NRC Generic Letter 1987-03

NRC Generic Letter 1987-003: Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46

ML031140317
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Clinch River, Crane
Issue date:	02/27/1987
From:	Denton H R Office of Nuclear Reactor Regulation
To:
References
USI A-46 GL-87-003, NUDOCS 8703060307
Download: ML031140317 (6)

UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555'FEB 2 7 1987-All Licensees, Applicants and Holders of Operating LicensesNot Required to be Reviewed for Seismic Adequacy of EquipmentUnder the Provisions of USI A-46, "Seismic -Qualification ofEquipment:in Operating Plants"TO:GENTLEMEN:-'SUBJECT: VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL ANDELECTRICAL EQUIPMENT IN OPERATING REACTORS, UNRESOLVEDSAFETY ISSUE (USI) A-46 (Generic Letter 87-03)As a result of the technical resolution of USI A-46, "9Seismic Qualification ofEquipment in Operating Plants," the NRC has concluded that the seismic adequacyof certain equipment in those operating nuclear power plants which have notpreviously been reviewed to current licensing requirements for seismicqualification must be reviewed to seismic criteria defined in the USI A-46technical resolution. The USI A-46 developed procedures make use of earthquakeexperience data supplemented by test data to verify the seismic capabilityof equipment below specified earthquake motion bounds. In the staff'sJudgment, this approach is the most reasonable and cost-effective means ofensuring that tWe purpose df GeneraT DesignCriteFTon-7 (10 Cr Part Du- -Appendix A) is met for these plants.Because affected plants are being asked to carry out this evaluation againstcriteria not used to establish the design basis of the facility, thisresolution is a backfit under 10 CFR 50.109. The backfit analysis andfindings may be found in the USI A-46 Regulatory Analysis (NUREG 1211) at pp. 31.We have documented evidence in staff SERs that your plant either has been,or is required to be, reviewed to current licensing requirements forSeismic Qualification of Equipment (i.e., SRP-3.10, IEEE-344/75 and RegulatoryGuide 1.100) and therefore you are inot required to respond to this letter or toperform the plant reviews described in the enclosures.K-tIThe information developed in resolving USI A-46 is described in theto this letter and is being provided to you for information only.enclosuresWe would also like to call to your attention several recent incidents reportedin Licensee Event Reports (LERs) which involved inadequate or missing anchorage.Between late March 1986 and May 1986, three LERs were received that documentedinadequate seismic anchorage of electrical equipment in operating nuclearpower plants. The initial case was at the Davis-Besse 1 plant (LER 86-011)where cabinet doors on Cyberex Class 1E equipment for essential instrument 120aLTI5, 870Cof CARtDao:o oc'53 p0-2-YAC power were found to lack the required door bolts. The second LER concernedemergency diesel generator switchgear cabinets at the Cooper plant that werenot fastened to embedded channels beneath the cabinets (LER 86-009). Thethird deficiency was found at the Dresden 2 and 3 plants, where it wasdetermined that the control room control panels did not have positive anchorageto the floor (LER 86-009). In each instance, the deficiency had existed sinceplant construction and was the-result of Installation errors, since the designdrawings had specified seismic anchorage.. As a consequence of these events, areview was initiated by the NRC Office for Analysis and Evaluation ofOperational Data (AEOD). This review included an LER search which revealedfour other instances of inadequate seismic anchorage or support of safetyrelated electrical equipment plus other related seismic inadequacies.We are enclosing the regulatory a'naysis (NURE& 1211) and the USI A-46technical findings (NUREG1030) for your information. The generic letter,which was issued to each nuclear plant that is required to perform seismicadequacy reviews under the provisions of USI A-46, is included as Appendix Ato NUREG-1211;Sincerely,1IAT.I -.II .Enclosures:L NUREG 1211;2. NUREG 1030cc: Service List':i kHarold R. Denton, DiOffice ul ear_2RRegulationI.., IL II.i.,.II.I

.r ._ _, ALIST OF RECENTLY ISSUED GENERIC LETTERS ' i "GenericLetter No.Date ofI ssuanceSubjectIssued ToGL 87-02 -:', , IVERIFICATION OF SEISMIC 02/19/87ADEQUACY OF MECHANICAL ANDELECTRICAL EQUIPMENT INOPERATING REACTORS CUSI A-46)ALL HOLDERS OFOPERATINGLICENSES NOTREVIEWED TOCURRENTLICENSINGCRITERIA ONSEISMICQUALIFICATIONOF EQUIPMENT4A 'GL 87-01 PUBLIC AVAILABILITY OF THE NRC 01/08/87OPERATOR LICENSING EXAMINATIONQUESTION BANKALL POWERREACTORLICENSEES ANDAPPLICANTS FORAN OPERATINGLICENSEGL 86-17 AVAILABILITY OF NUREG-11699"TECHNICAL FINDINGS RELATED TOGENERIC ISSUE C-BBWR MSIC LEAKAGE AND LEAKAGECONTROL SYSTEM1017/m610/22/e6ALL LICENSEES -4-OF BOILING .WATER REACTORS : -,.I-'GL 86-16GL 66-15GL 86-14GL 86-136L 86-12WESTINGHOUSE ECCS EVALUATIONMODELSINFORMATION RELATING TOCOMPLIANCE WITH 10 CFR 50.49,"EQ OF ELECTRICAL EQUIPMENTIMPORTANI TO SAFETY"OPERATOR LICENSINGEXAMINATIONSPOTENTIAL INCONSISTENCYBETWEEN PLANT SAFETY ANALYSESAND TECHNICAL SPECIFICATIONSCRITERIA FOR UNIQUE

PURPOSE

EXEMPTION FROM CONVERSION FROMTHE USE OF HEU FUEL08/20/8607/23/8607/03/e6ALLPRESSURIZEDWATER REACTORAPPLICANTS ANDLICENSEESALL LICENSEES.AND HOLDERS OFAN APPLICATIONFOR ANOPERATINGLICENSE *ALL POWER -- FREACTORLICENSEES AND-APPLICANTSALL POWERREACTORLICENSEES WITHCE AND B&WPRESSURIZEDWATER REACTORSALL NON-POWERREACTORLICENSEESAUTHORIZED TOUSE HEU FUEL

VAC power were found to lack the required door bolts. The second LER concernedemergency diesel generator switchgear cabinets at the Cooper plant that werenot fastened to embedded channels beneath the cabinets (LER 86-009). Thethird deficiency was found at the Dresden 2 and 3 plants, where it wasdetermined that the control room control panels did not have positive anchorageto the floor (LER 86-009). In each Instance, the deficiency had existed sinceplant construction and was the result of installation errors, since the designdrawings had specified seismic anchorage. As a consequence of these events, areview was initiated by the NRC Office for Analysis and Evaluation ofOperational Data (AEOD). This review included an LER search which revealedfour other instances of inadequate seismic anchorage or support of safetyrelated electrical equipment plus other related seismic inadequacies.We are enclosing the regulatory analysis (NUREG 1211) and the USI A-46technical findings (NUREG 1030) for your information. The generic letter,which was issued to each nuclear plant that is required to perform seismicadequacy reviews under the provisions of USI A-46, is included as Appendix Ato NUREG-1211.Sincerely,Harol R. Denton, DirectorOffice of Nuclear Reactor RegulationEnclosures:1. NUREG 12112. NUREG 1030cc: Service ListDistribution:Central FileDSRO Chron File KEIB Reading File 8703060307H. DentonR. Vollmer AF. HebdonS. RubinT. SpeisB. SheronR. BosnakN. AndersonT. Y. Chang(* see previous concurrence)OFC :EIB:DSR0,* > EIB:DSRO :EIB:DSRO :DD:DSRO :D:DSRO :DDfiRRNAMIE :*TChang/vt :*NAnderson/ :*RBosnak :*BSheron :*TSpeis :R erDATE 3/6 /87 :3/ /87 :3/ /87 :3/ /87 :3/ /87 --- -87 *OFFICIAL RECORD COPY

The second LER concerned emergency diesel generator switchgear cabinets atthe Cooper plant that were not fastened to embedded channels beneath thecabinets (LER 86-009). The third deficiency was found at the Dresden 2 and 3plants, where It was determined that the control room control panels did nothave positive anchorage to the floor (LER 86-009). In each instance, thedeficiency had existed since plant construction and was the result of installationerrors, since the design drawings had specified seismic anchorage. As aconsequence of these events, a review was initiated by the NRC Office forAnalysis and Evaluation of Operational Data (AEOD). This review included anLER search which revealed four other instances of inadequate seismic anchorageor support of safety related electrical equipment plus other related seismicinadequacies. This information is documented in AEOD report "Seismic Anchorsfor Electrical and Control Panels" (AEOD/E611).We are enclosing the generic letter which was issued to each nuclear plantthat is required to perform seismic adequacy reviews under the provisions ofUSI A-46, the regulatory analysis (NUREG 1211) and the USI A-46 TechnicalFindings (NUREG 1030) for your information.Sincerely,Orifinal Signed 8hyrichard H. VollmerHarold R. Denton, DirectorOffice of Nuclear Reactor RegulationEnclosures:1. Generic Letter2. NUREG 12113. NUREG 1030cc: Service ListDistribution:Central Fi S. RubinDSRO Chron File T. SpeisEIB Reading File B. SheronH. Denton R. BosnakR. Vollmer N. AndersonF. Hebdon T. Y. Chang(* see previous concurrence)OFC :EIB:DSRO :EIB:DSRO :DD:DSRO :D:DSRO :DD:WRRI zD:------------___:------------: ------------:- :----i:------ ------_____NAME :NAnderson/dw* RBosnak* :BSheron* :TSpeis* :RY V r :HD~tit n :_____ __ _________ ________ ___ -------- :-- _-. -----------DATE :2/ /87 :2/ /87 :2/ /87 :2/ /87 :2t /87 :2/2(/87OFFICIAL RECORD COPY

S y -aS--IVAC power were found to lack the required door bolts. The second LER concernedemergency diesel generator switchgear cabinets at the Cooper plant that werenot fastened to embedded channels beneath the cabinets (LER 86-009). Thethird deficiency was found at the Dresden 2 and 3 plants, where it wasdetermined that the control room control panels did not have positive anchorageto the floor (LER 86-009). In each instance, the deficiency had existed sinceplant construction and was the result of installation errors, since the designdrawings had specified seismic anchorage. As a consequence of these events, areview was initiated by the NRC Office for Analysis and Evaluation ofOperational Data (AEOD). This review included an LER search which revealedfour other instances of inadequate seismic anchorage or support of safetyrelated electrical equipment plus other related seismic inadequacies.We are enclosing the generic letter which was issued to each nuclear plantthat is required to perform seismic adequacy reviews under the provisions ofUSI A-46, the regulatory analysis (NUREG 1211) and the USI A-46 TechnicalFindings (NUREG 1030) for your information.Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationEnclosures:1. Generic Letter2. NUREG 12113. NUREG 1030cc: Service ListDistribution:Central FileDSRO Chron FileEIB Reading FileH. DentonR. VollmerF. HebdonS. RubinT. SpeisB. SheronR. BosnakN. AndersonT. Y. ChangOFC :EIB:DSRO :EIB:DSi DD: :D: D :DD:NRR :D:NRR---------- ----- -----------NAME :NAnders / w RBosn -:B eron : peis :RVollmer :HDenton-____ -------- --- -- -- -- -- -- -- -- _______ ------------ -----DATE :2/#3 /87 :2//Ig7 & :2/L187 1 2/l 87 :2/ /87 :2/ /87OFFICIAL RECORD COPY