NRC Generic Letter 1990-02
UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555February 1, 1990TO ALL LIGHT-WATER REACTOR LICENSEES AND APPLICANTSSUBJECT: ALTERNATIVE REQUIREMENTS FOR FUEL ASSEMBLIES IN THE DESIGN FEATURESSECTION OF TECHNICAL SPECIFICATIONS (Generic Letter 90-02)Technical Specifications (TS) include design requirements for fuel assembliesin Section 5, "Design Features." On a plant-specific basis, the staff hasapproved changes to these requirements that provide flexibility for improvedfuel performance by permitting timely removal of fuel rods that are found tobe leaking during a refueling outage or are determined to be probable sourcesof future leakage. Because these improvements in a licensee's fuel performanceprogram will provide for reductions in future occupational radiation exposureand plant radiological releases, this alternative is being made available toall plants as a line-item improvement in TS.The requirements included in Section 5 of the TS on "Design Features" addressthose features of the facility such as materials of construction and geometricarrangements which, if altered or modified, would have a significant effect onsafety and are not covered under other sections of the TS on "Safety Limits,""Limiting Conditions for Operation," or "Surveillance Requirements." Recently,the staff approved a lead-plant request to modify the requirements for "FuelAssemblies." Specification 5.3.1, for the McGuire and Catawba plants. Thatchange allows the substitution of Zircaloy-4 or stainless steel filler rods oropen water channels for fuel rods in fuel assemblies if justified by cycle-specificreload analyses using an NRC-approved methodology. In addition, the changerequires that a special report describing the number of rods replaced besubmitted to NRC if more than 30 rods in the core, or 10 rods in any assembly,are replaced per refueling.The enclosed guidance addresses the preparation of a license amendmentrequest for this change to TS. Licensees and applicants are encouraged to900129005
-4propose changes to their TS that are consistent with the guidance in the enclosure.Conforming amendment requests will be expeditiously reviewed by the NRC ProjectManager for the facility. Please contact the Project Manager if you havequestions on this matter.Sincerely,J es G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationEnclosures:1. Guidance for the Modification of theRequirements for Fuel Assemblies in theDesign Features Section of TechnicalSpecifications2. List of Most Recently Issued NRCGeneric LetterseRHi..
Generic Letter 90-.Q? EnclosureGUIDANCE FOR THE MODIFICATION OF THE REQUIREMENTS FOR FUEL ASSEMBLIESIN THE DESIGN FEATURES SECTION OF TECHNICAL SPECIFICATIONSINTRODUCTIONThis enclosure provides guidance for the preparation of a license amendmentrequest to modify the Technical Specifications (TS) requirements for "FuelAssemblies" in the Section 5, "Design Features," of TS. This change to the TSpermits the substitution of Zircaloy-4 or stainless steel filler rods or openwater channels for fuel rods in fuel assemblies if justified by cycle-specificreload analyses.DISCUSSIONThe requirements for fuel assemblies specify the quantity of fuel assembliesand the number of fuel rods per assembly. Flexibility to deviate from thenumber of fuel rods per assembly is desirable to permit timely removal of fuelrods that are found to be leaking during a refueling outage or are determinedto be probable sources of future leakage. This improvement in the licensee'sfuel performance program will provide for reductions in future occupationalradiation exposure and plant radiological releases.The substitution of filler rods or open water channels for fuel rods is accept-able when justified by cycle-specific reload analyses using an NRC-approvedmethodology. This reload analyses will demonstrate that existing design limitsand safety analyses criteria are met in advance of the next operating cycle.An "NRC-approved methodology" includes those methodologies acknowledged in theFinal Safety Analysis Report and applied in support of the issuance of theoriginal operating license. It also includes those subsequent methodologiesthat have been submitted to and accepted by the NRC staff as amendments to theoperating license.If the reconstitution of fuel assemblies through the use of filler rods oropen water channels is extensive, this information should be reported to NRC.Therefore, if more than 30 rods in the core, or 10 rods in any assembly, arereplaced during a refueling, a special report describing the number of rodsreplaced must be submitted to NRC in accordance with the provisions of the TSfor special reports.The attached example is a typical specification for fuel assemblies with therequired modifications shown underlined. Proposed changes to plant TS shouldfollow this guidance.SUMMARYThe modification of the "Design Features" section of the TS on "Fuel Assemblies"will not result in modifications to fuel assemblies that would have a signifi-cant effect on safety because of the necessity to justify such changes usingan NRC-approved methodology. This requirement will confirm conformance toexisting design limits and that safety analyses criteria are met before oper-ation during the next fuel cycle. A license amendment request to modify therequirements for "Fuel Assemblies" that is consistent with the guidance provid-ed will result in flexibility for improved fuel performance.
Generic Letter 90-02EnclosureMODEL TECHNICAL SPECIFICATION CHANGE(CHANGES SHOWN UNDERLINED)5.0 DESIGN FEATURES5.3 REACTOR COREFUEL ASSEMBLIES5.3.1 The core shall contain 193 fuel assemblies with each fuel assemblynominally containing 264 fuel rods clad with Zircaloy-4,3 except that substitu-tibini577ircaloy-4 or stainless steel filler rods or open water channels forfuel rods may be ma-de in fuel assemblies if justified by cycle-speciffic Rreoadanalyses using an NRC-a-pproved methodolo y. Should more than 30 rods in-thecore. or 10 rods in any assembly be replaced per-refuel ing a secialreo~rtdescribing tenumber o rodsreplaced shal besubmited to te Commissionpursuant to Specification 6.9.2 within 30-days after c cle startup Each fuelrod shal have a nomina active fuel lengt of 14 nches. Reload fuel shallbe similar in physical design to the initial core loading and shall have amaximum enrichment of 4.0 weight percent U-235.Specification 6.9.2 of the Standard Technical Specifications (STS) states:Special reports shall be submitted to the Regional Administrator of theRegional Office of the NRC within the time period specified for eachreport.Plants whose Technical Specifications do not include STS 6.9.2 should ensurethat the revised Specification 5.3.1 includes reporting requirements equivalentto the combination of STS 5.3.1 and 6.9.2 above.A..
LIST OF RECENTLY ISSUED GENERIC LETTERSGenericLetter No.Date ofSubject IssuanceIssued ToIssued To90-0189-2389-22REQUEST FOR VOLUNTARY 01/18/90PARTICIPATION IN NRCREGULATORY IMPAC SURVEYNRC STAFF RESPONSES TO 10/23/89QUESTIONS PERTAINING TOIMPLEMENTATION OF 10 CFRPART 26 -GENERIC LETTER89-23POTENTIAL FOR INCREASED ROOF 10/19/89LOADS AND PLANT AREA FLOODRUNOFF DEPTH AT LICENSEDNUCLEAR POWER PLANTS DUE TORECENT CHANGE IN PROBABLEMAXIMUM PRECIPITATIONCRITERIA DEVELOPED BY THENATIONAL WEATHER SERVICE(GENERIC LETTER 89-22)REQUEST FOR INFORMATION 10/19/89CONCERNING STATUS OFIMPLEMENTATION OF UNRESOLVEDSAFETY ISSUE (USI) REQUIREMENTSPROTECTED AREA LONG-TERM 09/26/89HOUSEKEEPING89-21ALL LICENSEES OFOPERATING REACTORS &CONSTRUCTION PERMITSFOR LWR NUCLEAR POWERPLANTSALL HOLDERS OFOPERATING LICENSEESAND CONSTRUCTIONPERMITS FOR NUCLEARPOWER PLANTSALL LICENSEES OFOPERATING REACTORS ANDHOLDERS OF CONSTRUCTIONPERMITS (EXCEPT BYRONBRAIDWOOD, VOGTLE,SOUTH TEXAS, AND RIVERBEND)ALL HOLDERS OFOPERATING LICENSESAND CONSTRUCTIONPERMITS FOR NUCLEARPOWER REACTORSALL FUEL CYCLEFACILITY LICENSEESWHO POSSESS, USE,OR PROCESS FORMULAQUANTITIES OFSTRATEGIC SPECIALNUCLEAR MATERIALALL LICENSEES OFOPERATING REACTORS,APPLICANTS FOROPERATING LICENSESAND HOLDERS OFCONSTRUCTION PERMITSFOR LIGHT WATERREACTOR NUCLEARPOWER PLANTSALL HOLDERS OFOPERATING LICENSESOR CONSTRUCTIONPERMITS FOR NUCLEARPOWER PLANTS89-2089-19REQUEST FOR ACTION RELATED TO 09/20/89RESOLUTION OF UNRESOLVEDSAFETY ISSUE A-47 "SAFETYIMPLICATION OF CONTROLSYSTEMS IN LWR NUCLEARPOWER PLANTS" PURSUANT TO10 CFR 50.54(f)89-18RESOLUTION OF UNRESOLVEDSAFETY ISSUE A-17, "SYSTEMSINTERACTIONS IN NUCLEARPOWER PLANTS09/06/89
-2 -propose changes to their TS that are consistent with the guidance in the enclosure.Conforming amendment requests will be expeditiously reviewed by the NRC ProjectManager for the facility. Please contact the Project Manager if you havequestions on this matter.Sincerely,Original signed byJames G. PartlowJames G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationEnclosures:1. Guidance for the Modification of theRequirements for Fuel Assemblies in theDesign Features Section of TechnicalSpecifications2. List of Most Recently Issued NRCGeneric LettersDistribution:See AttachedConcurrence:The following individuals concurred in this Generic Letter by theirconcurrence in the May 10, 1989 memorandum forwarding the Generic Letter toCRGR:TGDunning, OTSB:DOEA; RLEmch, OTSB:DOEA; EJButcher, C:OTSB:DOEA;BCalure, TECH EDITOR; CHBerlinger, C:GCB:DOEA; CERossi, D:DOEA:NRR;FJCongel D:DREP:NRR; LCShao, D:DEST; SATreby, OGC; FJMiraglia, ADT:NRR;JHSniezek, DD:NRR.In a memorandum from ELJordan, Chairman, CRGR, to JHSniezek, Deputy Director,NRR, dated August 11, 1989, CRGR waived their review of this Generic Letter.Jose A. Calvo, ChiefTechnical Specifications BranchDivision of Operational Events Assessment, NRRDOCUMENT NAME: FUELGL HOXIE\* ADTY R AIg."R#3FMAbiia vW~flow -s4°MA a /90