used for the no loss-of-function loading conditions.The equivalent normal load combinations for USD (PLB) in comparison to WSD (CLB)are as follows:Table 6 -Load CombinationsUltimate Strength Desin Stress .-. (PLB)., --... .. *. ..(CLB) ' ..U = 1/f)(1.4 0 + 1.7L + 1.7H)(1) S = 0 + LU =1/c1(1.0D+/-+O.05D +1.25L +1.25W +1.25H)(2) S =D +L +H +W or EU =1/q)(1.0D + 0.05D + 1.25L + 1.25E + 1.25H)(2)U = 1/¢1(1.4D + 1.7H + 1.7F)(3) S = 0 + H + FWhere:S = Required section capacityU = Required ultimate strength capacityD = Dead load, including internal controlled hydrostatic4L = Live loadH = Soil Load4W = Wind loadE = Design earthquake LIC-1 5-0142EnclosurePage 15F = Flood hydrostatic load to elevation 1007 feetStrength reduction factor(1) The USD load factors for normal operating/service load conditions are consistentwith those for Equation 1 in Section 9.2.1 of ACl 349-97 (Reference 6.11) inaccordance with the guidance of Section 3.A. of Standard Review Plan (SRP) 3.8.4,Revision 4 (Reference 6.12). Note that these factors are less severe than thoserequired by the ACl 318-63 Code for the ultimate strength design load combination ofSection 1506 equation (15-1). However, the load factors applied to normal dead andlive loads (1 .5D +1 .8L) in the ACI 318-63 Code have not been commonly adopted bycommercial nuclear plants in the United States (See Section 4.2). The 1 .4D and1.7L load factors were implemented in the ACI 318-71 Code (References 6.13 and6.17.) and remained constant for more than thirty years. In addition, soil pressure (H)(lateral earth pressure or ground water pressure for design of structures belowgrade) is added to align with editions of ACI 318 issued subsequent to 1963.(2) The USD load combinations are developed for normal operating/service conditionsusing the current ultimate strength method USAR equation (i.e. 1//l, (1.0 D + 0.05D +1 .25Pc + 1 .25E + 1 .0Tc)) for the extreme condition, no loss-of-function equation.The equation is modified by replacing the Pc load (differential pressure betweencompartments resulting from reactor coolant system break) with the live load (L) andreplacing the Tc load with the soil load (H) to include lateral earth pressure, which isaligned with editions of ACI 318 issued after 1963. The load combinations for normalload conditions are similar to the ACI 318-71 Code equation 9-2: U = 0.75 (1.4D +1.7L + 1.7W).(3) The USD load combination for normal operating/service load conditions is revised toconsider dead load (D) in combination with the hydrostatic flood load (F) and soilpressure (H) to include lateral earth pressure. ACI 318-63 is silent regarding properconsideration of hydrostatic loads and soil pressure. This change is consistent withACI 349-97 and later revisions of ACI 318.(4) Soil dynamic pressure and hydrodynamic pressure loading shall be accounted,where applicable in accordance with the current licensing basis.
LIC-1 5-0142EnclosurePage 16These changes will be applied to new designs or to re-evaluations of existing reinforcedconcrete structures in the auxiliary building, intake structure, and containment internalstructures. As noted previously, these changes will not be applied to the containmentstructure, the spent fuel pool, or the foundation mats.For extreme conditions, the no loss-of-function ultimate strength load combinations willremain unchanged. However, a clarification to these load combinations includes soilload (H), which has always been included in design basis calculations. Thus, as this isintended to clarify the license basis, it is not considered a change.2.2 Determination of Actual Concrete Compressive Strength Based on Original TestDataThe containment structure was originally designed using Class A concrete (specified ascompressive strength 5000 psi). Other Class I structures (i.e. the auxiliary building,intake structure, and non-shell portions of the containment building) were originallydesigned using Class B concrete (specified as compressive strength 4000 psi).As detailed below, the proposed change will allow reinforced concrete structures locatedin specified areas of the auxiliary and containment buildings to be evaluated usingconcrete compressive strength based on actual 28-day test data while meeting thestrength testing requirements of the FCS licensing basis concrete Building Code ACI318-63 Section 504 in lieu of the original specified value (i.e. 4000 psi for Class Bconcrete). This is appropriate as original test data shows that the actual 28-daycompressive strength of the concrete exceeds the original specified value.No change is proposed to the design criterion for compressive strength of concrete inthe containment structure, intake structure, or the foundation mats.Proposed Methodoloqy for PLB Concrete Strengqth DeterminationThe concrete strength for the PLB will be determined through application of FCSlicensing basis concrete Building Code ACI 31 8-63 Section 504(c), which specifies theuse of the 28-day laboratory-cured concrete strength test data.
LIC-1 5-0142EnclosurePage 17This methodology will be applied for the structures as shown in Table 7. Specifically,one concrete strength will be established for the auxiliary building and one concretestrength will be established for containment internal structures.* Documentation of the new design basis concrete strengths will be recordedwithin FCS design basis calculations.* The 28-day test data used will be limited to the areas to which the data applies,i.e. the auxiliary building and containment internal structures.* A rolling average will be calculated for five consecutive strength tests for WSD(ACI 31 8-63 Section 504(c)(1 )).* A rolling average will be calculated for three consecutive strength tests for USD(ACI 31 8-63 Section 504(c)(2)).* The 20th percentile of the rolling average strengths will be calculated for WSD(ACl 31 8-63 Section 504(c)(1)).* The 10th percentile of the rolling average strengths will be calculated for USD(ACl 31 8-63 Section 504(c)(2)).* The minimum of the rolling average strengths for WSD and USD, not more thanthe 20th and 10th percentile for WSD and USD accordingly, will be used as thenew design basis concrete strength.* If more than the indicated permissive percentage is below the specified strength,the procedures of A~l 214-65 will be employed to determine if the averagestrength being calculated is adequately in excess of the specified strength (ACl318-63 Section 504(c)(*)).* FOS will limit this new design basis concrete strength to no greater than the 95%confidence level of all test data analyzed for each specific structure (additionalconservatism beyond ACl 31 8-63 requirements).Justification for Proposed MethodologqyThe actual concrete strengths determined with the methodology prescribed in thissection satisfies the strength testing requirements of ACI 318-63. As defined in Section301 of ACl 318-63, "Compressive strength shall be determined by test of standard 6-in. x12-in, cylinders made and tested in accordance with ASTM specifications at 28 days orsuch earlier age as concrete is to receive its full service load or maximum stress."
LIC-1 5-0142EnclosurePage 18Per ACl 318-63 Section 504(a), "Specimens made to check... strength of concrete or asa basis for acceptance of concrete shall be made and laboratory-cured in accordancewith... (ASTM C31) .... Strength tests shall be made in accordance with... (ASTM C39)."ACI 318-63 Section 504 also states, "Additional test specimens cured entirely under fieldconditions may be required by the Building Official to check adequacy of curing andprotection of the concrete." Test specimens cured entirely under field conditions are notspecified for the determination of concrete compressive strength.In regard to the use of rolling average calculations for data analysis, FCS licensing basisconcrete Building Code ACI 318-63 Section 504(c) specifies, "To conform to therequirements of this code:"For Working Stress Design:1. For structures designed in accordance with Part IV-A of this code, theaverage of any five consecutive strength tests of the laboratory-curedspecimens representing each class of concrete shall be equal to or greaterthan the specified strength, f0', and not more than 20 percent of the strengthtests shall have values less than the specified strength.For Ultimate Strength Design:2. For structures designed in accordance with Part IV-B of this code, and forprestressed structures the average of any three consecutive strength tests ofthe laboratory-cured specimens representing each class of concrete shall beequal to or greater than the specified strength, fe', and not more than 10percent of the strength tests shall have values less than the specifiedstrength.Limiting the determined strength to the 95% confidence level is an additional means ofestablishing a high level of confidence in the new design basis strengths.The actual concrete strength may only be used in areas not potentially affected bydegradation of concrete due to long-term exposure to high radiation, excessive moisture LIC-1 5-01 42EnclosurePage 19or harsh chemicals for prolonged periods. Areas of Class I structures where actualconcrete strength may and may not be used are shown in Table 7.Table 7 -Concrete Strength App licable AreasArea, Allowed Application-of Non-Allowed Application ofOriginal, Test, Data Original Test- Data1Auxiliary Building All areas except where Exterior walls at elevations belownot allowed. 1007 feet shall continue to usef'= 4000 psi.Containment Internal All areas except where Reactor cavity floor and concreteStructures (CIS) not allowed, around the reactor vessel shallcontinue to use f&' = 4000 psi.Intake Structure and Not allowed. Not applicable, will continue toFoundation Mat use f0' = 4000 psi.Containment Not allowed. Not applicable, will continue toStructure / use fc' = 5000 psi.Foundation MatsSpent Fuel Pool Not allowed. Not applicable, will continue touse fc' = 4000 psi.Note: The application of actual concrete compressive strength in lieu of original specified design values isnot allowed where structures undergo prolonged exposure to high radiation, excessive moisture, or harshchemicals.The containment structure, the spent fuel pool, the intake structure, and the foundationmats will continue to use the original specified design values for concrete compressivestrength.Aging management of these structures is described in Section 2.7 of this document.
L1C-15-0142EnclosurePage 202.3 Determination of Actual Reinforcing Steel Yield Strength Based on Original TestDataHigher steel yield strength values are proposed for reinforcement of the C3IS beams,slabs, and columns. Higher yield strength values are also proposed for reinforcing steelused in the re-evaluation of the walls of the reactor cavity and compartments (RC3&C).The increase is limited to 44 ksi. Section 3.3 of this document provides technicaljustification for the use of the actual yield strength.2.4 Use of Dynamic Increase Factors (DIF) and Limit Design for RC&CThe LAR proposes to allow use of dynamic increase factors (DIF) and limit designmethod for analysis of the RC3&C. This change applies to the reactor cavity andcompartment walls and transfer canal and is not being applied to other Class Istructures.In accordance with A(3l 349-97, Appendix C3, dynamic strength increase factorsappropriate for the strain rates involved may be applied to static material strengths ofsteel and concrete for purposes of determining section strength. The dynamic strengthincrease factors are specified in Section C3.2.1 of ACI1 349-97. This change will allow useof DIFs for no loss-of-function conditions associated with compartment pressurization.A gap analysis compared the ACI1 349-97 Code to the C3OR. See Section 2.9 for results.2.5 Clarification of Hydrostatic Load in the USAR Section 5.11The controlled hydrostatic load is changed from live load to dead load for ultimatestrength design in the definition. The definition for dead load was improved by clarifyingthat controllable fluids are considered dead load instead of a live load. This is consistentwith AC31-349-97.
LIC-1 5-0142EnclosurePage 212.6 Conditions that the Proposed Amendment will Resolve2.6.1 Replace WSD with USD for Normal Operating/Service ConditionsFor normal operating/service load cases, Fort Calhoun Station's original designcalculations used the WSD method, which gives unnecessarily conservative results incomparison to the USD method for the design of reinforced concrete structures. Forexample, the USD method does not show flexural overstress in normal loadingconditions as found during the re-constitution efforts for the CIS and auxiliary buildingusing the WSD method. The WSD method gives more conservative results for membercapacity compared to using the USD method. The difference in design margin betweenthe two methods varies depending on proportions and types of loads. The ACl 31 8-63USD method has been used for the design of reinforced concrete structures with safe,reliable performance for over fifty years, including its use at many other operatingnuclear power reactors.The proposed change only affects the evaluation of normal operating/service conditions.The no loss-of-function, ultimate load combinations for extreme conditions utilizing USDremain unchanged. The no loss-of-function condition evaluations will conservativelymaintain the application of differential pressure loads on containment internal structuresdue to a design basis pipe break accident such as a loss-of-coolant accident or mainsteam line break concurrent with a seismic event. OPPD will continue to maintain theexisting design margins for no loss-of-function conditions for extreme conditions at FCS.The proposed change increases consistency between normal operating/serviceconditions and no loss-of-function conditions. Projects requiring new designs or re-evaluations of existing reinforced concrete structures can be conducted more efficientlywith less chance for error as design calculations will only require USD membercapacities. (This does not apply to the containment structure, which will continue to usethe WSD method.) The current method requiring both WSD and USD calculations, isunnecessarily complex, and results in over-designed and over-engineered concretestructures. Furthermore, universities no longer teach working stress design and thereare a diminishing number of engineers with the necessary experience, due partly to thefact that local government jurisdictions no longer accept this obsolete method.
LIC-15-0 142EnclosurePage 22The proposed load factors use a select load combination (1 .4D + 1 .7L) for the ultimatestrength method to evaluate normal operating/service conditions and are consistent withEquation 1 in Section 9.2.1 of ACl 349-97 and are in accordance with the guidance ofSection 3.A of SRP 3.8.4, Revision 4. Although the ACl 349-97 load factors are lowerthan those required by the ACl 318-63 Code for the ultimate strength design loadcombination of Section 1506, Equation 15-1, U.S. commercial nuclear plants do notcommonly use the ACl 318-63 Code load combination (i.e. 1.5D +1.8L). The proposedload factors better reflect ultimate strength design behavior.Load combinations are developed for normal operating/service conditions using the noloss-of-function ultimate strength design method equation from USAR Section 5.11 (i.e.l/4b (I.0D _+ 0.050 + 1.25 Pc + 1.25E + 1.0Tc) by removal of differential pressure (Pc)and differential temperature (Tc) loads. These load combinations for normaloperating/service load conditions are similar to the ACl 318-71 Code Equation 9-2: U =0.75(1 .4D + 1 .7L + 1.7W) for use with the ultimate strength design method.The load combination for normal operating/service load conditions using the ultimatestrength method is a simple conversion to consider loads in combination with the floodload (F).2.6.2 Determination of Actual Concrete Compressive Strength Based on OriginalTest DataThe use of the actual concrete compressive strength based on 28-day test data in lieu ofthe original specified 4000 psi in design re-evaluations will resolve conditions foundduring the re-constitution efforts for the CIS. This includes shear overstress in beamsand axial strength of columns for normal operating/service and no loss-of-functionloading.
LIC-15-0 142EnclosurePage 232.6.3 Determination of Actual Reinforcing Steel Yield Strength Based on OriginalTest DataThe use of actual reinforcing steel yieid strength helps resolve bending overstresses inbeams. The use of 10% higher yield strength for reinforcing steel is limited toapproximately 1.65 standard deviations of the Certified Material Test Reports (CMTRs),which shows a high confidence level. The higher yield strength is restricted to the RC&Cand to the CIS. The increase in yield strength maintains design margin and its use indesign basis calculations is subject to the limitations previously noted.2.6.4 Limit Design Method and Use of Dynamic Increase FactorsUse of the limit design method and DIFs helps resolve overstress issues with the RC&C.Guidance for application of Dynamic Increase Factors (DIE) is included in ACI 349-97Appendix C and associated commentary. Regulatory Guide 1.142 provides furtherguidance and identifies restrictions. Specifically, DIE can be realized only when materialis subjected to high strain rates.2.6.5 Controllable FluidsThe clarifications associated with fluids are consistent with the standard approach toaddressing tanks and cavities that contain fluids.2.7 Evaluation of PLB Change to License Renewal and Aging ManagementIn Section 3.5 of the LRA (References 6.6 and 6.7 respectively), OPPD described itsaging management review (AMR) for structural components within the containment andother structures (i.e. Class I, Class II, etc.,) at ECS. The passive, long-lived componentsin these structures that are subject to an AMR were identified in LRA Tables 2.4.1-1 and2.4.2.1-1 through 2.4.2.7-1.OPPD's AMRs included an evaluation of plant-specific and industry operatingexperience. The plant-specific evaluation included reviews of condition reports anddiscussions with appropriate site personnel to identify aging effects requiring LIC-1 5-0142EnclosurePage 24management. These reviews concluded that the aging effects requiring management,based on FCS operating experience, were consistent with aging effects identified inNUREG-1 801, "Generic Aging Lessons Learned (GALL) Report," published July 2001.OPPD's review of industry operating experience included a review of operatingexperience through 2001. This review concluded that aging effects requiringmanagement based on industry operating experience were consistent with aging effectsidentified in the GALL Report. OPPD's ongoing review of plant-specific and industryoperating experience is conducted in accordance with the FCS operating experienceprogram.Revision 2 of NUREG-1801 was issued in December 2010. For Condition Report 2013-07171, Westinghouse performed a gap analysis of NUREG-1 801 Revision 0 versusRevision 2. Westinghouse noted that the standards referenced in Revision 2 of theGALL do not change the conclusions of the FCS topical reports developed for the LRAthat certain aging effects do not require aging management. Acceptable inspections ofaccessible areas have been performed.A Structures Monitoring Program (Reference 6.10) is implemented at FCS consisting ofperiodic inspection and monitoring of structures and structure component supports toensure that aging degradation leading to loss of intended functions will be detected andthat the extent of degradation can be determined. This program is implemented inaccordance with NEI 93-01, Revision 2, "Industry Guideline for Monitoring theEffectiveness of Maintenance at Nuclear Power Plants," and Regulatory Guide 1.160,Revision 2, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," tosatisfy the requirement of 10 CFR 50.65, "Requirements for Monitoring the Effectivenessof Maintenance at Nuclear Power Plants."FCS currently inspects the auxiliary building and containment internal structure perprocedures SE-PM-AE-1 001, Auxiliary Building Structural Inspection and SE-PM-AE-1004, Containment Building Structural Inspection. Each procedure has an inspectionfrequency of 3 years with caveats to increase or decrease the frequency as accumulatedinspection findings warrant, but shall not exceed 5 years. A review of the results fromrecent inspections did not identify any significant structural deterioration that wouldinvalidate the use of the CLB or PLB items requested by this LAR; the results LIC-1 5-0142EnclosurePage 25demonstrate satisfactory health of the structures in question.2.8 Analysis Supporting the License Amendment ChangesDetailed analysis is in progress to restore the 01S to design basis. The preliminaryresults of the beam evaluations based on CLB and PLB criteria suggest that a majorityof the CIS can be restored on the basis requested in this LAR. Table 8 below shows thepreliminary results from the CLB calculation prepared in 2012 compared to the analysisperformed to date while implementing the changes to the license basis (PLB). Using theCLB, 19 of the 22 total beams require modification. Using the PLB preliminary analysis,4 of the 22 total beams may require modification.Table 8 -Summary of IRs for CLB and PLB ConditionsCurrent License Basis Proposed License BasisCIS Beams (CLB) (PLB)USD IR with newWSD R US IR load factors (preliminary)Beams on Elevation 1013'B5-13 1.04 0.81 0.80-0.90B13-13 1.27 0.86 0.70-0.80B14-13 0.82 0.73 N/AB43-13 1.30 1.00 0.70-0.80B44-13 1.48 1.09 0.80-0.90B21-13 1.46 1.44 1.20-1.30B22a-13 1.65 2.47 1.20-1.30B22b-13 1.66 2.44 1.20-1.30B23-13 1.65 1.43 1.05-1.15B36-13 1.30 2.17 0.85-0.95B46b-13 1.05 1.19 0.80-0.90B27-13 1.12 0.92 0.70-0.80B29-13 2.45 2.38 0.80-0.90___________Beams on Elevation 1045'B812-45 1.90 1.75 [0.90-1.00B2l a-45 0.65 0.44 0.30-0.40 LIC-1 5-0142EnclosurePage 26Current License Basis Proposed License BasisCIS Beams (CLB) (PLB)USD IR with newWSD R US IR load factors (preliminary)B21lb-45 0.65 0.44 0.30-0.40B23-45 1 .32 0.81 0.75-0.85Beams on Elevation 1060'B56a-60 1.02 0.74 0.70-0.80B61a-60 1.19 1.20 0.90-1.00B61lb-60 1.16 1.18 0.90-1.00B64-60 0.88 1.11 0.60-0.70B65-60 1.15 0.93 0.90-1.00Notes1. The IRs presented in this table do not include reductions that result from modifications.2. The preliminary PLB analysis results (LAR methodology) presented in the table aboveinclude elimination of WSD, use of 44ksi reinforcing steel yield strength, use of 5440psiconcrete strength, and new load combinations 1 .4D+1l.7L and 1 .05D+1 .25(L+E).3. The IRs over 1.0 for beams B22a-13 and B22b-13 are being resolved in RFO28 to meetCLB conditions in accordance with the Regulatory Commitment made in OPPD letter LIC-15-0042. Remaining beams with PLB IRs greater than 1.0 will be resolved with futuremodifications depending on the results of the final analysis.Detailed analysis results have not been completed for the auxiliary building, RC&C, orintake structure. However, preliminary analysis indicate PLB conditions will minimize themodifications required to restore these structures to the design basis.2.9 Gap Analysis of ACI 318-63 to ACI 349-972.9.1 ScopeThe scope of the gap analysis is to compare ACI 349-97 to the COR and evaluate thedifferences between the two codes. The comparison looks specifically at the marginassociated with concrete design for applying DI~s and the limit design method to theRC&C.
LIC-1 5-0142EnclosurePage 27ACI 349-97 is based on ACI 318-89 (Revised 1992)- with an exception that Chapter 12is based on ACI 31 8-95.2.9.2 MethodologyA section-by-section comparison of the language and material between the strengthdesign provisions of ACI 349-97 and the original design basis working stress designmethod along with the ultimate strength design method of the ACI 318-63 wasperformed. Dissimilarities are summarized as follows:*Design load combinations (ACl 349-97, Chapter 9)--A~l 349-97 aligns codeprovisions by introducing nuclear safety-related load combinations regardingnormal, severe environmental, extreme environmental, and abnormal loads.However, the Fort Calhoun load combinations also apply ultimate strength loadfactors that are different but comparable to both Codes. In addition, the strengthreduction factors listed in the USAR are consistent with both Codes.Other differences were identified due to expanded or new provisions as follows:*Slenderness effects (ACI 349-97, Chapter 10) ACI 349-97 adds to the provisionsto account for member stiffness and moment magnification in computation ofsecond-order demand load effects.*Shear-friction considerations (ACI 349-97, Chapter 11) ACI 349-97 addsequations to introduce shear-friction reinforcement design provisions.*Special seismic requirements for steel reinforcing detailing (ACI 349-97, Chapter21) ACI 349-97 adds special detailing provisions for seismic that are not relatedto impactive or impulsive conditions.*Special provisions for thermal loading (ACI 349-97, Appendix A) ACI 349-97addresses the consideration of thermal stresses and thermal strains for bothnormal operating and thermal accident conditions.*Design of steel embedment (ACI 349-97, Appendix B) ACI 349-97 providesminimum requirements for design and anchorage of steel embedments to bring LIC-1 5-0142EnclosurePage 28consistency between ACI and AlSC practice and this is not related to impactiveor impulsive conditions for the RC&C walls.Special provisions for impulsive and impactive loadings (ACl 349-97, AppendixC) provides design provisions to account for time-dependent loads due tocollision of masses and those time-dependent loads not associated with collisionof finite masses, including the concept of dynamic strength increase (DIE), whichconcerns the strain rates of the load effects.Based on the review of the provisions of ACI 349-97 and an assessment of thedissimilarities to the A~l 318-63 Code, the provisions of the ACI 349-97, Appendix C arecompatible with the ACl318-63 design methodology for Fort Calhoun Station with regardto Dynamic Increase Factors.2.9.3 FindingsMost of the code sections that are presented in ACI 349-97 are similar to ACI 318-63and do not adversely affect the assessment of the design basis compared to the originallicense basis. There are technical aspects of ACI 349-97 that influence the structural re-evaluation of the existing FCS concrete structures and have been reconciled.2.9.4 ConclusionsBased on the comparison of ACI 349-97 Code and the dissimilarities to ACI 318-63 ithas been determined that use of DIF as described in ACI 349-97 and Regulatory Guide1.142 would be advantageous for re-evaluation of the RC&C. Use of the USDmethodology is adequate to evaluate the RC&C.
LIC-1 5-0142EnclosurePage 292.10 Quality Program During Construction and Quality of Material TestsThe quality program (Reference 6.25) was implemented at the Fort Calhoun Station during plantconstruction. The quality program contained detailed procedures for controlling installation ofsteel reinforcement and the concrete. Delivery of these materials required testing and recordsidentifying their placement within Class I structures. The records were maintained andtransmitted to OPPD (Reference 6.26) and include signoffs for each delivery, steelreinforcement test data, and the location where the steel reinforcement was placed in the ClassI structures. Concrete test records are available that accurately show test results and referencethe location in the Class I structures where the concrete was placed.Proper tracking and recording of material locations of concrete pours and location of steelreinforcement was emphasized during plant construction. For example, Reference 6.27 recordsa discussion confirming the requirements for controlling concrete. Reference 6.27 states:GHD&R [Gibbs, Hill, Durham, and Richardson] inspectors are to cover concrete placementcontinuously and by contact with PKS [Peter Kiewit Services] supervision that correct placementis being carried out continuously. This also involves remaining at the pour until satisfied thatfinishing and curing will be as specified.In conclusion, the installation of concrete and steel reinforcement during plant construction wascontrolled as documented in the numerous quality records. This gives high confidence that thematerials and installation methods used to construct the plant support the changes proposed inthis license amendment request.3.0 TECHNICAL EVALUATION3.1 Use Ultimate Strength Method for Normal Operating/Service ConditionsThe change from WSD to USD design methodology for concrete capacities within thesame ACI 318-63 Code is an appropriate change; see discussion in Section 1504 of ACI318-63, Publication SP-10 (Reference 6.16). The materials, construction, and detailingrequirements are unchanged. The ACI 318-63 Code included both working stressdesign and ultimate strength design methods just before the industry began phasing out LIC-1 5-0142EnclosurePage 30the application of working stress design for reinforced concrete in the 1960s. In 1971,the American Concrete Institute labeled working stress design as an alternate designmethod. In 1999, the American Concrete Institute completely removed the workingstress method from the ACl 318 Code.The current ECS structural design criteria for Class I structures specifies use of ACI 318-63 USD section capacities for extreme (i.e. no loss-of-function) conditions. Thisproposed amendment applies new factored load combinations for normaloperating/service conditions using the USD section capacities from the ACI 318-63Code.The proposed factored load combinations for normal conditions are required since USDdesign methodologies require factored loads in combinations that represent the normaloperating condition of the plant. The proposed load factors in the first revised loadcombination (1.4D + 1.7L) will be used for ultimate strength design to qualify thestructure for normal operating/service conditions and are consistent with those inEquation I in Section 9.2.1 of ACI 349-97 and are in accordance with the guidance ofSection 3.A. of SRP 3.8.4, Revision 4. The ACI 349-97 load factors are lower than thosespecified by the ACI 318-63 Code in the Section 1506 ultimate load combinationequation (15-1). Commercial nuclear plants in the United States do not commonly usethis load combination (i.e. 1.5D +1.8L) from the ACI 318-63 Code. The proposed loadfactors better reflect ultimate strength design behavior, see discussion in Section 9.3.1 ofACI 318R-71 (Reference 6.17).Load combinations are developed for normal operating/service conditions using the noloss-of-function ultimate strength design method equation from USAR Section 5.11 (i.e.D + 0.05D + 1.25 Pc + 1.25 E + 1.0 Tc)) by removal of Pc and Tc loads. Theseload combinations for normal load conditions are similar to the ACI 318-71 Codeequation 9-2: U = 0.75 (1.4 D + 1.7 L + 1.7 W) for use with the ultimate strength method.The factored load combination for normal load conditions using the ultimate strengthmethod are a simple conversion to consider loads in combination with the hydrostaticload (F).
LIC-1 5-0142EnclosurePage 313.2 Determination of Actual Concrete Compressive Strength Based on Original TestDataThe request to implement actual concrete compressive strength while meeting thetesting requirements in ACI 318-63 Code is substantiated because test strengths aresignificantly higher than the original design basis specified 4000 psi compressivestrength for Class B concrete. The use of actual concrete compressive strength appliesto concrete (not related to age hardening) as defined in Section 301 of ACI 318-63.Section 301 of ACI 318-63 states: "Compressive strength shall be determined by test ofstandard 6 x 12-in, cylinders made and tested in accordance with American Society forTesting and Materials (ASTM) specifications at 28 days or such earlier age as concreteis to receive its full service load or maximum stress." By definition, the ACI is concernedwith the age at which concrete receives its full load or maximum stress and therebyallowing the full load or maximum stress earlier than 28 days if validated by test data.Therefore, by implication, new or additional loads applied at a later date would beacceptable as long as test data validates the actual compressive strength.The ACI 318-63 Code is the CLB COR for the design and construction of reinforcedconcrete structures at FCS. Quality records from concrete pours at FCS as well asoriginal test data are available, and the data supports a higher actual concretecompressive strength above the minimum specified CLB COR 4000 psi value. The useof the actual 28-day properties from the results of compressive tests performed duringconstruction shall be permissible when it can be shown that (1) the samples taken forcompressive tests represent the structure being evaluated, and (2) the value selected isderived from a statistical analysis indicating high confidence level. The actual concretestrength will be established using analysis of original lab test data meeting the testingrequirements of ACI 318-63. The data analysis method to be used is described inSection 2.2 of this document.Application of the actual concrete strength will be limited to areas in the auxiliary buildingand containment internal structures that are not exposed to excessive moisture, highradiation, or harsh chemicals for prolonged periods.
LIC-1 5-0142EnclosurePage 323.3 Determination of Actual Reinforcing Steel Yield Strength Based on Original TestDataQuality records show that there were 115 heat code samples used in the construction ofthe CIS. Some of the heat code yield stress values could not be identified and 105 ofthe 115 samples are known. Based on 105 samples specifically used for CIS, the 95%confidence level is equal to 44.45 ksi. As a result, the current design steel yield strength(i.e. 40 ksi) is increased to 44 ksi with high confidence for the RC&C and for CIS(Reference 6.14).3.4 Use of Dynamic Increase Factors (DIF) and Limit Design for RC&CThe request to allow the inclusion of the Limit Design Method is required because thereis no equivalent method in the ACI 318-63 Code. The original design of the reactorcavity and compartment walls (RC&C walls) was based on the limit state of thereinforced concrete structure. Design forces and moments at the limit state, which wereused to determine sizes and placements of reinforcing bars (rebar), cannot be replicatedby any form of linear finite element analysis, herein called the Linear Design Method.They can only be computed by using non-linear (or step-wise linear) finite elementanalysis, herein called the Limit Design Method. While the Limit Design Method is ableto reasonably reproduce the original design forces and moments at the limit state bysimulating load redistribution behavior, the Linear Design Method is not.When the Limit Design Method is applied, where flexure controls design of the RC&Cwalls, rotations of the walls in any yield zone must be less than the rotational capacity ofthe zone, as expressed by Equations 3.4.1 and 3.4.2 in Section 0.3.4 of ACl 349R-97Appendix C (ACI 349-97 Commentary). It is important to note that the Limit DesignMethod applies to all load combinations applicable to the RC&C walls.The request to allow the inclusion of dynamic increase factors (DIE) is required becausethere are no equivalent factors in the ACl 318-63 Code. Accidental pressure loads resultfrom high-energy line breaks inside the RC&C walls. Because of their impulsive natureand rapid strain rates that occur in structural elements under them, both the concreteand reinforcing steel will exhibit strengths higher than those under static loading LIC-15-0142EnclosurePage 33conditions. DI~s represent the ratio of dynamic to static strengths. OPPD requests thatDI~s may be utilized as specified in Section C.2.1 of ACI 349-97 Appendix C. Asrestricted in Regulatory Guide 1.142 (Reference 6.23), DI~s will not be used if dynamicload factors (DLF) are less than 1.2. It is important to note that DIFs apply only tocompartmental pressures.The application of the limit design method and DIFs is similar to the guidance in BechtelPower Corporation Topical Report BC-TOP-9A "Design of Structures for Missile Impact",Revision 2 (Reference 6.21), which was recently approved (Reference 6.22) for FortCalhoun Station.3.5 Clarification of Hydrostatic Load in the USAR Section 5.11The controlled hydrostatic load is changed from live load to dead load for ultimatestrength design in the definition. The definition for dead load was improved by clarifyingthat controllable fluids are considered dead load instead of a live load. This is consistentwith ACI-349-97.4.0 REGULATORY EVALUATION4.1 Applicable Regulatory Requirements/CriteriaFort Calhoun Station was licensed for construction prior to May 21, 1971, and at thattime committed to the draft General Design Criteria (GDC). The draft GDC arecontained in Appendix G of the Fort Calhoun Station USAR and is similar to 10 CFR 50,Appendix A, General Design Criteria for Nuclear Power Plants. The draft GDC mostpertinent to this request are USAR Appendix G, Criterion 2, Performance Standards andUSAR Appendix G, Criterion 10, which pertains to the containment building. Criteria 2and 10 as described in USAR Appendix G are shown below.CRITERION 2 -PERFORMANCE STANDARDSThose systems and components of reactor facilities which are essential to the preventionof accidents which could affect public health and safety or to mitigation of their LIC-15-0 142EnclosurePage 34consequences shall be designed, fabricated, and erected to performance standards thatwill enable the facility to withstand, without loss of the capability to protect the public, theadditional forces that might be imposed by natural phenomena such as earthquakes,tornadoes, flooding conditions, winds, ice and other local site effects. The design basesso established shall reflect: (a) Appropriate consideration for the most severe of thesenatural phenomena that have been recorded for the site and the surrounding area and(b) an appropriate margin for withstanding forces greater than those recorded to reflectuncertainties about the historical data and their suitability as a basis for design.This criterion is met. The systems and components of the Fort Calhoun Station, Unit No.I reactor facility that are essential to the prevention or mitigation of accidents that couldaffect public health and safety are designed, fabricated, and erected to withstand withoutloss of capability to protect the public, the additional forces that might be imposed bynatural phenomena such as earthquakes, tornadoes, floods, winds, ice and other localsite effects.The containment will be designed for simultaneous stresses produced by the dead load,by 60 psig internal pressure at the associated design temperature, and by theapplication of forces resulting from an earthquake whose ground motion is 0. 08ghorizontally and 0. 053g vertically. Further, the containment structure will be designed towithstand a sustained wind velocity of 90 mph in combination with the dead load anddesign internal pressure and temperature conditions. The wind load is based on thehighest velocity wind at the site location for 100-year period of recurrence: 90 mph basewind at 30 feet above ground level. Other Class I structures will be designed similarlyexcept that no internal pressure loading is applicable. Class I systems will be designedfor their normal operating loads acting concurrently with the earthquake describedabove.The containment structure is predicted to withstand without loss of function thesimultaneous stresses produced by the dead load, by 75 psig internal pressure andtemperature associated with this pressure and by an earthquake whose ground motionis 0. lOg horizontally and O.07g vertically.The containment structure is predicted to withstand without loss of function 125% of the LIC-15-0 142EnclosurePage 35force corresponding to a 90 mph wind impinging on the building concurrently with thestresses associated with the dead load and 75 psig internal pressure.With no earthquake or wind acting, the structure is predicted to withstand 90 psiginternal pressure without loss of function.Under each of these conditions, stresses in the structural members will not exceed 0.95yield.The facility is designed so that the plant can be safely shutdown and maintained in asafe shutdown condition during a tornado. Design considerations associated withtornadoes are further explained in Section 5.4.7 of the USAR.Flooding of Fort Calhoun Station, Unit No. 1 is considered highly unlikely. Furtherinformation is available in USAR Section 2. 7.1.2.CRITERION 10- CONTAINMENTContainment shall be provided. The containment structure shall be designed to sustainthe initial effects of gross equipment failures, such as a large coolant boundary break,without loss of required integrity and, together with other engineered safety features asmay be necessary, to retain for as long as the situation requires the functional capabilityto protect the public.This criterion is met. The containment structure is designed to sustain the initial effectsof gross equipment failures, such as a large reactor coolant boundary break, without lossof required integrity and, together with other engineered safety features as necessary, toretain for as long as necessary, the functional capability to protect the public.The containment building is designed to withstand an internal pressure of 60 psig at305°F including all thermal loads resulting from the temperature associated with thispressure with a leakage rate of 0.2% or less of the contained volume per 24 hours andwill be subject to a leak rate and pressure test to demonstrate compliance with thedesign.
LIC-1 5-0142EnclosurePage 36The changes proposed by this LAR will continue to ensure that Criterion 2 and Criterion10 are met.The USD method is an appropriate method for reinforced concrete design. Qualityrecords list original test data for specific pour locations. This data supports usingconcrete compressive strength based on actual 28-day test data (not age hardening) inlieu of the original specified value of 4,000 psi for Class B concrete. Application of theactual compressive strength will be limited to areas in the auxiliary building andcontainment internal structures where the concrete is not exposed to excessivemoisture, high radiation, or harsh chemicals for prolonged periods. The 10% increase inyield strength is supported by statistical analysis of the original test data.Inclusion of the Limit Design Method and dynamic strength increase factors (DIE) fills agap in the ACI 318-63 Code. The proposed application is similar to the guidance inBechtel Power Corporation, Topical Report BC-TOP-9A, "Design of Structures forMissile Impact," Revision 2, approved for use in the evaluation of tornado missileimpacts by Amendment No. 272. The DIFs will be utilized as specified in ACI 349 C.2.1and will not be used if dynamic load factors (DLF) are less than 1.2. ACI 349-97,Appendix C is an accepted design code used in the Nuclear Industry.4.2 PrecedentThe ACI 318-63 Code was used for the design of nuclear power plants constructed inthe era that Fort Calhoun Station was built. Operating nuclear power plants licensed touse the ACI 31 8-63 ultimate strength design method for normal operating/service loadcombinations include the following sites:* Arkansas Nuclear One (ANO)* Calvert Cliffs* Turkey Point* Watts Bar* WaterfordFurthermore, ANO, Calvert Cliffs, and Waterford were designed using the same LIC-1 5-0142EnclosurePage 37proposed 1.25 load factor on operating-basis earthquake (OBE) seismic level loads intheir normal operating/service load combinations for the USD method.The licensing of ACl codes has also evolved at other nuclear plants. For example,Section 3.8.5.4.2 of the Watts Bar Updated Final Safety Analysis Report (UFSAR)describes the auxiliary-control building as designed in compliance with the ACl 31 8-63Code. However, Appendix 3.8E of the Watts Bar UFSAR shows that the current code isthe ACI 318-77 Code for the modification and evaluation of existing structures and fordesign of new features added to existing structures and the design of structures initiatedafter July 1979.The use of dynamic strength increase factors (DIF) are specified in Section 0.2.1 of ACl349-97 and is a method previously endorsed by the NRC in SRP 3.8.4 and RG 1.142.The ACI 318-63 Code is the current licensing basis code of record at FCS. Use ofactual concrete compressive strength applies to concrete meeting the strength testingrequirements of Section 504 in ACI 318-63.4.3 No Significant Hazards ConsiderationThis License Amendment Request (LAR) proposes to revise Fort Calhoun Station (FCS)Unit No. 1, Updated Safety Analysis Report (USAR), Section 5.2 "Structure Materials ofConstruction," and Section 5.11 "Design Criteria -Class I Structures." The proposedamendment seeks to change structural design criteria and methodology used for thedesign or re-evaluation of Class I structures at FCS.The Omaha Public Power District (OPPD) has evaluated whether or not a significanthazards consideration is involved with the proposed amendment(s) by focusing on thethree standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussedbelow:
L-IC-5-0142EnclosurePage 381. Does the proposed amendment involve a significant increase in the probabilityor consequences of an accident previously evaluated?.Response: No.This LAR revises the methodology used to design new or re-evaluate existing Class Istructures other than the containment structure (cylinder, dome, and base mat), thespent fuel pool (SFP), and the foundation mats. These structures will continue toutilize the current license basis and thus are not affected by this change. Theproposed change allows other Class I structures to apply the ultimate strengthdesign (USD) method from the ACI 318-63 Code for normal operating/service loadcombinations.The ACI USD method is an accepted industry standard used for the design andanalysis of reinforced concrete. A change in the methodology that an analysis usesto verify structure qualifications does not have any impact on the probability ofaccidents previously evaluated. Designs performed with the ACI USO method willcontinue to demonstrate that the Class I structures meet industry accepted ACI Coderequirements. This LAR does not propose changes to the no loss-of-function loads,loading combinations, or required ultimate strength capacity.Calculations that apply the limit design method and use dynamic increase factors(DIF) of ACI 349-97, Appendix C will demonstrate that the concrete structures meetrequired design criteria. Therefore, these proposed changes will not pose asignificant increase in the probability or consequences of an accident previouslyevaluated.The use of actual concrete strength based on original test data for the areasidentified in Section 2.2 of this document and the use of 10% higher steel yieldstrength for the reactor cavity and compartment (RC&C) and containment internalstructures (CIS) maintain adequate structural capacity. As such, these proposedchanges do not pose a significant increase in the probability or consequences of anaccident previously evaluated because the revised strength values are determinedbased on actual original test data using a high level of confidence.
LIC-1 5-0142EnclosurePage 39The controlled hydrostatic load is changed from live load to dead load for ultimatestrength design in the definition. This is consistent with ACI-349-97 and thereforedoes not pose a significant increase in the probability or consequences of anaccident previously evaluated.Therefore, the proposed changes do not involve a significant increase in theprobability or consequences of an accident previously evaluated.2. Does the proposed amendment create the possibility of a new or different kindof accident from any accident previously evaluated?Response: No.This LAR proposes no physical change to any plant system, structure, or component(SS0). Similarly, no changes to plant operating practices, operating procedures,computer firmware, or computer software are proposed. This LAR does not proposechanges to the design loads used to design Class I structures. Application of thenew methodology to the design or evaluation of Class I structures will continue toensure that those structures will adequately house and protect equipment importantto safety.Calculations that use the ACI USD method for normal operating/service loadcombinations will continue to demonstrate that the concrete structures meet requireddesign criteria. Calculations that apply the limit design method and use dynamicincrease factors (DIE) of ACI 349-97, Appendix C will demonstrate that the concretestructures meet required design criteria. Use of the actual compressive strength ofconcrete based on 28-day test data (not age hardening) is permitted by the ACI 318-63 Code and ensures that the concrete structure is capable of performing its designfunction without alteration or compensatory actions of any kind. A 10% higher steelyield has minimal reduction on design margin for the RC&C or the CIS. Thecontrolled hydrostatic load is changed from live load to dead load for ultimatestrength design in the definition which is consistent with ACI-349-97.
LIC-1 5-0142EnclosurePage 40The use of these alternative methodologies for qualifying Class I structures does nothave a negative impact on the ability of the structure or its components to house andprotect equipment important to safety and thus, does not create the possibility of anew or different kind of accident from any previously evaluated.3. Does the proposed amendment involve a significant reduction in a margin ofsafety?Response: No.The proposed change is for the design of new or re-analysis of existing Class Istructures with the exception of the containment structure, the spent fuel pool, andthe foundation mats for which no change to the current licensing basis (CLB) isproposed.Utilization of the ACI 318-63 Code USD method applies only to the normaloperating/service load cases and is already part of the CLB for no loss-of-functionload cases. No changes to design basis loads are proposed; therefore, new designsor re-evaluations of existing Class I structures shall still prove capable of coping withdesign basis loads.Use of the actual compressive strength of concrete based on 28-day test data (notage hardening) is justified and further constrained by limiting its application to areaswhere the concrete is not exposed to harsh conditions. ACI 349-97, Appendix C isan accepted design code used in the nuclear industry. Calculations using DI~s perACI 349-97, Appendix C must demonstrate that the Class I structures continue tomeet an appropriate design code widely used in the nuclear industry. The use of a10% higher steel yield was conservatively derived from original test data and hasminimal reduction on design margin for the RC&C or the CIS. The controlledhydrostatic load is changed from live load to dead load for ultimate strength design inthe definition which is consistent with ACI-349-97.Therefore, the proposed changes do not involve a significant reduction in a margin ofsafety.
LIC-1 5-0142EnclosurePage 41Based on the above, OPPD concludes that the proposed amendment presents nosignificant hazards consideration under the standards set forth in 10 CER 50.92(c), and,accordingly, a finding of "no significant hazards consideration" is justified.4.4 ConclusionIn conclusion, based on the considerations discussed above, (1) there is reasonableassurance that the health and safety of the public will not be endangered by operation inthe proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical tothe common defense and security or to the health and safety of the public.5.0 ENVIRONMENTAL CONSIDERATIONA review has determined that the proposed amendment would change a requirementwith respect to installation or use of a facility component located within the restrictedarea, as defined in 10 CFR 20, or would change an inspection or surveillancerequirement. However, the proposed amendment does not involve (i) a significanthazards consideration, (ii) a significant change in the types or significant increase in theamounts of any effluent that may be released offsite, or (iii) a significant increase inindividual or cumulative occupational radiation exposure.Accordingly, the proposed amendment meets the eligibility criterion for categoricalexclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51 .22(b), noenvironmental impact statement or environmental assessment need be prepared inconnection with the proposed amendment.6.0 REFERENCES6.1 Fort Calhoun Station Unit I Updated Safety Analysis Report (USAR) Section5.11, "Structures Other Than Containment"6.2 Fort Calhoun Station Unit 1 Updated Safety Analysis Report (USAR) Section 5.2"Materials of Construction"6.3 Fort Calhoun Station Unit 1 Updated Safety Analysis Report (USAR) Section 5.5, LIC-1 5-0142EnclosurePage 42"Containment Design Criteria"6.4 Letter from NRC (S. Bloom) to OPPD (T. L. Patterson), "Fort Calhoun Station,Unit No. 1 -Amendment No. 155 to Facility Operating License No. DPR-40 (TACNo. M851 16)," dated August 12, 1993 (NRC-93-0292)6.5 ACI 318-63, Building Code Requirements for Reinforced Concrete, AmericanConcrete Institute6.6 Letter from OPPD (W. G. Gates) to NRC (Document Control Desk), "FortCalhoun Station Unit 1 Application for Renewed Operating License," datedJanuary 9, 2002 (LIC-02-0001) (ML020290333)6.7 Letter from OPPD (R. P. Clemens) to NRC (Document Control Desk), "FortCalhoun Station Unit I Revised Application for Renewed Operating License,"dated April 5, 2002 (LIC-02-0042)6.8 Letter from NRC (R. K. Anand) to OPPD (R. T. Ridenoure), "Issuance ofRenewed Facility Operating License No. DPR-40 Fort Calhoun Station, Unit 1,"dated November 4, 2003 (NRC-03-0209) (ML033040033)6.9 Letter from NRC (M. Hay) to OPPD (L. P. Cortopassi), "Fort Calhoun -NRCIntegrated Inspection Report Number 05000285/2014007," dated May 14, 2014(NRC-i14-0053) (ML14134A410)6.10 Program Basis Document (PBD)-42, "Structures Monitoring," Revision 46.11 ACI 349-97, Code Requirements for Nuclear Safety Related Concrete Structures,American Concrete Institute6.12 NUREG-0800, Standard Review Plan, Section 3.8.4, "Other Seismic Category IStructures," Rev. 4, 09/20136.13 ACI 318-71, Building Code Requirements for Reinforced Concrete, AmericanConcrete Institute6.14 DIT-SA-13-005, "Use of Higher Reinforcement Yield Strength for OperabilityCalculations"6.15 ACI 214-65, Recommended Practice for Evaluation of Compression Test Resultsof Field Concrete, American Concrete Institute.6.16 ACI 31 8-63, Publication SP-10, Commentary on Building Code Requirements forReinforced Concrete, American Concrete Institute6.17 ACI 318R-71, Commentary on Building Code Requirements for ReinforcedConcrete, American Concrete Institute6.18 Not Used.6.19 Not Used.
LIC-15-0 142EnclosurePage 436.20 Not Used.6.21 Not Used.6.22 Regulatory Guide 1.142, "Safety-Related Concrete Structures for Nuclear PowerPlants (Other than Reactor Vessels and Containments)," Rev. 2, November 20016.23 Not Used.6.24 Quality Assurance Program (WIP 008372).6.25 Quality Assurance Records Transmittal For Batch Documents Number 83-268(WIP 5932), Dated June 17, 19836.26 Letter from J. Woolsey to OPPD (J. Gassman, C. Murphy, F. Wittlinger, C. Mann)"Concrete Control," dated February 5, 1969 (WIP 013439)
LIC-1 5-0142Enclosure, Attachment 1Page 1Fort Calhoun Station, Unit No. IRenewed Facility Operating License No. DPR-40Mark-up of Updated Safety Analysis ReportSection 5.2Section 5.11 Page 1 of 13USAR-5.2I1StructuresMaterials of ConstructionRev 8Safety Classification:II Safety IUsage Level:II Information IChange No.:Reason for Change:Preparer:Issued:Fort Calhoun Station USAR-5.2 Information Use Page 2ofl13Materials of Construction Rev. 8Table of Contents5.2 Materials of Construction ...................................................................... 45.2.1 Concrete............................................................................... 45.2.2 Reinforcing Steel and Cadweld Splices............................................. 75.2.2.1 Reactor Cavity and Compartments and Maintenance Activities ........ 75.2.3 Prestressing Post-Tensioning System .............................................. 75.2.3.1 Description................................................................... 75.2.3.2 Material Properties.......................................................... 85.2.3.3 Corrosion Protection ........................................................ 95.2.4 Liner Plate and Penetrations......................................................... 95.2.5 Protective Coatings and Paints Inside the Containment ......................... 115.2.6 Compressive Test Strength of Concrete........................................... 12 USAR-5.2Materials of ConstructionInformation UsePage 3 of 13Rev. 8List of TablesTable 5.2-2 -Concrete Mix Compositions........................................................... 6 USAR-5.2 Information Use Page 4of 13Materials of Construction Rev. 85.2 Materials of ConstructionThe basic specifications for the primary structural elements of containmentconstruction are presented in Sections 5.2.1 through 5.2.4. During the Nuclear SteamSupply System Refurbishment Project (NSSSRP) in 2006, a temporary opening wasprovided in the cylindrical wall for the entry of major equipment components into thecontainment. The NSSSRP construction opening is described in Section 5.3.6.5.2.1 ConcreteConcrete for the NSSSRP construction opening is described in Section 5.3.6.IngqredientsCement conformed to ASTM C150 Type II with low alkali content. Themaximum alkali content calculated as sodium oxide was limited to0.50 percent.The air entraining agent used was "MBVR" (Master Builders Vinsol Resin).This material conformed to ASTM C260.The water reducing agent used was "Pozzolith Low Heat" as manufacturedby the Master Builders Co. This material conformed to ASTM C494 Type A.Fine aggregate is Platte River Valley sand gravel with 1/4 inch maximumsize.Coarse aggregate consists of 1-1/2 inch crushed limestone (3/4 inch forspecial limited applications) from the Plattsmouth ledge at Weeping Water,Nebraska.The aggregate materials conformed substantially to ASTM C33, except forminor variations in gradation. The aggregate mix was based on therequirements of the Nebraska Standard Specifications for HighwayConstruction, modified slightly in accordance with local practice.Investigqation ProgqramThe aggregates for use in the concrete mix were tested for acceptability.The tests were performed by the Omaha Testing Laboratory of Omaha,Nebraska, in accordance with the then current editions of the following ASTMstandards:a. ASTM C40, Organic Impurities in Sands for Concrete;b. ASTM C75, Sampling Stone, Slag, Gravel, Sand and Stone Block for Useas Highway Materials; USAR-5.2 Information Use Page 5 of 13Materials of Construction Rev. 8c. ASTM C87, Effect of Organic Impurities in Fine Aggregate on Strength ofMortar;d. ASTM 088, Soundness of Aggregates by Use of Sodium Sulfate orMagnesium Sulfate;e. ASTM 0117, Materials Finer than No. 200 Sieve in Mineral Aggregate byWashing;f. ASTM 0123, Lightweight Pieces in Aggregate;g. ASTM 0127, Specific Gravity and Absorption of Coarse Aggregate;h. ASTM C128, Specific Gravity and Absorption of Fine Aggregate;i. ASTM Cl131, Resistance to Abrasion of Small Size Coarse Aggregate byUse of the Los Angeles Machine;j. ASTM 0136, Sieve or Screen Analysis of Fine and Coarse Aggregates;k. ASTM 0142, Clay Lumps in Natural Aggregates;I. ASTM 0235, Scratch Hardness of Coarse Aggregate Particles;m. ASTM 0289, Potential Reactivity of Aggregates;n. ASTM 0295, Petrographic Examination of Aggregates for Concrete;o. ASTM 0324, Potential Volume Change of Cement AggregateCombinations.
USAR-5 .2Materials of ConstructionInformation UsePage 6 of 13Rev. 8MixesThe design and associated tests of concrete mixes was also performed bythe Omaha Testing Laboratory. Concrete strengths were predicated on thebasis of ACI-301, "Specification for Structural Concrete for Buildings",Section 308, Method 2 for Ultimate Strength Type Concrete and PrestressedConcrete.The basic concrete mixes evolved and utilized for construction are shown inTable 5.2-2.Table 5.2-2 -Concrete Mix CompositionsApplicationAggregate Size, inCompressive Strength, psiat 28 daysWater-Cement Ratio, gals,max/sackCement Content, max sacks!cu. yd.Aggregate Proportions, %Sand GravelCrushed LimestoneAir Content, %Pozzolith Low Heat, Ibs/sack cementSlumps, in, maximumDensity, lb/cu. ft, minimumContainmentMat & Shell1-1/2Special LimitedApplications*3/450004.256.2550004.007.0050++/-350++/-34.75 + 0.7550+/-350+/-34.75 + 0.750.231450.23145*This mix was a special mix utilizing 3/4 in. maximum crushed limestone forspecial limited applications where the density of reinforcement and difficultyof ensuring good placement of 1-1/2 in. aggregate concrete warranted itsuse. Its application has been restricted to the portion of the structure in theimmediate vicinity of the anchorages for the helical tendons.
USAR-5.2 Information Use Page 7 of 13Materials of Construction Rev. 85.2.2 Reinforcing Steel and Cadweld SplicesReinforcing Steel and Cadweld Splices for the NSSSRP constructionopening are described in Section 5.3.6.3.Reinforcing steel in the foundation mat consists of deformed billet steel barswhich conformed to ASTM A615, Grade 60. This steel has a minimum yieldstrength of 60,000 psi, minimum tensile strength of 90,000 psi, and aminimum elongation of 7 percent in an 8 inch specimen.Reinforcing steel in the cylindrical wall, the domed roof and around openingsis deformed billet steel which conformed to ASTM A615, Grade 40. Thissteel has a minimum yield strength of 40,000 psi, minimum tensile strength of70,000 psi, and a minimum elongation of 7 percent in a 8 inch specimen.Splices for reinforcing steel conformed to the requirements of AClCode 318-63. Splices for bar sizes No. 11 and smaller were lapped except atcertain locations such as at the construction openings. Splicing for bars atthese locations and for all bar sizes larger than No. 11 was accomplished byapproved positive connectors, specifically Cadweld "T" series connectors,(as manufactured by Erico Products Incorporated of Cleveland, Ohio),designed to develop the specified tensile strength of the reinforcing steel.No reinforcing steel strength or tack welding was permitted.5.2.2.1 Reactor Cavity and Compartments and Maintenance ActivitiesFor the reactor cavity and compartments. the yield strength (Fy' of reinforcingsteel is based on testing in accordance with ASTM Standards. Historicallaboratory test data of Grade 40 steel reinforcement used in the constructionof Fort Calhoun Station Class I structures indicate that the yield strength testresults exceed the material specification values used in the original design.Statistical analysis of Certified Material Test Repo rts (CMTR' for the CISconfirms the 95% confidence yield strength for Grade 40 reinforcing steel tobe 44 ksi. This is applicable to the reactor cavity and compartments andraises the yield strength from 40 ksi to 44 ksi.The higher reinforcing steel strenath is also used to evaluate the containmentinternal structure beams, slabs, and columns.5.2.3 Prestressing Post-Tensioning SystemSection 5.3.6.4 describes the prestressing system and the NSSSRPconstruction opening.5.2.3.1 Description USAR-5.2 Information Use Page 8 of 13Materials of Construction Rev. 8The prestressing system is the 90 wire BBRV system as furnishedby the Inland-Ryerson Construction Products Company.Each tendon consists of 90 parallel 1/4 inch diameter high tensilecold drawn, stress relieved wires. Each end of the tendonterminates in an anchorage assembly which transfers the tendonforce to the concrete structure. Positive anchorage of the wireends is achieved with 3/8 inch diameter button heads, cold formedat the wire ends.The anchorage system consists of:a) A stressing head on one end of the tendon and a stressinghead/shim nut combination on the other end of the tendon:The cold formed button head on the tendon wire endtransmits the tendon force to the stressing head. Thestressing head or stressing head/shim nut is engagedthrough the external buttress threads by a hydraulicstressing device which induces the desired force in thetendon.b) A set of split tube shims: These shims are installed betweenthe stressing head or stressing head/shim nut and thebearing plate; they maintain the strain induced in the tendonand transmit the tendon force from the stressing head to thebearing plate.c) A bearing plate to transfer the tendon force to the concretesurface.The tendons were installed in the concrete structure in steelconduits, rigid or semi-rigid depending on location, and fullyinterlocked and completely sealed from terminal to terminalagainst leakage of mortar into the conduit.5.2.3.2 Material PropertiesTendon wire was cold drawn and stress relieved, with a minimumultimate strength of 240,000 psi. Each 90 wire tendon has aminimum ultimate strength of 1,060,000 pounds and a minimumyield strength of 848,000 pounds.Anchor components were designed to work within their elasticrange up to a load equal to the ultimate strength of the tendon,except for the plastic seating of the button heads.Governing prestressing material specifications were as follows:
USAR-5.2 Information Use Page 9 of 13Materials of Construction Rev. 8a) Tendon wires: ASTM A421, Type BA;b) Bearing plate: ASTM A36, (Fine Grained Practice);c) Anchor head: AISI 1141 Special Quality;d) Bushing: HFSM Tubing AISI 1045 or AISI 4140;e) Shims: HFSM Tubing AISI 1026;f) Tendon sheathing:1. Rigid: 4 inch 0.0., 14 gage and 3 gage flash controlledwelded tubing;2. Semi-rigid: 3-3/4 inch 1.0. 22 gage spirally formed fromsteel strip with interlocked seam.5.2.3.3 Corrosion ProtectionTendons were prepared at the factory for shipping by applicationof a coating of a thin-filmed temporary corrosion inhibitor. Eachtendon was then coiled and enclosed in a plastic bag, and4 ounces of Shell No. 250 VPI (vapor phase inhibitor) powder wasdusted into each bag. Each bag was then sealed and shipped tothe job site.The temporary corrosion inhibitor contained not more than 10 ppmeach of chlorides, nitrates and sulfides. It was designed to adhereto the tendon during installation in the structure and to providecorrosion protection under the prevalent field conditions.The permanent corrosion protection system subsequently appliedto the tendons was manufactured and supplied by the samemanufacturer and has the same chemical restrictions as thetemporary corrosion inhibitor to ensure that all materials used inthe compounding of both systems were compatible.The exposed portion of the bearing plates, which are located inthe stressing galleries and receive the tendon stress, were coatedwith grease after final tendon installation to prevent rusting.5.2.4 Liner Plate and PenetrationsLiner plate for the NSSSRP construction opening is described inSection 5.3.6.2.
USAR-5.2 Information Use Page 10 of 13Materials of Construction Rev. 8The liner plate is 1/4 inch in thickness. The materials specified for thevarious components of the containment liner are in accordance with thefollowing:a. Liner plate at the foundation mat and within the recess below the reactorconformed to ASTM A51 6, Grade 60, except that Charpy vee-notchimpact tests in accordance with the ASME Boiler and Pressure VesselCode, Section III, Class B vessels, were performed at a maximumtemperature of 0°F.b. Material for the cylinder and dome liner plate, for embedded structuralshapes and stiffeners, for test channels, for reinforcing plates aroundpenetrations, for personnel air lock internals and for the polar crane, withexception of the thickened liner plate, conformed to ASTM A36.c. The thickened liner plate at the crane supports conformed to ASTMA516, Grade 60. In addition these plates meet and in special areasexceeded the requirements of ASTM A435 for ultrasonic testing.d. Plate for the personnel air lock barrel, bulkhead and doors, and for theequipment hatch barrel and cover and surrounding reinforcing plates,conformed to ASTM A516, Grade 60, manufactured to ASTM A300requirements, except that Charpy vee-notch impact tests were inaccordance with the ASME Boiler and Pressure Vessel Code, Section III,Class B vessels, and were performed at a maximum temperature of 0°F.e. Material for penetration sleeves conformed to ASTM A333, Grade 1, forseamless pipe and ASTM A516, Grade 60, manufactured to ASTM A300requirements for pipe formed from rolled plate, except that Charpyvee-notch impact tests were in accordance with the ASME Boiler andPressure Vessel Code Section III, Class B vessels, and were performedat a maximum temperature of 0°F.f. Bolting materials for the equipment hatch cover conformed to ASTMA320.g. Material for forged flanges conformed to ASTM A350 except for impacttest requirements; material for flanges fabricated from plate conformed toASTM A516, Grade 60, manufactured to ASTM A300 requirements.Charpy vee-notch impact tests were in accordance with the ASME Boilerand Pressure Vessel Code Section III, Class B vessels, and wereperformed at a maximum temperature of 0°F.h. Pipe for pressure connections to the test channels over liner seam weldsinaccessible for inspection conformed to ASTM Al106, Grade B.
USAR-5.2 Information Use Page 11 of 13Materials of Construction Rev. 8Materials for penetrations and openings which must resist full designpressure conformed to the requirements of the ASME Boiler and PressureVessel Code, Section III, Class B vessels. NDT considerations wereaccounted for in paragraph N-I1211 a, ASME Boiler and Pressure VesselCode, Section III, which required that Charpy V-specimens be tested at atemperature at least 30°F lower than the lowest service metal temperature inaccordance with the requirements of paragraphs N-331, N-332, N-51 1.2 andN-5I15. The lowest service metal temperature for penetrations within thecontainment is 50°F. All those penetrations projecting outside thecontainment are located within the enclosure provided by the auxiliarybuilding; the lowest service metal temperature for these penetrations is 50°F.5.2.5 Protective Coatings and Paints Inside the ContainmentProtective coatings for the NSSSRP construction opening are described inSection 5.3.6.2.ConstructionCoatings used within the containment were specified to withstand accidentconditions. The applicable requirements of ANSI NIO01.4-1 972, QualityAssurance for Protective Coatings Applied to Nuclear Facilities, andRegulatory Guide (RG) 1.54, Revision 0, Quality Assurance Requirementsfor Protective Coatings Applied to Water Cooled Nuclear Power Plants, wereimplemented for modification activities and meet or exceed original plantspecifications and manufacturer recommendations.Most carbon steel original equipment has prime coats of Carbozinc orCarboweld and finish coats of Phenoline 305, all products of the CarbolineCorporation. The Safety Injection Tanks were primed with DuPont Corlar825-8031 epoxy zinc chromate primer number 583 while the PressurizerQuench Tank was primed with DuPont number 773 Dulux zinc chromateprimer. Documentation that all primers and top coats stated above have beentested or are acceptable for their service applications is shown by CarbolineCorporation and DuPont specifications and test sheets.Concrete inside the containment was treated with Amercoat Nu-Klad 1100OAand top coated with Amercoat No. 66. Testing has proven this type ofcoating to be adequate under accident conditions.Some minor components such as instrument housings and electricalcabinets have proprietary coatings, mostly baked enamels. The total area socoated, however, is very small compared to the total surface area.
USAR-5.2 Information Use Page 12 of 13Materials of Construction Rev. 8Maintenance and ModificationCoating materials currently used for maintenance of existing surfaces or forsurfaces of new modifications installed inside the reactor containment areepoxy materials tested to withstand Fort Calhoun design basis accident(i.e., loss of coolant accident (LOCA)) conditions. The coating materials andtheir application comply with the requirements of RG 1.54. Each coating wastested in accordance with ANSI NI101.2, Protective Coatings (Paints) forLight Water Nuclear Reactor Containment Facilities, or ASTM D391 1,Evaluating Coatings Used in Light-Water Nuclear Power Plants at SimulatedDesign Basis Accident (DBA) Conditions, to conditions that bound the FortCalhoun DBA conditions. Prior to exposure to the simulated DBA conditions,each coating test panel was irradiated to an accumulated dose of at least1.8 x 108 Rads in accordance with ASTM D4082, Standard Test Method forEffects of Gamma Radiation on Coatings for Use in Light-Water NuclearPower Plants.Use of the above coatings precludes the possibility of large flaking orskinning off of sheets of paint during accident conditions. Since the only wayuse of these coatings could affect performance of engineered safety featuresis by flaking off and entry through the drains during recirculation after anaccident, it is expected that their use will have no deleterious effects onengineered safety equipment and that flow blockage or fouling of heattransfer surfaces will not take place.5.2.6 Compressive Test Strength of ConcreteSpecified compressive concrete strength (f0') is used for design of Class Istructures except for the structures defined below where actual compressivestrength has been established.Where applicable. actual concrete design compressive strength isestablished using analysis of 28-day test data based on Building Code ACI318-63 Section 504(c).For structures designed in accordance with Part IV-A of AC! 318-63. theaverage of any five consecutive strength tests of the laboratory-curedspecimens representinq each class of concrete shall be equal to or are aterthan the specified strength. f0,'. and not more than 20 percent of the strenathtests shall have values less than the specified strength.For structures designed in accordance with Part IV-B of AC! 3 18-63. and forprestressed structures the average of any three consecutive strenqth tests ofthe laboratory-cured specimens representinci each class of concrete shall beequal to or are ater than the specified strenath. f0,'. and not more than 10percent of the strength tests shall have values less than the specifiedstrength USAR-5.2 Information Use Page 13 of 13Materials of Construction Rev. 8A rolling average is calculated for consecutive strength tests, and theminimum strenath of the average values represents the area specified. Thedesign strength is the lesser of the minimum rolling average design basisconcrete strength or the 95% confidence level of all test data for thestructural group.Concrete strengths based on 28-day test data may only be used in areas notpotentially affected by degradation of concrete by long-term exposure to highradiation, damaging chemicals, or excessive moisture.Actual concrete design compressive strengths are established using themethodology described above in the following areas:-Auxiliary Building: Except for exterior walls below elevation 1007 ft.-Containment Internal Structures: Except for the concrete wallssurrounding the reactor vessel and the floor of the reactor cavity.Actual concrete design compressive strenath is not used for the IntakeStructure or its foundation, the Spent Fuel Pool. Containment Structure or theContainment / Auxiliary Building foundation.
Page 1 of 18II usAR-5.11 IStructuresStructures Other Than ContainmentRev 14Safety Classification:II SafetyUsage Level:II Information IChange No.:Reason for Change:Preparer:Issued:Fort Calhoun Station USAR-5.11I Information Use Page 2 of 18Structures Other Than Containment Rev. 14Table of Contents5.11 Structures Other Than Containment ........................................................ 45.11.1 Classification of Structures ......................................................... 45.11.2 Description of Class I Structures................................................... 45.11.3 Design Criteria -Class I Structures................................................ 55.11.4 Design of Structures -Class II.................................................... 175.11.5 Visual Weld Acceptance Criteria ................................................. 18 USAR-5.11IStructures Other Than ContainmentInformation Use Page 3 of 18Rev. 14List of FiguresThe following figures are controlled drawings and can be viewed and printed from the listedaperture card.Figqure No.TitleAperture Card5.11-1Section Through Engineered Safeguards Equipment Room36534 USAR-5.11I Information Use Page 4 of 18Structures Other Than Containment Rev. 145.11 Structures Other Than Containment5.11.1 Classification of StructuresStructures are classified into two categories. Class I and Class I1. Asdescribed in Appendix F, Class I structures include containment (including allpenetrations and air locks, the concrete shield, the liner and the interiorstructures), the auxiliary building (including the control room, spent fuel pool,safety injection and refueling water storage tank and emergencydiesel-generator rooms), and the intake structure up to 1007.5'.USAR Section 5.11 describes the auxiliary building, intake structure, and theinterior structures of containment. The containment building Shell (walls,roof, flat base) is described in Section 5.5.5.11.2 Description of Class I StructuresThe auxiliary building is a Class I structure other than the reactorcontainment, and is located immediately adjacent to the containmentstructure.The foundation mat for the auxiliary building and the containment structure isan integral unit supported on piles driven to bedrock. The piling type anddesign criteria are presented in Section 5.7.The auxiliary building is a multi-floored structure Of reinforced concreteconstruction. The building was designed to provide suitable tornado andearthquake protection for the Class I equipment and components containedtherein. The criteria for this design are given in Section 5.11.3.The masonry walls in the area of safety-related equipment have beenreinforced to provide protection for Class 1 equipment and componentsnearby.A section through the engineered safeguards equipment room showing thestructural relationship between this room, the auxiliary building and thecontainment wall, is shown on Figure 5.11-1.The containment internal structure (CIS) is a reinforced concrete structureconsisting of several levels and compartments constructed of beams, slabsand walls supported by reinforced concrete columns located around theperiphery of the containment, and the reactor cavity and compartment wallslocated in the center of containment. The CIS was designed to providesupport to major systems and components required for the safe operation ofFCS during all operational and outage conditions, including accidentmitigation. The CIS is isolated from the containment shell by a shake spacewhich uncouples the response of the shell and dome from that of the internal USAR-5.11I Information Use Page 5 of 18Structures Other Than Containment Rev. 14structure during a seismic event and also permits the distribution anddissipation of any internal pressures during postulated accident events. Thecriteria for the CIS design are given in Section 5.11.3.The intake structure is a multi-floored reinforced concrete structure supportedby a mat foundation on steel pipe piles driven to bedrock. Major systemsand components, both critical quality element (CQE) and non-CQE, thatprovide water from the Missouri River required for heat removal, are housedwithin this structure in designated rooms. The building was designed toprovide the structural support and environmental protection necessary toensure the functional integrity of the CQE systems and components under alloperational and environmental conditions is maintained. The criteria for thisdesign are given in Section 5.11.3.5.11 .3 Design Criteria -Class I StructuresClass I structures were designed to ensure that their functional integrityunder the most extreme environmental loadings, such as tornado ormaximum hypothetical earthquake, will not be impaired and thereby, preventa safe shutdown of the plant.5.11.3.1 Loadinga. Dead Load (D)Dead loads included the weight of the structure and other itemspermanently affixed to it such as equipment, non-structural toppings,partitions, cables, pipes and ducts.Dead loads also include interior hydrostatic fluid loads which are knownand controllable. This tvpe of loading is often sustained over time. Thisclassification is consistent with ACI 349-97 which defines fluid loads as"loads due to weight and pressures of fluids with well-defined densitiesand controllable maximum heights."b. Live Load (L)Live loads included floor loadings of a magnitude commensurate withtheir intended use, ice and snow loads on roofs, and impact loads suchas may be produced by switchgear, cranes, railroad and equipmenthandling. Design live loads, with the exception of snow and ice loads,were generally based on temporary or transient loads resulting from thedisassembly or replacement of equipment for maintenance purposes.Except for the containment, Class I structures were basically ofreinforced concrete box-type construction with internal bracing providedby the vertical concrete interior walls and the horizontal floor slabs. In USAR-5.11I Information Use Page 6 of 18Structures Other Than Containment Rev. 14general, the beams and girders of these structures do not contributesignificant lateral shear resistance for the structures, and therefore, inmost instances structural elements basically stressed by the floor liveloads will not be stressed significantly by the maximum hypotheticalearthquake. However, localized areas were investigated and whereappropriate, live loads were combined with dead loads and the maximumhypothetical earthquake load. Roof live loads from snow and ice wereconsidered as acting simultaneously with maximum hypotheticalearthquake loads.c. Wind Load (W)Wind loadings were incorporated as set forth in the ASCE paperNo. 3269, Wind Forces on Structures, for the fastest mile of wind, whichis 90 mph basic wind 30 feet above ground level at the site for 100 yearsperiod of recurrence.d. Wind Loading due to Tornado (N)The Class I structures tornado safe shut down analysis has reviseddesign criteria for future evaluations. The methodology for combinedloads is maintained. The design basis wind velocity from a tornado eventis reduced to a value of 230 mph for the Midwest zones based on studiesof tornado winds as defined in Regulatory Guide 1.76, Revision 1.Class I structures, other than the containment, were originally designedto withstand a tornado with a maximum wind velocity of 300 miles perhour. The wind loads were distributed throughout the structures inaccordance with ASCE paper No. 3269, Transactions of the AmericanSociety of Civil Engineers, Part II, 1961, utilizing a uniform loadthroughout the height of the structures.The grade slab of the auxiliary building was designed to support fallingdebris that might result from tornado wind speeds in excess of the abovestructures design wind speed of 300 mph so as to provide additionalmargin. The emergency diesel generator enclosure and the spent fuelpool structure were designed to withstand the tornado with a maximumwind velocity of 500 miles per hour, and thus have additional marginbeyond the 300 mph basis value.The 300 mph and 500 mph maximum wind velocities specified in theUSAR were considered to be the sums of the translational and rotationalcomponents of the tornado.e. Pressure Loading due to a Differential Pressure (Q)
USAR-5.11I Information Use Page 7 of 18Structures Other Than Containment Rev. 14Class I structures, other than the containment, were designed towithstand a tornado with a maximum wind velocity of 300 miles per hourand a concurrent pressure drop of 3 psi applied in a period of 3 secondsas the tornado passes across the building. This is conservative incomparison to the requirements in Regulatory Guide 1.76, Revision 1.Sufficient venting was provided to prevent the differential pressure,during depressurization, from exceeding a 1.5 psi design value which,when combined with other applicable loads, was determined to be withinthe allowable load criteria as defined later in this section. Whereasnon-vented structures would experience only external depressurization(internal pressures being greater than external pressures) ventedstructures are subject to external pressurization (internal pressures beinglower than external) during the repressurization phase of a tornado. Theresulting loads could be more limiting than those of the depressurizationphase. The vented structures have, therefore, been subsequentlyreanalyzed for a complete tornado transient which includes the pressuredrop (depressurization) of 3 psi in 3 seconds followed by a low pressuredwell period followed by a recovery pressure rise (repressurization of 3psi in 3 seconds). The dwell period was sufficient for internal pressuresto drop 3 psi prior to repressurization, which results in the mostconservative recovery differentials. The transient reanalysis wasperformed using a suitable dynamic Thermal-Hydraulic analysis codewhich models the structure as a series of internal volumes connected byvarious flow paths and vent openings to other volumes and/or boundaryconditions. The tornado transient was applied as a time history pressureboundary condition on external flow paths. The structures have beenshown to be within design basis allowables for the resultantrepressurization differentials combined with other applicable loadsthereby demonstrating no loss of function during the repressurizationphase of a design basis tornado.Two cases were considered, during design, in determining vent arearequirements. First, a space communicating directly to the outside wastreated as a chamber with a sharp edge orifice. The orifice was sizedusing classical formulae, to give pressure drop of 1.5 psig when flow wasfully developed. The flow corresponding to that pressure drop was thatrequired to reduce the pressure in the room by 0.5 psi per second. Thecriterion developed by this process was that there should be one squarefoot of vent area for each 1,000 cubic feet of space. This criterionincluded a margin of safety over the calculation value. For reanalysis, itwas conservatively assumed that exterior hinged doors and horizontalconcrete relief panels reclose, during repressurization, when air flowsreverse in the direction of closure resulting in reduced vent area andhigher than 1.5 psid pressure drops.In many cases, spaces do not communicate directly with the outside, butthrough another space. For example, the ground floor of the auxiliary USAR-5.11I Information Use Page 8 of 18Structures Other Than Containment Rev. 14building communicates directly to the outside, but the basementcommunicates indirectly, i.e., through the ground floor. A two stage,iterative model, using the same classical formulae as above, was used tocalculate this case for design. The criterion used was that pressure dropacross an outside wall should not exceed 1.5 psi, and pressure dropacross an interior wall or ceiling should not exceed 1 .psi. The calculationwas performed on a dynamic basis, i.e., the tornado pressure depressionof 0.5 psi per second was assumed to act on initially static conditions.This ramp acted for three seconds, and the AP between the basementand the first floor, and between the first floor and the outside wascalculated as a function of time. It was found that an opening of onesquare foot per thousand cubic feet of basement volume was sufficientbetween the basement and the first floor. Also, an opening in the outsidewall of four square feet per thousand cubic feet of first floor volume wassufficient. For reanalysis, it was conservatively assumed that interiorhinged doors reclose, during repressurization, if air flow reversed in thedirection of closure. This resulted in pressure differentials greater thanI psi for some interior envelopes.The vent areas consist primarily of doors and relief panels. These wereassumed, for original design, not to be capable of resisting more thanapproximately 0.5 psi pressure differential. With resistance capability ofonly one third the design pressure differential, these barriers wereexpected to open well within the required time. For reanalysis, theexisting fire doors installed since original construction were found, frommanufacturers data, to have failure ratings greater than 0.5 psid in theopen direction. The appropriate values were used for reanalysis. It hasbeen shown that these doors open in time to limit pressure differentialsto acceptable values based on the building structures compliance withapplicable load limits for no loss of function.f. Tornado Missile LoadClass I structures were also designed to withstand the spectrum oftornado generated missiles listed in Section 5.8.2.2. The spectrum oftornado generated missiles and the methodology for structuralevaluations were updated by Amendment 272.The methodology uses Regulatory Guide 1.76, Revision I and TopicalReport BC-TOP-9A, Revision 2 to address protection of SSCs fromtornado-generated-missiles at ECS with one exception. The exceptionregards the potential impact height of an automobile missile whereprocedural controls prohibit vehicle access to higher surroundingelevations within 0.5 miles of plant structures during periods of increasedpotential for tornadoes.
USAR-5.11 Information Use Page 9 of 18Structures Other Than Containment Rev. 14g. Seismic Load (E, E')E = Seismic load from operating basis earthquake (OBE)E' = Seismic load from maximum hypothetical earthquake (also calledDesign Basis Earthquake, DBE)Class I structures were designed for seismic loads as discussed inAppendix F.Potential seismic loadings were specified as static mechanical loads forthe design of the reactor coolant pumps and their drives. These loadingsinclude inertia loadings at the center of gravity of the pump driveassemblies, nozzle loads at the pump suction and discharge and support(hanger) reactions at the pump support lugs. In design calculations forthe pump casings, potential seismic loads, in combination with otherspecified loadings, were evaluated and the calculated stresses limited inaccordance with Table 4.2-3.The seismic input for the internal structure of the reactor vessel, wasobtained by "normalizing" the response spectra, Figure F-I and F-2(Appendix F) to a ground acceleration equal to the maximumacceleration of the reactor vessel flange.h. Soil Pressure Load (H)Load due to lateral earth pressure or ground water pressure for design ofstructures below grade. Load due to pressure of bulk materials for designof other retention structures.i.Flood Load (F, F')F = Flood load to elevation 1007 feetHydrostatic load due to lateral pressure of floodwaters to 1007 feetelevation. These loads are equal to the product of the water pressuremultiplied by the surface area on which the pressure acts. Hydrostaticpressure is equal in all directions and acts perpendicular to the surfaceon which it is applied.
USAR-5.11I Information Use Page 10 of 18Structures Other Than Containment Rev. 14F" = Hydrostatic load to elevation 1014 feetClass I structures were also designed for the Corps of Engineersestimate of the flood level that might result from the failure of Oahe orFort Randall dams. The estimated flood level resulting from the failure ofa dam coincident with the probable maximum flood is 1014 feet (SeeSection 2.7.1.2).5.11.3.2 Operating Basis Load Combinations for Class I Steel StructuresClass I steel structures were designed on the basis of working stress forthe following load combinations:S=D+L+HS=D+L+H+WorES=D+H+Fwhere:S = Required section capacitylo-dL- Ii',,e load including1. hd,-rostatic load¢H -Soil PressureF -H,,dr,-ostatic l,-oad to. ,lc' ....o 1;.007 feet\A- I'loadingThe allowable stress capacity of Class I structural steel is determined inaccordance with the allowable stress design provisions from the AISCCode. 1963 edition.5.11.3.3 Design Basis Load Combinations for Class I Steel StructuresClass I steel structures were also designed on the basis of no loss offunction for the following load combinations:S =D +H +E'S =D +H +L +E'S=D+N+QS = D + 1.25H + F'where:S = Required section capacityI'- Dead-,- load,-L- ie load, i h,,',,.-o+sa ,., loadE' Maimu hyothticl. earthquake USAR-5.11 Information Use Page 11 of 18Structures Other Than Containment Rev. 14H- -- SoI Prcssu reThe AlSO Code for Structural Steel, 1963 edition, design methods andallowable stresses were used for steel structures.5.11.3.4 Operating Basis Load Combinations for Class I Concrete StructuresS- D+L+WrS- Dea+laI-- Wind- IA- DesIgnI earhqakClass I concrete structures were originally designed for operating basisconditions using ACI 318-63 Code working stress capacities asdiscussed below in Section 5.11.3.4(b'a. Ultimate Strength DesignWith the approval of Amendment No. X)XX, the design criteria foroperating basis conditions chanaed to implement the ultimate strengthdesign method for normal/operating service conditions for changes andreanalysis using the following load combinations:U -1 (1 .4D + 1 .7L + 1 .7H)U = 1 (1 .0D + 0.05 D + 1 .25L + 1.25W + 1 .25H)
USAR-5.11I Information Use Page 12 of 18Structures Other Than Containment Rev. 14U = 1(1.0D + 0.05 0 + 1 .25L + 1 .25E + 1 .25H)U = 1 (1 .4D + 1 .7H + I1.7F)where:U = Ultimate strength capacity per the ACI 31 8-63 Codeci' = Reduction factors in accordance with the following valuesand applications:ci' = 0.90 for concrete in flexureci' = 0.90 for mild reinforcing steel in direct tension excludingmechanical or lapped splicesci' = 0.85 for mild reinforcing steel in direct tension withlaDped or mechanical splicesci' = 0.85 for diagonal tension, bond and anchorageci' = 0.70 for tied compression membersThe ultimate strength capacity of Class I reinforced concrete structures isdetermined in accordance with the ultimate strength provisions from theACI 318-63 Code using the capacity reduction factors, ci' listed above.b. Working Stress DesignFoundations for Class I structures are not upgraded to ultimate strengthdesign by Amendment XX(X. They are designed on the basis of workingstress for the following load combinations:S- D+LS= D+L+WorES= D+Fwhere:S = Reguired section capacityThe ACI Code 318-63 design methods and allowable stresses were usedfor reinforced concrete.The application of limit design method for RC&C walls includesdeformation limit eguations in ACI 349-97 Commentary on Appendix CSection C.3.
USAR-5.11I Information UseStructures Other Than ContainmentPage 13 of 18Rev. 145.11.3.5 Design Basis Load Combinations for Class I Concrete StructuresCla-ssc I trctulres,.÷ a-lso,', on the basisc no lossc. of fo'r the "followi;ng' Class I concrete structures were designed for no loss of function for theload combinations shown below using the ultimate strenath designprovisions of the ACI 318-63 Code.U = 1(1 .0D + 1 .OH + 1 .0E')U = 1 (1 .0D + 1 .0L + 1 .OH + 1 .0E'); Live Load (L) as required.U = 1 (1.00 + 1 .ON + 1 .OH + 1 .0Q)ci,U = 1 (1.00 + 1 .25H + I .OF')cI,where: U =Ultimate strength capacity required per the ACI 318-63CodeD- Dead. -., ,. Li'.c S- Windulotiong facoss defined in Section5.113.4 foa30eH -Soil Pressuretei lxrli'= Rducio facor as~n~ sownlin Scin51.34aoeiaccordanceI wIthl the followgIngvale n ppiain:"- 0.90 V forstuctra steelI Vl1. ii iraIa VThe application of limit design method for RC&C walls includesdeformation limit equations in ACI 349-97 Commentary on Appendix CSection C.3 USAR-5.11 Information Use Page 14 of 18Structures Other Than Containment Rev. 145.11.3.6 Special Case Load Combinationsa. Load Combinations for Faulted ConditionsThe concrete structure within the containment was considered as aClass I structure and was subject to the loads and analysis noted abovewith the exception of wind and tornado loads. In addition, a transientanalysis was made to determine the maximum differential pressureacross the interior shielding and structural walls and floors. Openings inthe interior concrete walls and floors are provided and grating floors areused wherever possible, without reducing the necessary shielding, toallow pressurization of all compartments with the minimal differentialpressure across walls and floors.In order to provide for the pressure loading resulting from a major breakin the reactor coolant system that portion of the concrete structure withinthe containment surrounding the reactor vessel and reactor coolantsystem was analyzed and checked on the basis of ultimate strengthdesign methods of ACI Code 318-63 for the factored load combinationsgiven below. Dynamic increase factors appropriate for the strain ratesinvolved for impulsive loads to the reactor cavity and compartment wallsand transfer canal complv with ACI 349-97. Appendix C. The factoredload equations are:U = 1(1.0D+/-+O.05D +1.5Pc +1.0Tc)U =1_ (1.0D+/-+O.05D +1.25Pc +1.25E +1.0Tc)U =1!(1.0D+/-+O.05D +1.0Pc + 1.0E' +1.0Tc)where: U, D, E and E' are as defined above, andPc = Differential pressure between compartments as a resultof a major break in the reactor coolant system.Tc = Thermal load caused by temperature gradient acrossthe concrete section (generally not applicable to thesestructures). The capacity reduction factors, ci', are asgiven above.
USAR-5.11I Information Use Page 15 of 18Structures Other Than Containment Rev. 14Special steel structures were used around the steam generators for thepurpose of limiting the motion of the generator in case a rupture occursin the reactor coolant piping or in the main steam pipe, or in thefeedwater pipe. The energy absorbing members of these structures arehold back rods acting in tension which were designed for strains beyondthe elastic limit. The energy due to a pipe break was transformed intostrain energy by the yielding of the hold back rods.b. Load Combinations for Spent Fuel PoolThe spent fuel pool (SEP) structure, including walls, slab and piling, wasrevisited for the 1994 rerack modification (Ref. 5.13.11 ). Athree-dimensional ANSYS finite element analysis was performed. Thedesign basis and load combinations have been upgraded to thoseprescribed in the NRC Standard Review Plan (SRP) 3.8.4. After deletingthose loads which are not applicable to the SEP structure, the limitingfactored load combinations are as follows:U = 1.4D+1.9EU = 0.75 (1.4D + 1.7To + 1.9E)U= D+Ta+E'U =D+Tma +1.25Ewhere:U = Ultimate strength capacity requiredD = Dead loadE = Design earthquakeE'= Maximum hypothetical earthquakeTa= Abnormal design thermal loadTo= Normal operating thermal loadThe pool is filled with water. The hydrostatic pressure, dead load ofracks plus 1083 fuel bundles having conservatively postulated dry weightof 2480 lbs per assembly, water sloshing and convective load, andthermal load were considered. The pool water temperature of 140°Fwhich bounds the normal operating condition was utilized for theanalysis. Cracked sections were assumed in the thermal stress analysis.Cracks are usual in reinforced concrete structure. Such credit ispermitted by ACI 349-85. The fuel transfer canal, which is next to thespent fuel pool, is assumed to be drained to maximize the loadingcondition for the spent fuel pool. The calculated loads for the SEPstructure, including the walls, slab, and piling, do not exceed the ultimatestrength capacity allowable delineated in SRP 3.8.4 and the applicableACI Code.
USAR-5.11I Information Use Page 16 of 18Structures Other Than Containment Rev. 14A stainless steel liner was provided on the inside face of the pool. Thisliner plate, due to its ductile nature, will absorb the strain due to thecracking of the concrete in the walls and along with the concrete wallswill guarantee tightness of the pool for the full range of credible watertemperatures.5.11.3.7 Codes and StandardsThe design of Class I structures, other than the containment, wasgoverned by the then applicable building design codes and standards. Ingeneral, those of the American Institute of Steel Construction, theAmerican Concrete Institute, and the American National StandardsInstitute were followed.Generally accepted design procedures were used in the development ofall structures with modern computerized practices to facilitate the studyof all credible combinations of loadings.Structural steel was designed in accordance with the requirements of theSpecification for the Design, Fabrication, and Erection of Structural Steelfor Buildings, 1963 edition, of the AISC. Elastic theory was the basis ofdesign for all structural steel except for the hold-back bolts at the steamgenerators.Reinforced concrete was designed in accordance with the Building CodeRequirements for Reinforced Concrete, of the ACI (ACI-31 8-63) and asstipulated in Sections 5.11.3.1a and 5.11.3.6.5.11.3.8 Concrete Compressive StrengthWhere applicable. concrete design compressive strengths (f') may beestablished usinq analysis of historical test data as described in Section5.2.6.5.11.3.9 Steel Reinforcing CapacityWhere applicable. steel reinforcing capacity allowable stress values maybe established using analysis of historical test data as described inSection 5.2.2.1.
USAR-5.11I Information Use Page 17 of 18Structures Other Than Containment Rev. 145.11.4 Design of Structures -Class IIClass II structures were designed in accordance with conventional practiceand on the basis of generally recognized governing codes and criteria suchas those of the American Institute of Steel Construction, American ConcreteInstitute, National Building Code and the American National StandardsInstitute. The following criteria apply:a. Dead loads include the weight of the structure and other itemspermanently affixed to it such as equipment, cables, piping, and ducts.b. Live loads include floor loadings of a magnitude commensurate with theirintended use, ice and snow loads on roofs, and impact loads such asmay be produced by equipment, cranes, and handling of equipment.c. Wind loadings were incorporated as set forth in the National BuildingCode, 1967 edition, for a moderate windstorm area.d. Earthquake loads were computed and utilized in accordance with theNational Building Code, 1967 edition, as defined in Appendix F, SectionF.2.4. These loads were applied to the structure independently of windloading or horizontal crane impact loading.e. Horizontal crane impact forces were computed in accordance with thestipulations of the American Institute of Steel Construction, sixth edition.f. For loading combinations involving wind or earthquake forces, aone-third increase in allowable design stresses was permitted.g. The design hydrostatic head for Class II structures was assumed to be atelevation I1007'-0". The circulating water tunnels were designed aspressure tunnels with hydrostatic pressures of a magnitudecommensurate with their intended use.For the most part, Class II structures were supported on piling with acompressive load capacity of 90 tons and an uplift capacity of 22.5 tons.Other foundations, separate from the main building, were supported on pilingof lesser capacity.The design of Class II structures was governed by then applicable buildingdesign codes and standards such as those of the American Institute of SteelConstruction, American Concrete Institute, National Building Code and theAmerican National Standards Institute. Generally accepted designprocedures were used.
USAR-5.11I Information Use Page 18 of 18Structures Other Than Containment Rev. 145.11.5 Visual Weld Acceptance CriteriaVisual weld acceptance criteria for use in structures and supports designedto the requirements of ASIC and AWS Dl1.1 and other Non-ASME codestamped structures shall be in accordance with AWS Dl1.1-86 or laterrevisions, or NCIG-01, Revision 2, titled, Visual Weld Acceptance Criteria forStructural Welding at Nuclear Power Plants. The NCIG-01, Revision 2,document is included as an EPRI document EPRI NP-5380, Volume 1,Research Project Q1 01, September 1, 1987.The use of the NCIG-01, Revision 2, acceptance criteria shall be specified instation approved procedures prior to use.The NCIG-01, Revision 2, has been evaluated by engineering and found tobe technically acceptable for use at the Fort Calhoun Station.
LIC-1 5-0142Enclosure, Attachment 2Page 1Fort Calhoun Station, Unit No. 1Renewed Facility Operating License No. DPR-40Clean Updated Safety Analysis ReportSection 5.2Section 5.11 Page 1 of 13[i usAR.5.2 IStructuresMaterials of ConstructionRev 8Safety Classification:II ~SafetyUsage Level:II Information IChange No.: ________________________Reason for Change: _______________________Preparer:_________________________Issued:_________________________Fort Calhoun Station USAR-5.2 Information Use Page 2 of 13Materials of Construction Rev. 8Table of Contents5.2 Materials of Construction ...................................................................... 45.2.1 Concrete............................................................................... 45.2.2 Reinforcing Steel and Cadweld Splices............................................. 75.2.2.1 Reactor Cavity and Compartments and Maintenance Activities ........ 75.2.3 Prestressing Post-Tensioning System .............................................. 75.2.3.1 Description................................................................... 75.2.3.2 Material Properties.......................................................... 85.2.3.3 Corrosion Protection ........................................................ 95.2.4 Liner Plate and Penetrations......................................................... 95.2.5 Protective Coatings and Paints Inside the Containment ......................... 115.2.6 Compressive Test Strength of Concrete........................................... 12 USAR-5.2Materials of ConstructionInformation UsePage 3 of 13Rev, 8List of TablesTable 5.2-2 -Concrete Mix Compositions .......................................................... 6 USAR-5.2 Information Use Page 4 of 13Materials of Construction Rev. 85.2 Materials of ConstructionThe basic specifications for the primary structural elements of containmentconstruction are presented in Sections 5.2.1 through 5.2.4. During the Nuclear SteamSupply System Refurbishment Project (NSSSRP) in 2006, a temporary opening wasprovided in the cylindrical wall for the entry of major equipment components into thecontainment. The NSSSRP construction opening is described in Section 5.3.6.5.2.1 ConcreteConcrete for the NSSSRP construction opening is described in Section 5.3.6.In~qredientsCement conformed to ASTM CI50 Type II with low alkali content. Themaximum alkali content calculated as sodium oxide was limited to0.50 percent.The air entraining agent used was "MBVR" (Master Builders Vinsol Resin).This material conformed to ASTM C260.The water reducing agent used was "Pozzolith Low Heat" as manufacturedby the Master Builders Co. This material conformed to ASTM C494 Type A.Fine aggregate is Platte River Valley sand gravel with 1/4 inch maximumsize.Coarse aggregate consists of 1-1/2 inch crushed limestone (3/4 inch forspecial limited applications) from the Plattsmouth ledge at Weeping Water,Nebraska.The aggregate materials conformed substantially to ASTM C33, except forminor variations in gradation. The aggregate mix was based on therequirements of the Nebraska Standard Specifications for HighwayConstruction, modified slightly in accordance with local practice.Investiqiation ProaqramThe aggregates for use in the concrete mix were tested for acceptability.The tests were performed by the Omaha Testing Laboratory of Omaha,Nebraska, in accordance with the then current editions of the following ASTMstandards:a. ASTM C40, Organic Impurities in Sands for Concrete;b. ASTM C75, Sampling Stone, Slag, Gravel, Sand and Stone Block for Useas Highway Materials; USAR-5.2 Information Use Page 5 of 13Materials of Construction Rev. 8c. ASTM 087, Effect of Organic Impurities in Fine Aggregate on Strength ofMortar;d. ASTM 088, Soundness of Aggregates by Use of Sodium Sulfate orMagnesium Sulfate;e. ASTM 0117, Materials Finer than No. 200 Sieve in Mineral Aggregate byWashing;f. ASTM 0123, Lightweight Pieces in Aggregate;g. ASTM 0127, Specific Gravity and Absorption of Coarse Aggregate;h. ASTM 0128, Specific Gravity and Absorption of Fine Aggregate;i. ASTM 0131, Resistance to Abrasion of Small Size Coarse Aggregate byUse of the Los Angeles Machine;j. ASTM 0136, Sieve or Screen Analysis of Fine and Coarse Aggregates;k. ASTM 0142, Clay Lumps in Natural Aggregates;I. ASTM 0235, Scratch Hardness of Coarse Aggregate Particles;m. ASTM 0289, Potential Reactivity of Aggregates;n. ASTM 0295, Petrographic Examination of Aggregates for Concrete;o. ASTM 0324, Potential Volume Change of Cement AggregateCombinations.
USAR-5.2 Information Use Page 6 of 13Materials of Construction Rev. 8MixesThe design and associated tests of concrete mixes was also performed bythe Omaha Testing Laboratory. Concrete strengths were predicated on thebasis of ACI-301, "Specification for Structural Concrete for Buildings",Section 308, Method 2 for Ultimate Strength Type Concrete and PrestressedConcrete.The basic concrete mixes evolved and utilized for construction are shown inTable 5.2-2.Table 5.2-2 -Concrete Mix CompositionsContainment Special LimitedApplication Mat & Shell Applications*Aggregate Size, in 1-1/2 3/4Compressive Strength, psiat 28 days 5000 5000Water-Cement Ratio, gals,max/sack 4.25 4.00Cement Content, max sacks!cu. yd. 6.25 7.00Aggregate Proportions, %Sand Gravel 50+/-+3 50+/-+3Crushed Limestone 50 + 3 50 +/- 3Air Content, % 4.75 + 0.75 4.75 + 0.75Pozzolith Low Heat, Ibs/sack cement 0.2 0.2Slumps, in, maximum 3 3Density, lb/cu. ft, minimum 145 145*This mix was a special mix utilizing 3/4 in. maximum crushed limestone forspecial limited applications where the density of reinforcement and difficultyof ensuring good placement of 1-1/2 in. aggregate concrete warranted itsuse. Its application has been restricted to the portion of the structure in theimmediate vicinity of the anchorages for the helical tendons.
USAR-5.2 Information Use Page 7 of 13Materials of Construction Rev. 85.2.2 Reinforcing Steel and Cadweld SplicesReinforcing Steel and Cadweld Splices for the NSSSRP constructionopening are described in Section 5.3.6.3.Reinforcing steel in the foundation mat consists of deformed billet steel barswhich conformed to ASTM A615, Grade 60. This steel has a minimum yieldstrength of 60,000 psi, minimum tensile strength of 90,000 psi, and aminimum elongation of 7 percent in an 8 inch specimen.Reinforcing steel in the cylindrical wall, the domed roof and around openingsis deformed billet steel which conformed to ASTM A61 5, Grade 40. Thissteel has a minimum yield strength of 40,000 psi, minimum tensile strength of70,000 psi, and a minimum elongation of 7 percent in a 8 inch specimen.Splices for reinforcing steel conformed to the requirements of AClCode 318-63. Splices for bar sizes No. 11 and smaller were lapped except atcertain locations such as at the construction openings. Splicing for bars atthese locations and for all bar sizes larger than No. 11 was accomplished byapproved positive connectors, specifically Cadweld "T" series connectors,(as manufactured by Erico Products Incorporated of Cleveland, Ohio),designed to develop the specified tensile strength of the reinforcing steel.No reinforcing steel strength or tack welding was permitted.5.2.2.1 Reactor Cavity and Compartments and Maintenance ActivitiesFor the reactor cavity and compartments, the yield strength (Fy) of reinforcingsteel is based on testing in accordance with ASTM Standards. Historicallaboratory test data of Grade 40 steel reinforcement used in the constructionof Fort Calhoun Station Class I structures indicate that the yield strength testresults exceed the material specification values used in the original design.Statistical analysis of Certified Material Test Reports (CMTR) for the CISconfirms the 95% confidence yield strength for Grade 40 reinforcing steel tobe 44 ksi. This is applicable to the reactor cavity and compartments andraises the yield strength from 40 ksi to 44 ksi.The higher reinforcing steel strength is also used to evaluate the containmentinternal structure beams, slabs, and columns.5.2.3 Prestressing Post-Tensioning SystemSection 5.3.6.4 describes the prestressing system and the NSSSRPconstruction opening.5.2.3.1 Description USAR-5.2 Information Use Page 8 of 13Materials of Construction Rev. 8The prestressing system is the 90 wire BBRV system as furnishedby the lnland-Ryerson Construction Products Company.Each tendon consists of 90 parallel 1/4 inch diameter high tensilecold drawn, stress relieved wires. Each end of the tendonterminates in an anchorage assembly which transfers the tendonforce to the concrete structure. Positive anchorage of the wireends is achieved with 3/8 inch diameter button heads, cold formedat the wire ends.The anchorage system consists of:a) A stressing head on one end of the tendon and a stressinghead/shim nut combination on the other end of the tendon:The cold formed button head on the tendon wire endtransmits the tendon force to the stressing head. Thestressing head or stressing head/shim nut is engagedthrough the external buttress threads by a hydraulicstressing device which induces the desired force in thetendon.b) A set of split tube shims: These shims are installed betweenthe stressing head or stressing head/shim nut and thebearing plate; they maintain the strain induced in the tendonand transmit the tendon force from the stressing head to thebearing plate.c) A bearing plate to transfer the tendon force to the concretesurface.The tendons were installed in the concrete structure in steelconduits, rigid or semi-rigid depending on location, and fullyinterlocked and completely sealed from terminal to terminalagainst leakage of mortar into the conduit.5.2.3.2 Material PropertiesTendon wire was cold drawn and stress relieved, with a minimumultimate strength of 240,000 psi. Each 90 wire tendon has aminimum ultimate strength of I1,060,000 pounds and a minimumyield strength of 848,000 pounds.Anchor components were designed to work within their elasticrange up to a load equal to the ultimate strength of the tendon,except for the plastic seating of the button heads.Governing prestressing material specifications were as follows:
USAR-5.2 Information Use Page 9 of 13Materials of Construction Rev. ga) Tendon wires: ASTM A421, Type BA;b) Bearing plate: ASTM A36, (Fine Grained Practice);c) Anchor head: AISI 1141 Special Quality;d) Bushing: HFSM Tubing AISI 1045 or AISI 4140;e) Shims: HESM Tubing AlSI 1026;f) Tendon sheathing:1. Rigid: 4 inch O.D., 14 gage and 3 gage flash controlledwelded tubing;2. Semi-rigid: 3-3/4 inch l.D. 22 gage spirally formed fromsteel strip with interlocked seam.5.2.3.3 Corrosion ProtectionTendons were prepared at the factory for shipping by applicationof a coating of a thin-filmed temporary corrosion inhibitor. Eachtendon was then coiled and enclosed in a plastic bag, and4 ounces of Shell No. 250 VPI (vapor phase inhibitor) powder wasdusted into each bag. Each bag was then sealed and shipped tothe job site.The temporary corrosion inhibitor contained not more than 10 ppmeach of chlorides, nitrates and sulfides. It was designed to adhereto the tendon during installation in the structure and to providecorrosion protection under the prevalent field conditions.The permanent corrosion protection system subsequently appliedto the tendons was manufactured and supplied by the samemanufacturer and has the same chemical restrictions as thetemporary corrosion inhibitor to ensure that all materials used inthe compounding of both systems were compatible.The exposed portion of the bearing plates, which are located inthe stressing galleries and receive the tendon stress, were coatedwith grease after final tendon installation to prevent rusting.5.2.4 Liner Plate and PenetrationsLiner plate for the NSSSRP construction opening is described inSection 5.3.6.2.
USAR-5.2 Information Use Page 10 of 13Materials of Construction Rev. 8The liner plate is 1/4 inch in thickness. The materials specified for thevarious components of the containment liner are in accordance with thefollowing:a. Liner plate at the foundation mat and within the recess below the reactorconformed to ASTM A51 6, Grade 60, except that Charpy vee-notchimpact tests in accordance with the ASME Boiler and Pressure VesselCode, Section III, Class B vessels, were performed at a maximumtemperature of 0°F.b. Material for the cylinder and dome liner plate, for embedded structuralshapes and stiffeners, for test channels, for reinforcing plates aroundpenetrations, for personnel air lock internals and for the polar crane, withexception of the thickened liner plate, conformed to ASTM A36.c. The thickened liner plate at the crane supports conformed to ASTMA516, Grade 60. In addition these plates meet and in special areasexceeded the requirements of ASTM A435 for ultrasonic testing.d. Plate for the personnel air lock barrel, bulkhead and doors, and for theequipment hatch barrel and cover and surrounding reinforcing plates,conformed to ASTM A51 6, Grade 60, manufactured to ASTM A300requirements, except that Charpy vee-notch impact tests were inaccordance with the ASME Boiler and Pressure Vessel Code, Section IIl,Class B vessels, and were performed at a maximum temperature of 0°F.e. Material for penetration sleeves conformed to ASTM A333, Grade 1, forseamless pipe and ASTM A516, Grade 60, manufactured to ASTM A300requirements for pipe formed from rolled plate, except that Charpyvee-notch impact tests were in accordance with the ASME Boiler andPressure Vessel Code Section III, Class B vessels, and were performedat a maximum temperature of 0°F.f. Bolting materials for the equipment hatch cover conformed to ASTMA320.g. Material for forged flanges conformed to ASTM A350 except for impacttest requirements; material for flanges fabricated from plate conformed toASTM A516, Grade 60, manufactured to ASTM A300 requirements.Charpy vee-notch impact tests were in accordance with the ASME Boilerand Pressure Vessel Code Section III, Class B vessels, and wereperformed at a maximum temperature of 0°F.h. Pipe for pressure connections to the test channels over liner seam weldsinaccessible for inspection conformed to ASTM A106, Grade B.
USAR-5.2 Information Use Page 11 of 13Materials of Construction. Rev. &Materials for penetrations and openings which must resist full designpressure conformed to the requirements of the ASME Boiler and PressureVessel Code, Section III, Class B vessels. NDT considerations wereaccounted for in paragraph N-I1211 a, ASME Boiler and Pressure VesselCode, Section III, which required that Charpy V-specimens be tested at atemperature at least 30°F lower than the lowest service metal temperature inaccordance with the requirements of paragraphs N-331, N-332, N-5I11.2 andN-51 5. The lowest service metal temperature for penetrations within thecontainment is 50°F. All those penetrations projecting outside thecontainment are located within the enclosure provided by the auxiliarybuilding; the lowest service metal temperature for these penetrations is 50°F.5.2.5 Protective Coatings and Paints Inside the ContainmentProtective coatings for the NSSSRP construction opening are described inSection 5.3.6.2.ConstructionCoatings used within the containment were specified to withstand accidentconditions. The applicable requirements of ANSI NI01.4-1972, QualityAssurance for Protective Coatings Applied to Nuclear Facilities, andRegulatory Guide (RG) 1.54, Revision 0, Quality Assurance Requirementsfor Protective Coatings Applied to Water Cooled Nuclear Power Plants, wereimplemented for modification activities and meet or exceed original plantspecifications and manufacturer recommendations.Most carbon steel original equipment has prime coats of Carbozinc orCarboweld and finish coats of Phenoline 305, all products of the CarbolineCorporation. The Safety Injection Tanks were primed with DuPont Corlar825-8031 epoxy zinc chromate primer number 583 while the PressurizerQuench Tank was primed with DuPont number 773 Dulux zinc chromateprimer. Documentation that all primers and top coats stated above have beentested or are acceptable for their service applications is shown by CarbolineCorporation and DuPont specifications and test sheets.Concrete inside the containment was treated with Amercoat Nu-Klad 1100QAand top coated with Amercoat No. 66. Testing has proven this type ofcoating to be adequate under accident conditions.Some minor components such as instrument housings and electricalcabinets have proprietary coatings, mostly baked enamels. The total area socoated, however, is very small compared to the total surface area.
USAR-5.2 Information Use Page 12 of 13Materials of Construction Rev. 8Maintenance and ModificationCoating materials currently used for maintenance of existing surfaces or forsurfaces of new modifications installed inside the reactor containment areepoxy materials tested to withstand Fort Calhoun design basis accident(i.e., loss of coolant accident (LOCA)) conditions. The coating materials andtheir application comply with the requirements of RG 1.54. Each coating wastested in accordance with ANSI NI101.2, Protective Coatings (Paints) forLight Water Nuclear Reactor Containment Facilities, or ASTM D391 1,Evaluating Coatings Used in Light-Water Nuclear Power Plants at SimulatedDesign Basis Accident (DBA) Conditions, to conditions that bound the FortCalhoun DBA conditions. Prior to exposure to the simulated DBA conditions,each coating test panel was irradiated to an accumulated dose of at least1.8 x 108 Rads in accordance with ASTM D4082, Standard Test Method forEffects of Gamma Radiation on Coatings for Use in Light-Water NuclearPower Plants.Use of the above coatings precludes the possibility of large flaking orskinning off of sheets of paint during accident conditions. Since the only wayuse of these coatings could affect performance of engineered safety featuresis by flaking off and, entry through the drains during recirculation after anaccident, it is expected that their use will have no deleterious effects onengineered safety equipment and that flow blockage or fouling of heattransfer surfaces will not take place.5.2.6 Compressive Test Strength of ConcreteSpecified compressive concrete strength (fc') is used for design of Class Istructures except for the structures defined below where actual compressivestrength has been established.Where applicable, actual concrete design compressive strength isestablished using analysis of 28-day test data based on Building Code ACI318-63 Section 504(c).For structures designed in accordance with Part IV-A of ACI 3 18-63, theaverage of any five consecutive strength tests of the laboratory-curedspecimens representing each class of concrete shall be equal to or greaterthan the specified strength, f0', and not more than 20 percent of the strengthtests shall have values less than the specified strength.For structures designed in accordance with Part IV-B of ACI 3 18-63, and forprestressed structures the average of any three consecutive strength tests ofthe laboratory-cured specimens representing each class of concrete shall beequal to or greater than the specified strength, f0', and not more than 10percent of the strength tests shall have values less than the specifiedstrength USAR-5.2 Information Use Page 13 of 13Materials of Construction Rev. 8A rolling average is calculated for consecutive strength tests, and theminimum strength of the average values represents the area specified. Thedesign strength is the lesser of the minimum rolling average design basisconcrete strength or the 95% confidence level of all test data for thestructural group.Concrete strengths based on 28-day test data may only be used in areas notpotentially affected by degradation of concrete by long-term exposure to highradiation, damaging chemicals, or excessive moisture.Actual concrete design compressive strengths are established using themethodology described above in the following areas:-Auxiliary Building: Except for exterior walls below elevation 1007 ft.-Containment Internal Structures: Except for the concrete wallssurrounding the reactor vessel and the floor of the reactor cavity.Actual concrete design compressive strength is not used for the IntakeStructure or its foundation, the Spent Fuel Pool, Containment Structure or theContainment / Auxiliary Building foundation.
Page 1 of 17IUSAR-5.11Ii,StructuresStructures Other Than ContainmentRev -1~4Safety Classification:II SafetyUsage Level:II Information IChange No.:_________________________Reason for Change: ________________________Preparer:__________________________Issued:_________________________Fort Calhoun Station USAR-5.11I Information Use Page 2 of 17Structures Other Than Containment Rev. 144Table of Contents5.11 Structures Other Than Containment ........................................................ 45.11.1 Classification of Structures ......................................................... 45.11.2 Description of Class I Structures................................................... 45.11.3 Design Criteria -Class I Structures................................................ 55.11.4 Design of Structures -Class II ................................................... 165.11.5 Visual Weld Acceptance Criteria ................................................. 17 USAR-5.11IStructures Other Than ContainmentInformation UsePage 3 of 17Rev. 144List of FiguresThe following figures are controlled drawings and can be viewed and printed from the listedaperture card.Ficqure No.TitleAperture Card5.11-1Section Through Engineered Safeguards Equipment Room36534 USAR-5.11I Information Use Page 4 of 17Structures Other Than Containment Rev.1-145.11 Structures Other Than Containment5.11.1 Classification of StructuresStructures are classified into two categories. Class I and Class I1. Asdescribed in Appendix F, Class I structures include containment (including allpenetrations and air locks, the concrete shield, the liner and the interiorstructures), the auxiliary building (including the control room, spent fuel pool,safety injection and refueling water storage tank and emergencydiesel-generator rooms), and the intake structure up to 1007.5'.USAR Section 5.11 describes the auxiliary building, intake structure, and theinterior structures of containment. The containment building Shell (walls,roof, flat base) is described in Section 5.5.5.11 .2 Description of Class I StructuresThe auxiliary building is a Class I structure other than the reactorcontainment, and is located immediately adjacent to the containmentstructure.The foundation mat for the auxiliary building and the containment structure isan integral unit supported on piles driven to bedrock. The piling type anddesign criteria are presented in Section 5.7.The auxiliary building is a multi-floored structure of reinforced concreteconstruction. The building was designed to provide suitable tornado andearthquake protection for the Class 1 equipment and components containedtherein. The criteria for this design are given in Section 5.11.3.The masonry walls in the area of safety-related equipment have beenreinforced to provide protection for Class I equipment and componentsnearby.A section through the engineered safeguards equipment room showing thestructural relationship between this room, the auxiliary building and thecontainment wall, is shown on Figure 5.11-1.The containment internal structure (CIS) is a reinforced concrete structureconsisting of several levels and compartments constructed of beams, slabsand walls supported by reinforced concrete columns located around theperiphery of the containment, and the reactor cavity and compartment wallslocated in the center of containment. The CIS was designed to providesupport to major systems and components required for the safe operation ofECS during all operational and outage conditions, including accidentmitigation. The CIS is isolated from the containment shell by a shake spacewhich uncouples the response of the shell and dome from that of the internal USAR-5.11 Information Use Page 5 of 17Structures Other Than Containment Rev. -44structure during a seismic event and also permits the distribution anddissipation of any internal pressures during postulated accident events. Thecriteria for the CIS design are given in Section 5.11.3.The intake structure is a multi-floored reinforced concrete structure supportedby a mat foundation on steel pipe piles driven to bedrock. Major systemsand components, both critical quality element (CQE) and non-CQE, thatprovide water from the Missouri River required for heat removal, are housedwithin this structure in designated rooms. The building was designed toprovide the structural support and environmental protection necessary toensure the functional integrity of the CQE systems and components under alloperational and environmental conditions is maintained. The criteria for thisdesign are given in Section 5.11.3.5.11.3 Design Criteria -Class I StructuresClass I structures were designed to ensure that their functional integrityunder the most extreme environmental loadings, such as tornado ormaximum hypothetical earthquake, will not be impaired and thereby, preventa safe shutdown of the plant.5.11.3.1 Loadinga. Dead Load (D)Dead loads included the weight of the structure and other itemspermanently affixed to it such as equipment, non-structural toppings,partitions, cables, pipes and ducts.Dead loads also include interior hydrostatic fluid loads which are knownand controllable. This type of loading is often sustained over time. Thisclassification is consistent with ACI 349-97 which defines fluid loads as"loads due to weight and pressures of fluids with well-defined densitiesand controllable maximum heights."b. Live Load (L)Live loads included floor loadings of a magnitude commensurate withtheir intended use, ice and snow loads on roofs, and impact loads suchas may be produced by switchgear, cranes, railroad and equipmenthandling. Design live loads, with the exception of snow and ice loads,were generally based on temporary or transient loads resulting from thedisassembly or replacement of equipment for maintenance purposes.Except for the containment, Class I structures were basically ofreinforced concrete box-type construction with internal bracing providedby the vertical concrete interior walls and the horizontal floor slabs. In USAR-5.11I Information Use Page 6 of 17Structures Other Than Containment Rev. -14general, the beams and girders of these structures do not contributesignificant lateral shear resistance for the structures, and therefore, inmost instances structural elements basically stressed by the floor liveloads will not be stressed significantly by the maximum hypotheticalearthquake. However, localized areas were investigated and whereappropriate, live loads were combined with dead loads and the maximumhypothetical earthquake load. Roof live loads from snow and ice wereconsidered as acting simultaneously with maximum hypotheticalearthquake loads.c. Wind Load (W)Wind loadings were incorporated as set forth in the ASCE paperNo. 3269, Wind Forces on Structures, for the fastest mile of wind, whichis 90 mph basic wind 30 feet above ground level at the site for 100 yearsperiod of recurrence.d. Wind Loading due to Tornado (N)The Class I structures tornado safe shut down analysis has reviseddesign criteria for future evaluations. The methodology for combinedloads is maintained. The design basis wind velocity from a tornado eventis reduced to a value of 230 mph for the Midwest zones based on studiesof tornado winds as defined in Regulatory Guide 1.76, Revision 1.Class I structures, other than the containment, were originally designedto withstand a tornado with a maximum wind velocity of 300 miles perhour. The wind loads were distributed throughout the structures inaccordance with ASCE paper No. 3269, Transactions of the AmericanSociety of Civil Engineers, Part II, 1961, utilizing a uniform loadthroughout the height of the structures.The grade slab of the auxiliary building was designed to support fallingdebris that might result from tornado wind speeds in excess of the abovestructures design wind speed of 300 mph so as to provide additionalmargin. The emergency diesel generator enclosure and the spent fuelpool structure were designed to withstand the tornado with a maximumwind velocity of 500 miles per hour, and thus have additional marginbeyond the 300 mph basis value.The 300 mph and 500 mph maximum wind velocities specified in theUSAR were considered to be the sums of the translational and rotationalcomponents of the tornado.e. Pressure Loading due to a Differential Pressure (Q)
USAR-5.11I Information Use Page 7 of 17Structures Other Than Containment Rev. -44Class I structures, other than the containment, were designed towithstand a tornado with a maximum wind velocity of 300 miles per hourand a concurrent pressure drop of 3 psi applied in a period of 3 secondsas the tornado passes across the building. This is conservative incomparison to the requirements in Regulatory Guide 1.76, Revision 1.Sufficient venting was provided to prevent the differential pressure,during depressurization, from exceeding a 1.5 psi design value which,when combined with other applicable loads, was determined to be withinthe allowable load criteria as defined later in this section. Whereasnon-vented structures would experience only external depressurization(internal pressures being greater than external pressures) ventedstructures are subject to external pressurization (internal pressures beinglower than external) during the repressurization phase of a tornado. Theresulting loads could be more limiting than those of the depressurizationphase. The vented structures have, therefore, been subsequentlyreanalyzed for a complete tornado transient which includes the pressuredrop (depressurization) of 3 psi in 3 seconds followed by a low pressuredwell period followed by a recovery pressure rise (repressurization of 3psi in 3 seconds). The dwell period was sufficient for internal pressuresto drop 3 psi prior to repressurization, which results in the mostconservative recovery differentials. The transient reanalysis wasperformed using a suitable dynamic Thermal-Hydraulic analysis codewhich models the structure as a series of internal volumes connected byvarious flow paths and vent openings to other volumes and/or boundaryconditions. The tornado transient was applied as a time history pressureboundary condition on external flow paths. The structures have beenshown to be within design basis allowables for the resultantrepressurization differentials combined with other applicable loadsthereby demonstrating no loss of function during the repressurizationphase of a design basis tornado.Two cases were considered, during design, in determining vent arearequirements. First, a space communicating directly to the outside wastreated as a chamber with a sharp edge orifice. The orifice was sizedusing classical formulae, to give pressure drop of 1.5 psig when flow wasfully developed. The flow corresponding to that pressure drop was thatrequired to reduce the pressure in the room by 0.5 psi per second. Thecriterion developed by this process was that there should be one squarefoot of vent area for each 1,000 cubic feet of space. This criterionincluded a margin of safety over the calculation value. For reanalysis, itwas conservatively assumed that exterior hinged doors and horizontalconcrete relief panels reclose, during repressurization, when air flowsreverse in the direction of closure resulting in reduced vent area andhigher than 1.5 psid pressure drops.In many cases, spaces do not communicate directly with the outside, butthrough another space. For example, the ground floor of the auxiliary USAR-5.11I Information Use Page 8 of 17Structures Other Than Containment Rev. 144building communicates directly to the outside, but the basementcommunicates indirectly, i.e., through the ground floor. A two stage,iterative model, using the same classical formulae as above, was used tocalculate this case for design. The criterion used was that pressure dropacross an outside wall should not exceed 1.5 psi, and pressure dropacross an interior wall or ceiling should not exceed 1 psi. The calculationwas performed on a dynamic basis, i.e., the tornado pressure depressionof 0.5 psi per second was assumed to act on initially static conditions.This ramp acted for three seconds, and the AP between the basementand the first floor, and between the first floor and the outside wascalculated as a function of time. It was found that an opening of onesquare foot per thousand cubic feet of basement volume was sufficientbetween the basement and the first floor. Also, an opening in the outsidewall of four square feet per thousand cubic feet of first floor volume wassufficient. For reanalysis, it was conservatively assumed that interiorhinged doors reclose, during repressurization, if air flow reversed in thedirection of closure. This resulted in pressure differentials greater than1 psi for some interior envelopes.The vent areas consist primarily of doors and relief panels. These wereassumed, for original design, not to be capable of resisting more thanapproximately 0.5 psi pressure differential. With resistance capability ofonly one third the design pressure differential, these barriers wereexpected to open well within the required time. For reanalysis, theexisting fire doors installed since original construction were found, frommanufacturers data, to have failure ratings greater than 0.5 psid in theopen direction. The appropriate values were used for reanalysis. It hasbeen shown that these doors open in time to limit pressure differentialsto acceptable values based on the building structures compliance withapplicable load limits for no loss of function.f. Tornado Missile LoadGlass I structures were also designed to withstand the spectrum oftornado generated missiles listed in Section 5.8.2.2. The spectrum oftornado generated missiles and the methodology for structuralevaluations were updated by Amendment 272.The methodology uses Regulatory Guide 1.76, Revision 1 and TopicalReport BC-TO P-9A, Revision 2 to address protection of SSCs fromtornado-generated-missiles at FCS with one exception. The exceptionregards the potential impact height of an automobile missile whereprocedural controls prohibit vehicle access to higher surroundingelevations within 0.5 miles of plant structures during periods of increasedpotential for tornadoes.
USAR-5.11I Information Use Page 9 of 17Structures Other Than Containment Rev. -44g. Seismic Load (E, E')E = Seismic load from operating basis earthquake (OBE)E'= Seismic load from maximum hypothetical earthquake (also calledDesign Basis Earthquake, DBE)Class I structures were designed for seismic loads as discussed inAppendix F.Potential seismic loadings were specified as static mechanical loads forthe design of the reactor coolant pumps and their drives. These loadingsinclude inertia loadings at the center of gravity of the pump driveassemblies, nozzle loads at the pump suction and discharge and support(hanger) reactions at the pump support lugs. In design calculations forthe pump casings, potential seismic loads, in combination with otherspecified loadings, were evaluated and the calculated stresses limited inaccordance with Table 4.2-3.The seismic input for the internal structure of the reactor vessel, wasobtained by "normalizing" the response spectra, Figure F-I and F-2(Appendix F) to a ground acceleration equal to the maximumacceleration of the reactor vessel flange.h. Soil Pressure Load (H)Load due to lateral earth pressure or ground water pressure for design ofstructures below grade. Load due to pressure of bulk materials for designof other retention structures.Flood Load (F, F')F = Flood load to elevation 1007 feetHydrostatic load due to lateral pressure of floodwaters to 1007 feetelevation. These loads are equal to the product of the water pressuremultiplied by the surface area on which the pressure acts. Hydrostaticpressure is equal in all directions and acts perpendicular to the surfaceon which it is applied.
USAR-5.11I Information Use Page 10 of 17Structures Other Than Containment Rev. -1-4F" = Hydrostatic load to elevation 1014 feetClass I structures were also designed for the Corps of Engineersestimate of the flood level that might result from the failure of Oahe orFort Randall dams. The estimated flood level resulting from the failure ofa dam coincident with the probable maximum flood is 1014 feet (SeeSection 2.7.1.2).5.11.3.2 Operating Basis Load Combinations for Class I Steel StructuresClass I steel structures were designed on the basis of working stress forthe following load combinations:S=D+L+HS =D+L+H +WorES=D+H+Fwhere:S = Required section capacityThe allowable stress capacity of Class I structural steel is determined inaccordance with the allowable stress design provisions from the AISCCode, 1963 edition.5.11.3.3 Design Basis Load Combinations for Class I Steel StructuresClass I steel structures were also designed on the basis of no loss offunction for the following load combinations:S=D+H+E'S =D +H +L +E'S=D+N+QS = D + 1.25H + F'where:S = Required section capacity USAR-5.11I Information Use Page 11 of 17Structures Other Than Containment Rev. -44The AlSC Code for Structural Steel, 1963 edition, design methods andallowable stresses were used for steel structures.5.11.3.4 Operating Basis Load Combinations for Class I Concrete StructuresClass I concrete structures were originally designed for operating basisconditions using ACI 318-63 Code working stress capacities asdiscussed below in Section 5.11.3.4(b)a. Ultimate Strength DesignWith the approval of Amendment No. XX(X, the design criteria foroperating basis conditions changed to implement the ultimate strengthdesign method for normal/operating service conditions for changes andreanalysis using the following load combinations:U = 1 (1 .4D + I1.7L + I1.7H)ci'U = 1 (1.0D + 0.05 D + 1.25L + 1.25W + 1.25H)c1U = 1 (1.0D+/-+0.05 D + 1.25L + 1.25E + 1.25H)ci'U = 1 (1 .4D + 1 .7H + 1 .7F)ci'where:U = Ultimate strength capacity per the ACI 318-63 Codeci' = Reduction factors in accordance with the following valuesand applications:ci' = 0.90 for concrete in flexureci' = 0.90 for mild reinforcing steel in direct tension excludingmechanical or lapped splicesci' = 0.85 for mild reinforcing steel in direct tension withlapped or mechanical splicesci' = 0.85 for diagonal tension, bond and anchorageci' = 0.70 for tied compression membersThe ultimate strength capacity of Class I reinforced concrete structures isdetermined in accordance with the ultimate strength provisions from theACI 318-63 Code using the capacity reduction factors, ci' listed above.b. Working Stress Design USAR-5.11I Information Use Page 12 of 17Structures Other Than Containment Rev. -14Foundations for Class I structures are not upgraded to ultimate strengthdesign by Amendment XXX. They are designed on the basis of workingstress for the following load combinations:S= D+LS= D+L+WorES= D+Fwhere:S = Required section capacityThe ACI Code 318-63 design methods and allowable stresses were usedfor reinforced concrete.The application of limit design method for RC&C walls includesdeformation limit equations in ACI 349-97 Commentary on Appendix CSection C.3.5.11.3.5 Design Basis Load Combinations for Class I Concrete StructuresClass I concrete structures were designed for no loss of function for theload combinations shown below using the ultimate strength designprovisions of the ACI 318-63 Code.U =1_(1 .OD + 1 .OH + 1 .OE')U = 1_ (1 .OD + 1 .0L + 1 .OH + I1.OE'); Live Load (L) as required.U = 1_(1 .OD + 1 .ON + 1 .OH + 1 .0Q)U = 1_ (1 .OD + 1 .25H + 1 .OF')where: U = Ultimate strength capacity required per the ACI 318-63Code4, = Reduction factors as shown in Section 5.11.3.4.
USAR-5.1 1 Information Use Page 13 of 17Structures Other Than Containment Rev. 44.The application of limit design method for RC&C walls includesdeformation limit equations in ACl 349-97 Commentary on Appendix CSection 0.35.11.3.6 Special Case Load Combinationsa. Load Combinations for Faulted ConditionsThe concrete structure within the containment was considered as aClass I structure and was subject to the loads and analysis noted abovewith the exception of wind and tornado loads. In addition, a transientanalysis was made to determine the maximum differential pressureacross the interior shielding and structural walls and floors. Openings inthe interior concrete walls and floors are provided and grating floors areused wherever possible, without reducing the necessary shielding, toallow pressurization of all compartments with the minimal differentialpressure across walls and floors.In order to provide for the pressure loading resulting from a major breakin the reactor coolant system that portion of the concrete structure withinthe containment surrounding the reactor vessel and reactor coolantsystem was analyzed and checked on the basis of ultimate strengthdesign methods of ACl Code 318-63 for the factored load combinationsgiven below. Dynamic increase factors appropriate for the strain ratesinvolved for impulsive loads to the reactor cavity and compartment wallsand transfer canal comply with ACI 349-97, Appendix C. The factoredload equations are:U = 1(1.0D+/-+O.05D +1.5Pc +1.0Tc)U = 1 (1.0D+/-+O.05D +1.25Pc +1.25E +1.0Tc)U =1!(1.0D+/-+O.05D +1.0Pc +1.0E' +1.0Tc)where: U, D, E and E' are as defined above, andPc = Differential pressure between compartments as a resultof a major break in the reactor coolant system.Tc = Thermal load caused by temperature gradient acrossthe concrete section (generally not applicable to thesestructures). The capacity reduction factors, ci', are asgiven above.
USAR-5.11I Information Use Page 14 of 17Structures Other Than Containment Rev. 1-4Special steel structures were used around the steam generators for thepurpose of limiting the motion of the generator in case a rupture occursin the reactor coolant piping or in the main steam pipe, or in thefeedwater pipe. The energy absorbing members of these structures arehold back rods acting in tension which were designed for strains beyondthe elastic limit. The energy due to a pipe break was transformed intostrain energy by the yielding of the hold back rods.b. Load Combinations for Spent Fuel PoolThe spent fuel pool (SEP) structure, including walls, slab and piling, wasrevisited for the 1994 rerack modification (Ref. 5.13.11). Athree-dimensional ANSYS finite element analysis was performed. Thedesign basis and load combinations have been upgraded to thoseprescribed in the NRC Standard Review Plan (SRP) 3.8.4. After deletingthose loads which are not applicable to the SEP structure, the limitingfactored load combinations are as follows:U = 1.4D +1.9EU = 0.75 (1.4D + 1.7To + 1.9E)U =D+Ta+E'U =D+Tma +1.25Ewhere:U = Ultimate strength capacity requiredD = Dead loadE = Design earthquakeE'= Maximum hypothetical earthquakeTa- Abnormal design thermal loadTo= Normal operating thermal loadThe pool is filled with water. The hydrostatic pressure, dead load ofracks plus 1083 fuel bundles having conservatively postulated dry weightof 2480 lbs per assembly, water sloshing and convective load, andthermal load were considered. The pool water temperature of 140°Fwhich bounds the normal operating condition was utilized for theanalysis. Cracked sections were assumed in the thermal stress analysis.Cracks are usual in reinforced concrete structure. Such credit ispermitted by ACI 349-85. The fuel transfer canal, which is next to thespent fuel pool, is assumed to be drained to maximize the loadingcondition for the spent fuel pool. The calculated loads for the SEPstructure, including the walls, slab, and piling, do not exceed the ultimatestrength capacity allowable delineated in SRP 3.8.4 and the applicableACI Code.
USAR-5.11I Information Use Page 15 of 17Structures Other Than Containment Rev. 44A stainless steel liner was provided on the inside face of the pool. Thisliner plate, due to its ductile nature, will absorb the strain due to thecracking of the concrete in the walls and along with the concrete wallswill guarantee tightness of the pool for the full range of credible watertemperatures.5.11.3.7 Codes and StandardsThe design of Class I structures, other than the containment, wasgoverned by the then applicable building design codes and standards. Ingeneral, those of the American Institute of Steel Construction, theAmerican Concrete Institute, and the American National StandardsInstitute were followed.Generally accepted design procedures were used in the development ofall structures with modern computerized practices to facilitate the studyof all credible combinations of loadings.Structural steel was designed in accordance with the requirements of theSpecification for the Design, Fabrication, and Erection of Structural Steelfor Buildings, 1963 edition, of the AISC. Elastic theory was the basis ofdesign for all structural steel except for the hold-back bolts at the steamgenerators.Reinforced concrete was designed in accordance with the Building CodeRequirements for Reinforced Concrete, of the ACI (ACI-31 8-63) and asstipulated in Sections 5.11.3.la and 5.11.3.6.5.11.3.8 Concrete Compressive StrengthWhere applicable, concrete design compressive strengths (fc') may beestablished using analysis of historical test data as described in Section5.2.6.5.11.3.9 Steel Reinforcing CapacityWhere applicable, steel reinforcing capacity allowable stress values maybe established using analysis of historical test data as described inSection 5.2.2.1.
USAR-5.11I Information Use Page 16 of 17Structures Other Than Containment Rev.1-145.11.4 Design of Structures -Class IIClass II structures were designed in accordance with conventional practiceand on the basis of generally recognized governing codes and criteria suchas those of the American Institute of Steel Construction, American ConcreteInstitute, National Building Code and the American National StandardsInstitute. The following criteria apply:a. Dead loads include the weight of the structure and other itemspermanently affixed to it such as equipment, cables, piping, and ducts.b. Live loads include floor loadings of a magnitude commensurate with theirintended use, ice and snow loads on roofs, and impact loads such asmay be produced by equipment, cranes, and handling of equipment.c. Wind loadings were incorporated as set forth in the National BuildingCode, 1967 edition, for a moderate windstorm area.d. Earthquake loads were computed and utilized in accordance with theNational Building Code, 1967 edition, as defined in Appendix F, SectionF.2.4. These loads were applied to the structure independently of windloading or horizontal crane impact loading.e. Horizontal crane impact forces were computed in accordance with thestipulations of the American Institute of Steel Construction, sixth edition.f. For loading combinations involving wind or earthquake forces, aone-third increase in allowable design stresses was permitted.g. The design hydrostatic head for Class II structures was assumed to be atelevation 1 007'-0". The circulating water tunnels were designed aspressure tunnels with hydrostatic pressures of a magnitudecommensurate with their intended use.For the most part, Class II structures were supported on piling with acompressive load capacity of 90 tons and an uplift capacity of 22.5 tons.Other foundations, separate from the main building, were supported on pilingof lesser capacity.The design of Class II structures was governed by then applicable buildingdesign codes and standards such as those of the American Institute of SteelConstruction, American Concrete Institute, National Building Code and theAmerican National Standards Institute. Generally accepted designprocedures were used.
USAR-5.11I Information Use Page 17 of 17Structures Other Than Containment Rev. 1445.11.5 Visual Weld Acceptance CriteriaVisual weld acceptance criteria for use in structures and supports designedto the requirements of ASIC and AWS Dl1.1 and other Non-ASME codestamped structures shall be in accordance with AWS D1.1-86 or laterrevisions, or NClG-01, Revision 2, titled, Visual Weld Acceptance Criteria forStructural Welding at Nuclear Power Plants. The NClG-01, Revision 2,document is included as an EPRI document EPRI NP-5380, Volume 1,Research Project QI101, September 1, 1987.The use of the NClG-01, Revision 2, acceptance criteria shall be specified instation approved procedures prior to use.The NCIG-01, Revision 2, has been evaluated by engineering and found tobe technically acceptable for use at the Fort Calhoun Station.
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