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| | issue date = 09/30/1994 | | | issue date = 09/30/1994 |
| | title = Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original Rept | | | title = Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original Rept |
| | author name = UDY A C | | | author name = Udy A |
| | author affiliation = EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY | | | author affiliation = EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:EGG-DNSP-11487 TECHNICAL EVALUATION REPORTEvaluation ofUtilityResponsetoSupplement 1toNRCBulletin90-01:St.Lucie-I/-2 DocketNos.50-335and50-389AlanC.UdyPublished Septemb'er 1994EGSGIdaho,Inc.IdahoNationalEngineering Laboratory IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatory Commission Washington, D.C.20555UnderDOEContractNo.DE-AC07-76ID01570 FINNo.L1695,TaskNo.11aTACNos.M85446andM85447e4~0a50149 e40e30PDRADOCK05000335',P-,;.PDR~i 0\~ | | {{#Wiki_filter:EGG-DNSP-11487 TECHNICAL EVALUATION REPORT Evaluation of Utility Response to Supplement 1 to NRC Bulletin 90-01: St. Lucie-I/-2 Docket Nos. 50-335 and 50-389 Alan C. Udy Published Septemb'er 1994 EGSG Idaho, Inc. |
| SUMMARYThisreportdocuments theEGKGIdaho,Inc.,reviewoftheFloridaPowerandLightCompanysubmittals thatrespondtoSupplement 1toNRCBulletin90-01forUnitNos.1and2oftheSt.LuciePlant.ThisNRCBulletinprovidesinformation regarding thelossoffill-oilincertainpressureanddifferential pressuretransmitters manufactured byRosemount, Inc.Thisreportfindsthatthelicenseecompliestotherequested actionsandthereporting requirements oftheSupplement.
| | Idaho National Engineering Laboratory Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. L1695, Task No. 11a TAC Nos. M85446 and M85447 PDR P -,; |
| FINNo.L1695,TaskNo.llaBERNo.320-19-15-05-0 DocketNos.50-335and50-389TACNos.M85446andM85447 e
| | e4~0a50149 e40e30 ADOCK 05000335 |
| PREFACEThisreportissuppliedaspartofthe"Technical Assistance inSupportoftheInstrumentation andControlsSystemsBranch."Itisbeingconducted fortheU.S.NuclearRegulatory Commission, OfficeofNuclearReactorRegulation, DivisionofReactorControlsandHumanFactors,byEGLGIdaho,Inc.,DOE/NRCSupportProgramsUnit.
| | .PDR |
| ~~ | | ~i |
| CONTENTSUMMARYo~~~~~~~~~~~~~~~~~~~~~~~~~~t~~~~~~~~~~~~~~~~~~~~~tt~~~~~~~~~SREFACE..............................................................
| | |
| Pill1.INTRODUCTION
| | 0 \ ~ |
| ..~.................................-..........,..... | | |
| 12.NRCSPECIFIED RE(UESTED ACTIONS.................................
| | ==SUMMARY== |
| 43.EVALUATION
| | |
| .....;................................................ | | This report documents the EGKG Idaho, Inc., review of the Florida Power and Light Company submittals that respond to Supplement 1 to NRC Bulletin 90-01 for Unit Nos. 1 and 2 of the St. Lucie Plant. This NRC Bulletin provides information regarding the loss of fill-oil in certain pressure and differential pressure transmitters manufactured by Rosemount, Inc. This report finds that the licensee complies to the requested actions and the reporting requirements of the Supplement. |
| 7'.1Evaluation ofLicenseeResponsetoReporting Requirements | | FIN No. L1695, Task No. lla BER No. 320-19-15-05-0 Docket Nos. 50-335 and 50-389 TAC Nos. M85446 and M85447 |
| .73.2Evaluation ofLicenseeResponsetoRequested Actions......74.CONCLUSIONS | | |
| ..~~~~~~~~~~~~~~~t~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~125.REFERENCES | | e PREFACE This report is supplied as part of the "Technical Assistance in Support of the Instrumentation and Controls Systems Branch." It is being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Reactor Controls and Human Factors, by EGLG Idaho, Inc., DOE/NRC Support Programs Unit. |
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| Evaluation ofUtilitResonsetoSulement1toNRCBulletin90-01:St.Lucie-1-21.INTRODUCTION TheNRCissuedBulletin90-01onMarch9,1990(Reference 1).ThatBulletindiscussed certain,Rosemount pressureanddifferential pressuretransmitter modelsidentified bythemanufacturer aspronetofill-oilleakage.TheBulletinrequested licensees toidentifywhetherthesetransmitters wereormaylaterbeinstalled insafety-related systems.Actionsweredetailedforlicenseeimplementation forcertainidentified transmitters installed inasafety-related system..Thesesameactionsapplytothoseidentified transmitters presently heldininventory forlaterinstallation inasafety-related system.Withthegradualleakageoffill-oil, thetransmitter wouldnothavethelongtermaccuracy, timeresponse, andreliability neededforitsintendedsafetyfunction. | | |
| Further,thiscondition couldgoundetected overalongperiod.Redundant instrument channelsaresubjecttothesamedegradation mechanism. | | CONTENTS S UMMARY o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ tt ~ ~ ~ ~ ~ ~ ~ ~ ~ |
| Thisincreases thepotential foracommonmodefailure.Thus,thispotential failuremechanism raisedconcernforthereliability ofreactorprotection systems(RPS),engineered safetyfeatures(ESF)actuation systems,andanticipated transient withoutscram(ATWS)mitigating systems.Toachievehighfunctional reliability, theremustbealowprobability ofcomponent failurewhileoperating, withanyfailuresreadilydetectable.
| | P REFACE .............................................................. ill |
| Supplement 1toNRCBulletin90-01(Reference 2)wasissuedonDecember22,1992.TheSupplement informedlicensees ofNRCstaffactivities regarding thesubjecttransmitters, andnotedcontinuing reportsoftransmitter failures. | | : 1. INTRODUCTION .. ~...........................................,..... 1 |
| The'RCrequested licenseeactiontoresolvetheissue.TheSupplement alsoupdatedthe.information contained intheoriginalbulletin. | | : 2. NRC SPECIFIED RE(UESTED ACTIONS ................................. 4 |
| Thelicenseewasrequested toreviewtheinformation anddetermine ifitwasapplicable attheirfacility.
| | : 3. E VALUATION .....;................................................ 7'. |
| Further,thelicenseewasrequested tomodifytheiractionsandenhancedsurveillance monitoring programstoconformwiththedirection given.Finally,thelicenseewasinstructed to1 respondtotheNRC.,TheReuestedActionsinSupplement 1toNRCBulletin90-Olsupersede theoriginalNRCBulletin90-01ReuestedActions.Inresponding toSupplement 1toNRCBulletin90-01,thelicenseeisdirectedtoaddressthreeitems.l.Astatement eithercommitting thelicenseetotaketheNRCBulletin90-01,Supplement 1,ReuestedActionsortakingexception tothoseactions.2.Addressing theactionscommitted tointheabovestatement, provide:a~b.C.alistofthespecificactions,including anyjustifications, tobetakentocompletethecommitment, ascheduleforcompletion, andaftercompletion, astatement confirming theactionscommitted toarecomplete. | | 1 Evaluation of Licensee Response to Reporting Requirements . 7 3.2 Evaluation of Licensee Response to Requested Actions ...... 7 |
| 3.Astatement identifying theNRCBulletin90-01,Supplement 1,ReuestedActionsnottaken,alongwithanevaluation providing thebasisforexemption. | | : 4. CONCLUSIONS .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 12 |
| Inimplementing thereplacement'ption oftheNRCReuestedActions,plantshutdownexclusively forreplacing thetransmitters isnotrequired.
| | : 5. R EFERENCES ...................................................... 13 |
| Thisallowance infersthatreplacements canbescheduled.
| | |
| Withreplacement inatimelymanner,enhancedsurveillance monitoring forinterimoperation isnotrequired.
| | ~ |
| TheFloridaPowerandLightCompany,thelicenseeforUnitNos.1and2oftheSt.LuciePlant,responded toSupplement 1ofNRCBulletin90-01withaletterdatedHarch5,1993(Reference 3).Thelicenseeprovidedadditional information onMarch9,1994(Reference 4).ThelicenseenotifiedtheNRCthattheirtransmitter replacements werecompleteonAugust18,1994(Reference 5).Thistechnical evaluation reportevaluates thecompleteness o'2 thosesubmittals.
| | ~ |
| Italsodetermines whetherproposedsurveillance methodsareadequatetodetermine fill-oilloss-caused degradation ofthetransmitter..
| | |
| Finally,thisreportaddresses theintervalofsurveillance proposedbythelicenseefor'anytransmitters includedintheenhancedsurveillance monitoring program.HanyRosemount transmitter failureshavebeenattributed totheuseofstainless steel"0"-rings betweenthesensingmoduleandtheprocessflanges.Rosemount improvedthemanufacturing processfortransmitters manufactured afterJulyll,1989.Thoseimprovements includedalimitofthetorqueappliedtotheflangebolts.Thislimitsthestresscausedinthesensingmodulebythe"0"-ring. | | Evaluation of Utilit Res onse to Su lement 1 to NRC Bulletin 90-01: St. Lucie-1 -2 |
| Post-production screening, including pressuretestingofthesensingmoduleforthispotential latentdefect,wasalsoimplemented atthattime.Therefore, asdescribed inSupplement 1ofNRCBulletin90-01,thoseRosemount transmitters manufactured afterJuly11,1989,arenotsubjecttothisreview. | | : 1. INTRODUCTION The NRC issued Bulletin 90-01 on March 9, 1990 (Reference 1). That Bulletin discussed certain, Rosemount pressure and differential pressure transmitter models identified by the manufacturer as prone to fill-oil leakage. The Bulletin requested licensees to identify whether these transmitters were or may later be installed in safety-related systems. |
| 2.NRCSPECIFIED REQUESTED ACTIONSTheNRCstaffspecified thefollowing ReuestedActionsoflicensees ofoperating reactors. | | Actions were detailed for licensee implementation for certain identified transmitters installed in a safety-related system.. These same actions apply to those identified transmitters presently held in inventory for later installation in a safety-related system. |
| 1.Reviewplantrecordsandidentifythefollowing Rosemount transmitters (ifmanufactured beforeJuly11,1989)thateitherareusedinormaybeusedineithersafety-related orATWSmitigating systems.Rosemount Hodel1153,SeriesBRosemount Hodel1153,SeriesDRosemount Hodel1154Following identification, thelicenseeistoestablish thefollowing: | | With the gradual leakage of fill-oil, the transmitter would not have the long term accuracy, time response, and reliability needed for its intended safety function. Further, this condition could go undetected over a long period. Redundant instrument channels are subject to the same degradation mechanism. This increases the potential for a common mode failure. Thus, this potential failure mechanism raised concern for the reliability of reactor protection systems (RPS), engineered safety features (ESF) actuation systems, and anticipated transient without scram (ATWS) mitigating systems. To achieve high functional reliability, there must be a low probability of component failure while operating, with any failures readily detectable. |
| 'a~Forthoseidentified transmitters havinganormaloperating pressuregreaterthan1500psi,andareinstalled aspartofreactorprotection tripsystems,ESFactuation systems,orATWSmitigating systems,eitherreplacethetransmitter inanexpedited manner,ormonitormonthly,forthelifeofthetransmitter, usinganenhancedsurveillance program.Iftheidentified transmitter exceedsthe60,000psi-month orthe130,000psi-month criterion (depending ontherangecodeofthetransmitter) established byRosemount, enhancedsurveillance onarefueling (notexceeding 24months)basisisacceptable. | | Supplement 1 to NRC Bulletin 90-01 (Reference 2) was issued on December 22, 1992. The Supplement informed licensees of NRC staff activities regarding the subject transmitters, and noted continuing reports of transmitter failures. The'RC requested licensee action to resolve the issue. |
| Underthisoption,justification mustbebasedontheservicerecordandthespecificsafetyfunctionofthetransmitter.
| | The Supplement also updated the. information contained in the original bulletin. The licensee was requested to review the information and determine if it was applicable at their facility. Further, the licensee was requested to modify their actions and enhanced surveillance monitoring programs to conform with the direction given. Finally, the licensee was instructed to 1 |
| Thatjustification canbebasedonhighfunctional reliability providedbyredundancy ordiversity.
| | |
| b.Forthoseidentified transmitters havinganormaloperating pressuregreaterthan1500psi,andareinstalled aspartofasafety-related systemotherthanreactorprotection tripsystems,ESFactuation, orATWSmitigating systems,eitherreplacethetransmitter ormonitorquarterly, forthelifeofthetransmitter, usinganenhancedsurveillance program.Iftheidentified transmitter exceedsthe60,000psi-month orthe130,000psi-month criterion (depending ontherangecodeofthetransmitter) established byRosemount, enhancedsurveillance onarefueling (notexceeding 24months)basisisacceptable. | | respond to the NRC. ,The Re uested Actions in Supplement 1 to NRC Bulletin 90-Ol supersede the original NRC Bulletin 90-01 Re uested Actions. |
| Underthisoption,justification mustbebasedontheservicerecordandthespecificsafetyfunctionofthetransmitter.
| | In responding to Supplement 1 to NRC Bulletin 90-01, the licensee is directed to address three items. |
| That justification canbebasedonhighfunctional reliability providedbyredundancy ordiversity.
| | : l. A statement either committing the licensee to take the NRC Bulletin 90-01, Supplement 1, Re uested Actions or taking exception to those actions. |
| Forboilingwaterreactors(BWR)--Forthoseidentified transmitters havinganormaloperating pressuregreaterthan500psiandlessthanorequalto1500psi,andareinstalled aspartofreactorprotection tripsystems,ESFactuation systems,orATWSmitigating systems,eitherreplacethetransmitter, ormonitormonthlywithanenhancedsurveillance monitoring program,untilthetransmitter reachesthedesignated (byRosemount) psi-month criterion (60,000psi-month or130,000psi-month, depending onthetransmitter rangecode).Fortransmitters thatprovidesignalstotheRPSorATWStripsforhighpressureorlowwaterlevel,theenhancedsurveillance mustbemonthly.Forothertransmitters inthisclassification, enhancedsurveillance onarefueling (notexceeding 24months)basisisacceptable.
| | : 2. Addressing the actions committed to in the above statement, provide: |
| Underthisoption,justification mustbebasedontheservice.recordandthespecificsafetyfunctionofthetransmitter.
| | a ~ a list of the specific actions, including any justifications, to be taken to complete the commitment, |
| Thatjustification canbebasedonhighfunctional reliability providedbyredundancy ordiversity.
| | : b. a schedule for completion, and C. after completion, a statement confirming the actions committed to are complete. |
| Forpressurized waterreactors(PWR)--Forthoseidentified transmitters havinganormaloperating pressuregreaterthan500psiandlessthanorequalto1500psi,andareinstalled as.partofreactorprotection tripsystems,ESFactuation systems,orATWSmitigating systems,eitherreplacethetransmitter, ormonitorwithanenhancedsurveillance monitoring program,untilthetransmitter reachesthedesignated (byRosemount) psi-month criterion (60,000psi-month or130,000psi-month, depending onthetransmitter rangecode)onarefueling (notexceeding 24months)basis.Forthoseidentified transmitters havinganormaloperating pressuregreaterthan500psiandlessthanorequalto1500psi,andareinstalled aspartofasafety-related systemotherthanreactorprotection tripsystems,ESFactuation, orATWSmitigating systems,eitherreplacethetransmitter, ormonitorwithanenhancedsurveillance monitoring program,untilthetransmitter reachesthedesignated (byRosemount) psi-month criterion (60,000psi-month or130,000psi-month, depending onthetransmitter rangecode)onarefueling (notexceeding 24months)basis.
| | : 3. A statement identifying the NRC Bulletin 90-01, Supplement 1, Re uested Actions not taken, along with an evaluation providing the basis for exemption. |
| e.Thosetransmitters havinganormaloperating pressuregreaterthan500psiandlessthanorequalto1500psi,andhaveaccumulated sufficient psi-month operating historytoexceedthecriterion established byRosemount, maybeexcludedfromtheenhancedsurvei.llance monitoring programatthediscretion ofthelicensee. | | In implementing the replacement'ption of the NRC Re uested Actions, plant shutdown exclusively for replacing the transmitters is not required. |
| However,thelicenseeshouldretainahigh'evel ofconfidence thatahighlevelofreliability ismaintained andthattransmitter failureduetolossoffill-oilisdetectable. | | This allowance infers that replacements can be scheduled. With replacement in a timely manner, enhanced surveillance monitoring for interim operation is not required. |
| Thosetransmitters havinganormaloperating pressurelessthanorequalto500psimaybeexcludedfromtheenhancedsurveillance monitoring programatthediscretion ofthelicensee.
| | The Florida Power and Light Company, the licensee for Unit Nos. 1 and 2 of the St. Lucie Plant, responded to Supplement 1 of NRC Bulletin 90-01 with a letter dated Harch 5, 1993 (Reference 3). The licensee provided additional information on March 9, 1994 (Reference 4). The licensee notified the NRC that their transmitter replacements were complete on August 18, 1994 (Reference 5). This technical evaluation report evaluates the completeness o' 2 |
| However,thelicenseeshouldretainahighlevelofconfidence thatahighlevelofreliability ismaintained andthattransmitter failureduetolossoffill'-oil isdetectable. | | |
| 2.Evaluatetheenhancedsurveillance monitoring program.Theevaluation istoensurethemeasurement datahasanaccuracycommensurate withtheaccuracyneededtocomparethedatatothemanufacturers driftdatacriteria. | | those submittals. It also determines whether proposed surveillance methods are adequate to determine fill-oil loss-caused degradation of the transmitter.. |
| Itisthiscomparison thatdetermines thedegradation threshold forlossoffill-oilfailuresofthesubjecttransmitters.
| | Finally, this report addresses the interval of surveillance proposed by the licensee for 'any transmitters included in the enhanced surveillance monitoring program. |
| TheSupplement alsostatestheNRCmayconductauditsorinspections inthefuturetoverifycompliance withtheestablished requirements.
| | Hany Rosemount transmitter failures have been attributed to the use of stainless steel "0"-rings between the sensing module and the process flanges. |
| 3.EVALUATION Thelicenseeresponded toSupplement 1ofNRCBulletin90-01onMarch5,1993.Thelicenseeprovidedadditional information onMarch9,1994.ThelicenseenotifiedtheNRCthattheirtransmitter replacements werecompleteonAugust19,1994.Thoseresponses werecomparedtotheBulletin~Reortinddidibdb1.ThhavingRosemount transmitters thataresubjecttotheReuestedActionsoftheSupplement. | | Rosemount improved the manufacturing process for transmitters manufactured after July ll, 1989. Those improvements included a limit of the torque applied to the flange bolts. This limits the stress caused in the sensing module by the "0"-ring. Post-production screening, including pressure testing of the sensing module for this potential latent defect, was also implemented at that time. Therefore, as described in Supplement 1 of NRC Bulletin 90-01, those Rosemount transmitters manufactured after July 11, 1989, are not subject to this review. |
| OtherRosemount transmitters are'outside thescopeoftheSupplement duetoreplacement orrefurbishment.
| | : 2. NRC SPECIFIED REQUESTED ACTIONS The NRC staff specified the following Re uested Actions of licensees of operating reactors. |
| 3.1Evaluation ofLicenseeResonsetoReortinReuirements Thelicenseestates,inReference 3,thattheyintendtoimplement theReuestedActionsdetailedinSupplement 1ofNRCBulletin90-01.Includedwiththatstatement isclarification, interpretation, andthelimitsplacedonthatcommitment. | | : 1. Review plant records and identify the following Rosemount transmitters (if manufactured before July 11, 1989) that either are used in or may be used in either safety-related or ATWS mitigating systems. |
| Thelicenseedescribed thespecificactionstakentoexecutetheReuestedActions.Thelicenseeprovidedastatement thatthe~ReuestedActionsarecompleteonAugust18,1994.Thelicenseesubmitt'als conformtotheReortinReuirements ofSupplement 1ofNRC,Bulletin 90-01.3.2Evaluation ofLicenseeResonsetoReuestedActionsSupplement 1ofNRCBulletin90-01requested licenseeactiontoresolvetheissueoffill-oilleakageinRosemount transmitters.
| | Rosemount Hodel 1153, Series B Rosemount Hodel 1153, Series D Rosemount Hodel 1154 Following identification, the licensee is to establish the following: |
| ThisTechnical Evaluation Reportsummarizes theReuestedActionsandtheassociated transmi'tter criteriainSection2.Rosemount transmitters manufactured afterJuly11,1989arenotsubjecttotheSupplement requirements oranenhancedsurveillance monitoring program.Thelicensee'esponse totheSupplement isdiscussed inthefollowing sections.
| | 'a ~ For those identified transmitters having a normal operating pressure greater than 1500 psi, and are installed as part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter in an expedited manner, or monitor monthly, for the life of the transmitter, using an enhanced surveillance program. |
| 3.2.1LicenseeResonsetoReuestedAction1.aUnitNo.1ThelicenseestatesthereareRosemount transmitters fromthistransmitter classification atUnitNo.1oftheSt.LuciePlant.Thelicenseescheduled thesubjecttransmitters forreplacement inthespringof1993.However,thelicenseecommi.tted thatifadelayintransmitter installation | | If the identified transmitter exceeds the 60,000 psi-month or the 130,000 psi-month criterion (depending on the range code of the transmitter) established by Rosemount, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be based on the service record and the specific safety function of the transmitter. That justification can be based on high functional reliability provided by redundancy or diversity. |
| : occurred, thelicenseewillmonitorthattransmitter monthlyaspartoftheirenhancedsurveillance monitoring program.Thelicenseestatedtheywillnotincreasethesurveillance intervalfrommonthlywithoutproviding justification totheNRC.Thelicenseeactionsfortransmitters intransmitter classification l.aatUnitNo.1areacceptable.
| | : b. For those identified transmitters having a normal operating pressure greater than 1500 psi, and are installed as part of a safety-related system other than reactor protection trip systems, ESF actuation, or ATWS mitigating systems, either replace the transmitter or monitor quarterly, for the life of the transmitter, using an enhanced surveillance program. |
| AsnotedinReference 5,thelicenseeactionsforthistransmitter classification arecomplete, andthetransmitters replacedasscheduled.
| | If the identified transmitter exceeds the 60,000 psi-month or the 130,000 psi-month criterion (depending on the range code of the transmitter) established by Rosemount, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be based on the service record and the specific safety function of the transmitter. That |
| UnitNo.2ThelicenseestatesthereareRosemount transmitters fromthistransmitter classification atUnitNo.2oftheSt.LuciePlant.However,allUnitNo.2Rosemount transmitters inthistransmitter classification weremanufactured afterJuly11,1989,andareexemptfromtheSupplement requirements.
| | |
| 3.2.2LicenseeResonsetoReuestedAction1.b.UnitNo.1ThelicenseestatesthereareRosemount transmitters fromthistransmitter classification atUnitNo.1oftheSt.LuciePlant.Thelicenseescheduled thesubjecttransmitters forreplacement inthespringof1993.However,thelicenseecommitted, inReference 3,thatifadelayintransmitter installation | | justification can be based on high functional reliability provided by redundancy or diversity. |
| : occurred, thelicenseewillmonitorthattransmitter quarterly aspartoftheirenhancedsurveillance monitoring program.Thelicenseestatestheywillnotincreasethesurveillance intervalfromquarterly withoutproviding justification totheNRC.Thelicenseeactionsfortransmitters intransmitter classification 1.batUnitNo.1areacceptable.
| | For boiling water reactors (BWR)-- |
| AsnotedinReference 5,thelicenseeactionsforthistransmitter classification arecomplete, andthetransmitters replaced.
| | For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and are installed as part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter, or monitor monthly with an enhanced surveillance monitoring program, until the transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code). |
| asscheduled.
| | For transmitters that provide signals to the RPS or ATWS trips for high pressure or low water level, the enhanced surveillance must be monthly. For other transmitters in this classification, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be based on the service .record and the specific safety function of the transmitter. That justification can be based on high functional reliability provided by redundancy or diversity. |
| UnitNo.2ThelicenseestatesthereareRosemount transmitters fromthistransmitter classification atUnitNo.2oftheSt.LuciePlant.Thelicenseescheduled thesubjecttransmitters forreplacement inthefallof1993.Thelicenseecommitted, inReference 3,tomonitorthesetransmitters quarterly aspartoftheenhancedsurveillance monitoring programuntilreplaced.
| | For pressurized water reactors (PWR)-- |
| SomeoftheUnitNo.2Rosemount transmitters weremanufactured afterJulyll,1989,andareexemptfromtheSupplement requirements.
| | For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and are installed as. part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter, or monitor with an enhanced surveillance monitoring program, until the transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code) on a refueling (not exceeding 24 months) basis. |
| Thelicenseeactionsfortransmitters intransmitter classification 1.batUnitNo.2areacceptable.
| | For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and are installed as part of a safety-related system other than reactor protection trip systems, ESF actuation, or ATWS mitigating systems, either replace the transmitter, or monitor with an enhanced surveillance monitoring program, until the transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code) on a refueling (not exceeding 24 months) basis. |
| AsnotedinReference 5,thelicenseeactionsforthistransmitter classification arecomplete, andthetransmitters replacedasscheduled.
| | : e. Those transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and have accumulated sufficient psi-month operating history to exceed the criterion established by Rosemount, may be excluded from the enhanced survei.llance monitoring program at the discretion of the licensee. |
| 3.2.3LicenseeResonsetoReuestedAction1.cThelicenseestatesthereareRosemount transmitters fromthistransmitter classification attheSt.LuciePlant.Thelicenseestatesthatthesetransmitters willparticipate inanenhancedsurveillance monitoring programonarefueling basis.Theintervalwillnotexceed24months.Eitherreplacement orsuccessfully achieving thepsi-month maturitythreshold willremoveatransmitter fromtheenhancedsurveillance monitoring program.Replacement withatransmitter manufactured afterJuly11,1989,removesthetransmitter fromtheSupplement requirements. | | However, the licensee should retain a high'evel of confidence that a high level of reliability is maintained and that transmitter failure due to loss of fill-oil is detectable. |
| Successfully achieving maturitytransfers thetransmitter totransmitter classification l.e.SeeSection3.2.5. | | Those transmitters having a normal operating pressure less than or equal to 500 psi may be excluded from the enhanced surveillance monitoring program at the discretion of the licensee. However, the licensee should retain a high level of confidence that a high level of reliability is maintained and that transmitter failure due to loss of fill'-oil is detectable. |
| 3.2.4LicenseeResonsetoReuestedAction1.dThelicenseestatesthereareRosemount transmitters fromthistransmitter classification attheSt.LuciePlant.Thelicenseestatesthatthesetransmitters willparticipate inanenhancedsurveillance-monitoring programonarefueling basis.Theintervalwillnotexceed24months.Eitherreplacement orsuccessfully achieving thepsi-month maturitythreshold willremove'atransmitter fromtheenhancedsurveillance monitoring program.Replacement withatransmitter manufactured afterJuly11,1989,removesthetransmitter fromtheSupplement requirements. | | : 2. Evaluate the enhanced surveillance monitoring program. The evaluation is to ensure the measurement data has an accuracy commensurate with the accuracy needed to compare the data to the manufacturers drift data criteria. It is this comparison that determines the degradation threshold for loss of fill-oil failures of the subject transmitters. |
| Successfully achieving maturitytransfers thetransmitter totransmitter classification l.e.SeeSection3.2.5.3.2.5LicenseeResonsetoReuestedActionl.eAstransmitters intransmitter classification 1.cand1.dexceedthepsi-month maturitythreshold, thelicenseewillremovethosetransmitters fromtheenhancedsurveillance monitoring program.TheSupplement'ermits thisaction.TheSupplement requiresthelicenseetomaintainahighdegreeofconfidence thatthesetransmitters remainhighlyreliable. | | The Supplement also states the NRC may conduct audits or inspections in the future to verify compliance with the established requirements. |
| Thelicenseestatesthatbeforeremovingatransmitter fromtheenhancedsurveillance monitoring program,thetransmitter willexhibitnoexcessive driftorsluggishness.
| | : 3. EVALUATION The licensee responded to Supplement 1 of NRC Bulletin 90-01 on March 5, 1993. The licensee provided additional information on March 9, 1994. The licensee notified the NRC that their transmitter replacements were complete on August 19, 1994. Those responses were compared to the Bulletin ~Re ortin d d i d ib d b 1 . Th having Rosemount transmitters that are subject to the Re uested Actions of the Supplement. Other Rosemount transmitters are'outside the scope of the Supplement due to replacement or refurbishment. |
| Thelicenseestatesthatexistingmaintenance andsurveillance programscandetectfuturefailuresduetothelossoffill-oil.
| | : 3. 1 Evaluation of Licensee Res onse to Re ortin Re uirements The licensee states, in Reference 3, that they intend to implement the Re uested Actions detailed in Supplement 1 of NRC Bulletin 90-01. Included with that statement is clarification, interpretation, and the limits placed on that commitment. The licensee described the specific actions taken to execute the Re uested Actions. The licensee provided a statement that the ~Re uested Actions are complete on August 18, 1994. |
| 3.2.6LicenseeResonsetoReuestedAction1.fThelicenseestatesthereareRosemount transmitters fromthisclassification attheSt.LuciePlant.Atlicenseediscretion, thesetransmitters arenotpartoftheenhancedsurveillance monitoring program.TheSupplement permitsthisaction.10 TheSupplement requiresthelicenseetomaintainahighdegreeofconfidence thatthesetransmitters remainhighlyreliable. | | The licensee submitt'als conform to the Re ortin Re uirements of Supplement 1 of NRC,Bulletin 90-01. |
| Thel,icensee statesthatexistingmaintenance andsurveillance programscandetectfuturefailuresduetothelossoffill-oil.
| | 3.2 Evaluation of Licensee Res onse to Re uested Actions Supplement 1 of NRC Bulletin 90-01 requested licensee action to resolve the issue of fill-oil leakage in Rosemount transmitters. This Technical Evaluation Report summarizes the Re uested Actions and the associated transmi'tter criteria in Section 2. Rosemount transmitters manufactured after July 11, 1989 are not subject to the Supplement requirements or an enhanced surveillance monitoring program. The licensee'esponse to the Supplement is discussed in the following sections. |
| 3.2.7EnhancedSurveillance Nonitorin ProramThelicenseedescribed themonitoring'intervals forthedifferent transmitter classifications. | | |
| Thelicensee, inaddressing ReuestedAction2oftheSupplement, statestheirenhancedsurveillance monitoring programusestheguidelines ofRosemount Technical BulletinNo.4.Following theguidelines ofRosemount Technical BulletinNo.4satisfies therequirements oftheSupplement andisacceptable.
| | 3.2. 1 Licensee Res onse to Re uested Action 1.a Unit No. 1 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 1 of the St. Lucie Plant. The licensee scheduled the subject transmitters for replacement in the spring of 1993. |
| 4.CONCLUSIONS Basedonourreview,wefindthelicenseehascompleted thereporting requirements ofSupplement 1ofNRCBulletin90-01.Further,thelicenseeconformstotheReuestedActionsofSupplement 1toNRCBulletin90-01.12 5.REFERENCES NRCBulletinNo.90-01:"LossofFill-oilinTransmitters Manufactured byRosemount," | | However, the licensee commi.tted that if a delay in transmitter installation occurred, the licensee will monitor that transmitter monthly as part of their enhanced surveillance monitoring program. The licensee stated they will not increase the surveillance interval from monthly without providing justification to the NRC. The licensee actions for transmitters in transmitter classification l.a at Unit No. 1 are acceptable. As noted in Reference 5, the licensee actions for this transmitter classification are complete, and the transmitters replaced as scheduled. |
| March9,1990,OHBNo.3150-0011.
| | Unit No. 2 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 2 of the St. Lucie Plant. However, all Unit No. 2 Rosemount transmitters in this transmitter classification were manufactured after July 11, 1989, and are exempt from the Supplement requirements. |
| NRCBulletinNo.90-01,Supplement 1:"LossofFill-oilinTransmitters Manufactured byRosemount,"
| | 3.2.2 Licensee Res onse to Re uested Action 1.b. |
| December22,1992,OMBNo.3150-0011.
| | Unit No. 1 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 1 of the St. Lucie Plant. The licensee scheduled the subject transmitters for replacement in the spring of 1993. |
| Letter,Florida.PowerandLightCompany(D.A.Sager)toNRC,"NRCBulletin90-01Supplement 1Response," | | However, the licensee committed, in Reference 3, that if a delay in transmitter installation occurred, the licensee will monitor that transmitter |
| March5,1993,L-93-61.Letter,FloridaPowerandLightCompany(D.A.Sager)toNRC,"NRCBulletin90-01Supplement 1Additional Information,"
| | |
| March9,1994,L-94-061.
| | quarterly as part of their enhanced surveillance monitoring program. The licensee states they will not increase the surveillance interval from quarterly without providing justification to the NRC. The licensee actions for transmitters in transmitter classification 1.b at Unit No. 1 are acceptable. As noted in Reference 5, the licensee actions for this transmitter classification are complete, and the transmitters replaced. as scheduled. |
| L'etter,FloridaPowerandLightCompany(D.A.Sager)toNRC,"NRCBulletin90-01Supplement 1Additional Information," | | Unit No. 2 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 2 of the St. Lucie Plant. The licensee scheduled the subject transmitters for replacement in the fall of 1993. The licensee committed, in Reference 3, to monitor these transmitters quarterly as part of the enhanced surveillance monitoring program until replaced. Some of the Unit No. 2 Rosemount transmitters were manufactured after July ll, 1989, and are exempt from the Supplement requirements. The licensee actions for transmitters in transmitter classification 1.b at Unit No. 2 are acceptable. |
| August18,1994,L-94-210.
| | As noted in Reference 5, the licensee actions for this transmitter classification are complete, and the transmitters replaced as scheduled. |
| | 3.2.3 Licensee Res onse to Re uested Action 1.c The licensee states there are Rosemount transmitters from this transmitter classification at the St. Lucie Plant. The licensee states that these transmitters will participate in an enhanced surveillance monitoring program on a refueling basis. The interval will not exceed 24 months. Either replacement or successfully achieving the psi-month maturity threshold will remove a transmitter from the enhanced surveillance monitoring program. |
| | Replacement with a transmitter manufactured after July 11, 1989, removes the transmitter from the Supplement requirements. Successfully achieving maturity transfers the transmitter to transmitter classification l.e. See Section 3.2.5. |
| | |
| | 3.2.4 Licensee Res onse to Re uested Action 1.d The licensee states there are Rosemount transmitters from this transmitter classification at the St. Lucie Plant. The licensee states that these transmitters will participate in an enhanced surveillance-monitoring program on a refueling basis. The interval will not exceed 24 months. Either replacement or successfully achieving the psi-month maturity threshold will remove'a transmitter from the enhanced surveillance monitoring program. |
| | Replacement with a transmitter manufactured after July 11, 1989, removes the transmitter from the Supplement requirements. Successfully achieving maturity transfers the transmitter to transmitter classification l.e. See Section 3.2.5. |
| | 3.2.5 Licensee Res onse to Re uested Action l.e As transmitters in transmitter classification 1.c and 1.d exceed the psi-month maturity threshold, the licensee will remove those transmitters from the enhanced surveillance monitoring program. The Supplement'ermits this action. |
| | The Supplement requires the licensee to maintain a high degree of confidence that these transmitters remain highly reliable. The licensee states that before removing a transmitter from the enhanced surveillance monitoring program, the transmitter will exhibit no excessive drift or sluggishness. The licensee states that existing maintenance and surveillance programs can detect future failures due to the loss of fill-oil. |
| | 3.2.6 Licensee Res onse to Re uested Action 1.f The licensee states there are Rosemount transmitters from this classification at the St. Lucie Plant. At licensee discretion, these transmitters are not part of the enhanced surveillance monitoring program. |
| | The Supplement permits this action. |
| | 10 |
| | |
| | The Supplement requires the licensee to maintain a high degree of confidence that these transmitters remain highly reliable. The l,icensee states that existing maintenance and surveillance programs can detect future failures due to the loss of fill-oil. |
| | 3.2.7 Enhanced Surveillance Nonitorin Pro ram The licensee described the monitoring'intervals for the different transmitter classifications. The licensee, in addressing Re uested Action 2 of the Supplement, states their enhanced surveillance monitoring program uses the guidelines of Rosemount Technical Bulletin No. 4. Following the guidelines of Rosemount Technical Bulletin No. 4 satisfies the requirements of the Supplement and is acceptable. |
| | : 4. CONCLUSIONS Based on our review, we find the licensee has completed the reporting requirements of Supplement 1 of NRC Bulletin 90-01. Further, the licensee conforms to the Re uested Actions of Supplement 1 to NRC Bulletin 90-01. |
| | 12 |
| | : 5. REFERENCES NRC Bulletin No. 90-01: "Loss of Fill-oil in Transmitters Manufactured by Rosemount," March 9, 1990, OHB No. 3150-0011. |
| | NRC Bulletin No. 90-01, Supplement 1: "Loss of Fill-oil in Transmitters Manufactured by Rosemount," December 22, 1992, OMB No. 3150-0011. |
| | Letter, Florida. Power and Light Company (D. A. Sager) to NRC, "NRC Bulletin 90-01 Supplement 1 Response," March 5, 1993, L-93-61. |
| | Letter, Florida Power and Light Company (D. A. Sager) to NRC, "NRC Bulletin 90-01 Supplement 1 Additional Information," March 9, 1994, L-94-061. |
| | L'etter, Florida Power and Light Company (D. A. Sager) to NRC, "NRC Bulletin 90-01 Supplement 1 Additional Information," August 18, 1994, L-94-210. |
| 13}} | | 13}} |
Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original ReptML17228A885 |
Person / Time |
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Site: |
Saint Lucie |
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Issue date: |
09/30/1994 |
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From: |
Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
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To: |
NRC |
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Shared Package |
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ML17228A883 |
List: |
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References |
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CON-FIN-L-1695 EGG-DNSP-11487, EGG-DNSP-11487-ERR, IEB-90-001, IEB-90-1, TAC-M85446, TAC-M85447, NUDOCS 9410250149 |
Download: ML17228A885 (21) |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML17229B0671999-03-16016 March 1999 Technical Evaluation Rept, Florida Power & Light Co, Unit 1 Third Ten-Year Interval Pump & Valve Inservice Testing Program,Unit 2 Second Ten-Year Interval Pump & Valve Inservice Testing Program. ML17355A2801998-09-30030 September 1998 Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point. ML17229B0011998-01-31031 January 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at St Lucie Nuclear Plant,Units 1 & 2. ML17229A4151997-05-27027 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for St Lucie Nuclear Plant. ML17228B1261995-03-31031 March 1995 Technical Evaluation Rept on Second 10-Year Interval Insp Program Plan. ML17309A7471994-09-30030 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001:St.Lucie-1/-2. ML17228A8851994-09-30030 September 1994 Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original Rept ML20138E1481993-06-22022 June 1993 Pump & Valve Inservice Testing Program St Lucie Unit 2 FPL, Technical Evaluation Rept ML20105D0871992-08-31031 August 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the St. Lucie Unit 1 Nuclear Power Generation Station ML17309A6651991-11-30030 November 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,St Lucie-Unit 1. ML17223B3231991-08-31031 August 1991 TER of Topical Rept CEN-396-P (Verification of Acceptability of a 1-PIN Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2). ML17308A5041990-08-17017 August 1990 Final Technical Evaluation Rept St Lucie Unit 1 Station Blackout Evaluation. ML17308A4821989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components,St Lucie 1/2, Technical Evaluation Rept ML17222A7411989-01-31031 January 1989 Technical Evaluation Rept on Second Ten-Year Interval Inservice Insp Program Plan:Florida Power & Light Co,St Lucie Plant,Unit 1. ML17223A1321988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 2. ML17223A1291988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 1. ML20244C2931988-11-30030 November 1988 Review of Florida Power & Light Co Safety Evaluations for Extending St Lucie Plant,Unit 2,ESFAS Subgroup Relay Test Interval, Technical Evaluation Rept ML17308A4461988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at St Lucie Unit 2. ML20196G2921988-02-29029 February 1988 Technical Evaluation Rept,Evaluation of High Density Spent Fuel Rack Structural Analysis for St Lucie Plant - Unit 1 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML17308A2391987-06-30030 June 1987 Integrated Leak Rate Test for St Lucie Nuclear Power Plant (Unit 2) Apr 1987-June 1987, Technical Evaluation Rept ML17219A6871987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2, 'Vendor Interface Program for All Other Safety-Related Components:St Lucie 1 & 2,' Final Rept ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML17308A2891987-01-31031 January 1987 Review of Tech Spec Changes Supporting NUREG-0737 Accident Instrumentation,St Lucie Units 1 & 2, Technical Evaluation Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML17308A2421986-05-31031 May 1986 Rev 1 to Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML17308A2151986-04-30030 April 1986 First Interval Inservice Insp Program,St Lucie Unit 2, Technical Evaluation Rept ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML17216A4331986-01-13013 January 1986 SPDS Progress Review,St Lucie 1 & 2. ML17301A1841985-06-17017 June 1985 Masonry Wall Design (B-59),Florida Power & Light Co,St Lucie Unit 1, Technical Evaluation Rept ML17301A1671985-02-28028 February 1985 Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML20080E0711984-01-13013 January 1984 Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept ML17301A0621983-10-31031 October 1983 Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase Ii). ML17214A6931983-10-31031 October 1983 Conformance to NRR Generic Ltr 82-16,St Lucie Plant,Units 1 & 2, Preliminary Rept ML17214A2041983-04-30030 April 1983 Draft Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase I), Technical Evaluation Rept ML17214A1581983-04-29029 April 1983 Control of Heavy Loads (C-10) St Lucie Unit 1, Draft Technical Evaluation Rept ML17214A1551983-04-26026 April 1983 Radiological Effluent Tech Specs (RETS) Implementation - St Lucie Unit 1 Nuclear Generating Plant. ML17214A4541983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML17301A0131982-11-24024 November 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),St Lucie Unit 1, Technical Evaluation Rept ML20065U2351982-10-31031 October 1982 Technical Evaluation Rept of Overpressure Mitigation Sys for St Lucie,Unit 1 ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML17301A0011982-09-28028 September 1982 ECCS Repts (F-47),TMI Action Plan Requirements,St Lucie Unit 1, Technical Evaluation Rept ML17213A7321982-09-17017 September 1982 Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20066B3231982-08-31031 August 1982 Audit of Environ Qualification of Safety-Related Electrical Equipment at St Lucie Unit 2 Nuclear Generating Station, Interim Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20062E2041982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations:Saint Lucie Case Study.Docket Nos. 50-335 and 50-389.(Florida Power and Light Company) ML17212B7831982-05-31031 May 1982 Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant Unit 2,FL Power & Light Co, Draft Technical Evaluation Rept ML20052B5341982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, St Lucie,Unit 1, Technical Evaluation Rept 1999-03-16
[Table view] Category:QUICK LOOK
MONTHYEARML17229B0671999-03-16016 March 1999 Technical Evaluation Rept, Florida Power & Light Co, Unit 1 Third Ten-Year Interval Pump & Valve Inservice Testing Program,Unit 2 Second Ten-Year Interval Pump & Valve Inservice Testing Program. ML17355A2801998-09-30030 September 1998 Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point. ML17229B0011998-01-31031 January 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at St Lucie Nuclear Plant,Units 1 & 2. ML17229A4151997-05-27027 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for St Lucie Nuclear Plant. ML17228B1261995-03-31031 March 1995 Technical Evaluation Rept on Second 10-Year Interval Insp Program Plan. ML17309A7471994-09-30030 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001:St.Lucie-1/-2. ML17228A8851994-09-30030 September 1994 Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original Rept ML20138E1481993-06-22022 June 1993 Pump & Valve Inservice Testing Program St Lucie Unit 2 FPL, Technical Evaluation Rept ML20105D0871992-08-31031 August 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the St. Lucie Unit 1 Nuclear Power Generation Station ML17309A6651991-11-30030 November 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,St Lucie-Unit 1. ML17223B3231991-08-31031 August 1991 TER of Topical Rept CEN-396-P (Verification of Acceptability of a 1-PIN Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2). ML17308A5041990-08-17017 August 1990 Final Technical Evaluation Rept St Lucie Unit 1 Station Blackout Evaluation. ML17308A4821989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components,St Lucie 1/2, Technical Evaluation Rept ML17222A7411989-01-31031 January 1989 Technical Evaluation Rept on Second Ten-Year Interval Inservice Insp Program Plan:Florida Power & Light Co,St Lucie Plant,Unit 1. ML17223A1321988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 2. ML17223A1291988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 1. ML20244C2931988-11-30030 November 1988 Review of Florida Power & Light Co Safety Evaluations for Extending St Lucie Plant,Unit 2,ESFAS Subgroup Relay Test Interval, Technical Evaluation Rept ML17308A4461988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at St Lucie Unit 2. ML20196G2921988-02-29029 February 1988 Technical Evaluation Rept,Evaluation of High Density Spent Fuel Rack Structural Analysis for St Lucie Plant - Unit 1 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML17308A2391987-06-30030 June 1987 Integrated Leak Rate Test for St Lucie Nuclear Power Plant (Unit 2) Apr 1987-June 1987, Technical Evaluation Rept ML17219A6871987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2, 'Vendor Interface Program for All Other Safety-Related Components:St Lucie 1 & 2,' Final Rept ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML17308A2891987-01-31031 January 1987 Review of Tech Spec Changes Supporting NUREG-0737 Accident Instrumentation,St Lucie Units 1 & 2, Technical Evaluation Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML17308A2421986-05-31031 May 1986 Rev 1 to Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML17308A2151986-04-30030 April 1986 First Interval Inservice Insp Program,St Lucie Unit 2, Technical Evaluation Rept ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML17216A4331986-01-13013 January 1986 SPDS Progress Review,St Lucie 1 & 2. ML17301A1841985-06-17017 June 1985 Masonry Wall Design (B-59),Florida Power & Light Co,St Lucie Unit 1, Technical Evaluation Rept ML17301A1671985-02-28028 February 1985 Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML20080E0711984-01-13013 January 1984 Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept ML17301A0621983-10-31031 October 1983 Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase Ii). ML17214A6931983-10-31031 October 1983 Conformance to NRR Generic Ltr 82-16,St Lucie Plant,Units 1 & 2, Preliminary Rept ML17214A2041983-04-30030 April 1983 Draft Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase I), Technical Evaluation Rept ML17214A1581983-04-29029 April 1983 Control of Heavy Loads (C-10) St Lucie Unit 1, Draft Technical Evaluation Rept ML17214A1551983-04-26026 April 1983 Radiological Effluent Tech Specs (RETS) Implementation - St Lucie Unit 1 Nuclear Generating Plant. ML17214A4541983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML17301A0131982-11-24024 November 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),St Lucie Unit 1, Technical Evaluation Rept ML20065U2351982-10-31031 October 1982 Technical Evaluation Rept of Overpressure Mitigation Sys for St Lucie,Unit 1 ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML17301A0011982-09-28028 September 1982 ECCS Repts (F-47),TMI Action Plan Requirements,St Lucie Unit 1, Technical Evaluation Rept ML17213A7321982-09-17017 September 1982 Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20066B3231982-08-31031 August 1982 Audit of Environ Qualification of Safety-Related Electrical Equipment at St Lucie Unit 2 Nuclear Generating Station, Interim Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20062E2041982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations:Saint Lucie Case Study.Docket Nos. 50-335 and 50-389.(Florida Power and Light Company) ML17212B7831982-05-31031 May 1982 Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant Unit 2,FL Power & Light Co, Draft Technical Evaluation Rept ML20052B5341982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, St Lucie,Unit 1, Technical Evaluation Rept 1999-03-16
[Table view] Category:ETC. (PERIODIC
MONTHYEARML17229B0671999-03-16016 March 1999 Technical Evaluation Rept, Florida Power & Light Co, Unit 1 Third Ten-Year Interval Pump & Valve Inservice Testing Program,Unit 2 Second Ten-Year Interval Pump & Valve Inservice Testing Program. ML17355A2801998-09-30030 September 1998 Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point. ML17229B0011998-01-31031 January 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at St Lucie Nuclear Plant,Units 1 & 2. ML17229A4151997-05-27027 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for St Lucie Nuclear Plant. ML17228B1261995-03-31031 March 1995 Technical Evaluation Rept on Second 10-Year Interval Insp Program Plan. ML17309A7471994-09-30030 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001:St.Lucie-1/-2. ML17228A8851994-09-30030 September 1994 Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original Rept ML20138E1481993-06-22022 June 1993 Pump & Valve Inservice Testing Program St Lucie Unit 2 FPL, Technical Evaluation Rept ML20105D0871992-08-31031 August 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the St. Lucie Unit 1 Nuclear Power Generation Station ML17309A6651991-11-30030 November 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,St Lucie-Unit 1. ML17223B3231991-08-31031 August 1991 TER of Topical Rept CEN-396-P (Verification of Acceptability of a 1-PIN Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2). ML17308A5041990-08-17017 August 1990 Final Technical Evaluation Rept St Lucie Unit 1 Station Blackout Evaluation. ML17308A4821989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components,St Lucie 1/2, Technical Evaluation Rept ML17222A7411989-01-31031 January 1989 Technical Evaluation Rept on Second Ten-Year Interval Inservice Insp Program Plan:Florida Power & Light Co,St Lucie Plant,Unit 1. ML17223A1321988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 2. ML17223A1291988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 1. ML20244C2931988-11-30030 November 1988 Review of Florida Power & Light Co Safety Evaluations for Extending St Lucie Plant,Unit 2,ESFAS Subgroup Relay Test Interval, Technical Evaluation Rept ML17308A4461988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at St Lucie Unit 2. ML20196G2921988-02-29029 February 1988 Technical Evaluation Rept,Evaluation of High Density Spent Fuel Rack Structural Analysis for St Lucie Plant - Unit 1 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML17308A2391987-06-30030 June 1987 Integrated Leak Rate Test for St Lucie Nuclear Power Plant (Unit 2) Apr 1987-June 1987, Technical Evaluation Rept ML17219A6871987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2, 'Vendor Interface Program for All Other Safety-Related Components:St Lucie 1 & 2,' Final Rept ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML17308A2891987-01-31031 January 1987 Review of Tech Spec Changes Supporting NUREG-0737 Accident Instrumentation,St Lucie Units 1 & 2, Technical Evaluation Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML17308A2421986-05-31031 May 1986 Rev 1 to Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML17308A2151986-04-30030 April 1986 First Interval Inservice Insp Program,St Lucie Unit 2, Technical Evaluation Rept ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML17216A4331986-01-13013 January 1986 SPDS Progress Review,St Lucie 1 & 2. ML17301A1841985-06-17017 June 1985 Masonry Wall Design (B-59),Florida Power & Light Co,St Lucie Unit 1, Technical Evaluation Rept ML17301A1671985-02-28028 February 1985 Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML20080E0711984-01-13013 January 1984 Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept ML17301A0621983-10-31031 October 1983 Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase Ii). ML17214A6931983-10-31031 October 1983 Conformance to NRR Generic Ltr 82-16,St Lucie Plant,Units 1 & 2, Preliminary Rept ML17214A2041983-04-30030 April 1983 Draft Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase I), Technical Evaluation Rept ML17214A1581983-04-29029 April 1983 Control of Heavy Loads (C-10) St Lucie Unit 1, Draft Technical Evaluation Rept ML17214A1551983-04-26026 April 1983 Radiological Effluent Tech Specs (RETS) Implementation - St Lucie Unit 1 Nuclear Generating Plant. ML17214A4541983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML17301A0131982-11-24024 November 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),St Lucie Unit 1, Technical Evaluation Rept ML20065U2351982-10-31031 October 1982 Technical Evaluation Rept of Overpressure Mitigation Sys for St Lucie,Unit 1 ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML17301A0011982-09-28028 September 1982 ECCS Repts (F-47),TMI Action Plan Requirements,St Lucie Unit 1, Technical Evaluation Rept ML17213A7321982-09-17017 September 1982 Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20066B3231982-08-31031 August 1982 Audit of Environ Qualification of Safety-Related Electrical Equipment at St Lucie Unit 2 Nuclear Generating Station, Interim Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20062E2041982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations:Saint Lucie Case Study.Docket Nos. 50-335 and 50-389.(Florida Power and Light Company) ML17212B7831982-05-31031 May 1982 Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant Unit 2,FL Power & Light Co, Draft Technical Evaluation Rept ML20052B5341982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, St Lucie,Unit 1, Technical Evaluation Rept 1999-03-16
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML17229B0671999-03-16016 March 1999 Technical Evaluation Rept, Florida Power & Light Co, Unit 1 Third Ten-Year Interval Pump & Valve Inservice Testing Program,Unit 2 Second Ten-Year Interval Pump & Valve Inservice Testing Program. ML17355A2801998-09-30030 September 1998 Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point. ML17229B0011998-01-31031 January 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at St Lucie Nuclear Plant,Units 1 & 2. ML17229A4151997-05-27027 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for St Lucie Nuclear Plant. ML17228B1261995-03-31031 March 1995 Technical Evaluation Rept on Second 10-Year Interval Insp Program Plan. ML17309A7471994-09-30030 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001:St.Lucie-1/-2. ML17228A8851994-09-30030 September 1994 Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original Rept ML20138E1481993-06-22022 June 1993 Pump & Valve Inservice Testing Program St Lucie Unit 2 FPL, Technical Evaluation Rept ML20105D0871992-08-31031 August 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the St. Lucie Unit 1 Nuclear Power Generation Station ML17309A6651991-11-30030 November 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,St Lucie-Unit 1. ML17223B3231991-08-31031 August 1991 TER of Topical Rept CEN-396-P (Verification of Acceptability of a 1-PIN Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2). ML17308A5041990-08-17017 August 1990 Final Technical Evaluation Rept St Lucie Unit 1 Station Blackout Evaluation. ML17308A4821989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components,St Lucie 1/2, Technical Evaluation Rept ML17222A7411989-01-31031 January 1989 Technical Evaluation Rept on Second Ten-Year Interval Inservice Insp Program Plan:Florida Power & Light Co,St Lucie Plant,Unit 1. ML17223A1321988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 2. ML17223A1291988-12-31031 December 1988 Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 1. ML20244C2931988-11-30030 November 1988 Review of Florida Power & Light Co Safety Evaluations for Extending St Lucie Plant,Unit 2,ESFAS Subgroup Relay Test Interval, Technical Evaluation Rept ML17308A4461988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at St Lucie Unit 2. ML20196G2921988-02-29029 February 1988 Technical Evaluation Rept,Evaluation of High Density Spent Fuel Rack Structural Analysis for St Lucie Plant - Unit 1 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML17308A2391987-06-30030 June 1987 Integrated Leak Rate Test for St Lucie Nuclear Power Plant (Unit 2) Apr 1987-June 1987, Technical Evaluation Rept ML17219A6871987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2, 'Vendor Interface Program for All Other Safety-Related Components:St Lucie 1 & 2,' Final Rept ML20206K6331987-04-0808 April 1987 Mod 3,changing Billing Address,To Quantify Performance of Waterborne Intruder Detection Sys Installed at St Lucie Nuclear Power Plant ML20206K6111987-04-0808 April 1987 Notification of Contract Execution,Mod 3,to Quantify Performance of Waterborne Intruder Detection Sys Installed at St Lucie Nuclear Power Plant. Contractor:Univ of Tx at Austin Applied Research Labs ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML17308A2891987-01-31031 January 1987 Review of Tech Spec Changes Supporting NUREG-0737 Accident Instrumentation,St Lucie Units 1 & 2, Technical Evaluation Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20211L3111986-12-0808 December 1986 Notification of Contract Execution,Mod 2,to Quantify Performance of Waterborne Intruder Detection Sys Installed at St Lucie Nuclear Power Plant. Contractor: Univ of Texas, Applied Research Labs ML20211L3381986-12-0808 December 1986 Mod 2,extending Period of Performance to 870630 at No Addl Cost, to Quantify Performance of Waterborne Intruder Detection Sys Installed at St Lucie Nuclear Power Plant ML20205D3581986-08-0606 August 1986 Mod 1,extending Period of Performance Until 861130 at No Addl Cost,To Quantify Performance of Waterborne Intruder Detection Sys at St Lucie Nuclear Power Plant ML20205D3411986-08-0606 August 1986 Notification of Contract Execution,Mod 1,to Quantify Performance of Waterborne Intruder Detection Sys at St Lucie Nuclear Power Plant. Contractor:Univ of Texas ML20206H4421986-06-23023 June 1986 Contract: Quantify Performance of Waterborne Intruder Detection Sys Installed at St Lucie Nuclear Power Plant, Awarded to Univ of Texas at Austin ML20206H4171986-06-23023 June 1986 Notification of Contract Execution: Quantify Performance of Waterborne Intruder Detection Sys Installed at St Lucie Nuclear Power Plant, Awarded to Univ of Texas at Austin ML17308A2421986-05-31031 May 1986 Rev 1 to Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML17308A2151986-04-30030 April 1986 First Interval Inservice Insp Program,St Lucie Unit 2, Technical Evaluation Rept ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML17216A4331986-01-13013 January 1986 SPDS Progress Review,St Lucie 1 & 2. ML17301A1841985-06-17017 June 1985 Masonry Wall Design (B-59),Florida Power & Light Co,St Lucie Unit 1, Technical Evaluation Rept ML17301A1671985-02-28028 February 1985 Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2. ML20080E0711984-01-13013 January 1984 Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept ML17214A6931983-10-31031 October 1983 Conformance to NRR Generic Ltr 82-16,St Lucie Plant,Units 1 & 2, Preliminary Rept ML17301A0621983-10-31031 October 1983 Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase Ii). ML17214A2041983-04-30030 April 1983 Draft Control of Heavy Loads at Nuclear Power Plants,St Lucie Plant,Unit 2 (Phase I), Technical Evaluation Rept ML17214A1581983-04-29029 April 1983 Control of Heavy Loads (C-10) St Lucie Unit 1, Draft Technical Evaluation Rept ML17214A1551983-04-26026 April 1983 Radiological Effluent Tech Specs (RETS) Implementation - St Lucie Unit 1 Nuclear Generating Plant. ML17214A4541983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML17301A0131982-11-24024 November 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),St Lucie Unit 1, Technical Evaluation Rept ML20065U2351982-10-31031 October 1982 Technical Evaluation Rept of Overpressure Mitigation Sys for St Lucie,Unit 1 1999-03-16
[Table view] |
Text
EGG-DNSP-11487 TECHNICAL EVALUATION REPORT Evaluation of Utility Response to Supplement 1 to NRC Bulletin 90-01: St. Lucie-I/-2 Docket Nos. 50-335 and 50-389 Alan C. Udy Published Septemb'er 1994 EGSG Idaho, Inc.
Idaho National Engineering Laboratory Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. L1695, Task No. 11a TAC Nos. M85446 and M85447 PDR P -,;
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SUMMARY
This report documents the EGKG Idaho, Inc., review of the Florida Power and Light Company submittals that respond to Supplement 1 to NRC Bulletin 90-01 for Unit Nos. 1 and 2 of the St. Lucie Plant. This NRC Bulletin provides information regarding the loss of fill-oil in certain pressure and differential pressure transmitters manufactured by Rosemount, Inc. This report finds that the licensee complies to the requested actions and the reporting requirements of the Supplement.
FIN No. L1695, Task No. lla BER No. 320-19-15-05-0 Docket Nos. 50-335 and 50-389 TAC Nos. M85446 and M85447
e PREFACE This report is supplied as part of the "Technical Assistance in Support of the Instrumentation and Controls Systems Branch." It is being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Reactor Controls and Human Factors, by EGLG Idaho, Inc., DOE/NRC Support Programs Unit.
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CONTENTS S UMMARY o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ tt ~ ~ ~ ~ ~ ~ ~ ~ ~
P REFACE .............................................................. ill
- 1. INTRODUCTION .. ~...........................................,..... 1
- 2. NRC SPECIFIED RE(UESTED ACTIONS ................................. 4
- 3. E VALUATION .....;................................................ 7'.
1 Evaluation of Licensee Response to Reporting Requirements . 7 3.2 Evaluation of Licensee Response to Requested Actions ...... 7
- 4. CONCLUSIONS .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 12
- 5. R EFERENCES ...................................................... 13
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Evaluation of Utilit Res onse to Su lement 1 to NRC Bulletin 90-01: St. Lucie-1 -2
- 1. INTRODUCTION The NRC issued Bulletin 90-01 on March 9, 1990 (Reference 1). That Bulletin discussed certain, Rosemount pressure and differential pressure transmitter models identified by the manufacturer as prone to fill-oil leakage. The Bulletin requested licensees to identify whether these transmitters were or may later be installed in safety-related systems.
Actions were detailed for licensee implementation for certain identified transmitters installed in a safety-related system.. These same actions apply to those identified transmitters presently held in inventory for later installation in a safety-related system.
With the gradual leakage of fill-oil, the transmitter would not have the long term accuracy, time response, and reliability needed for its intended safety function. Further, this condition could go undetected over a long period. Redundant instrument channels are subject to the same degradation mechanism. This increases the potential for a common mode failure. Thus, this potential failure mechanism raised concern for the reliability of reactor protection systems (RPS), engineered safety features (ESF) actuation systems, and anticipated transient without scram (ATWS) mitigating systems. To achieve high functional reliability, there must be a low probability of component failure while operating, with any failures readily detectable.
Supplement 1 to NRC Bulletin 90-01 (Reference 2) was issued on December 22, 1992. The Supplement informed licensees of NRC staff activities regarding the subject transmitters, and noted continuing reports of transmitter failures. The'RC requested licensee action to resolve the issue.
The Supplement also updated the. information contained in the original bulletin. The licensee was requested to review the information and determine if it was applicable at their facility. Further, the licensee was requested to modify their actions and enhanced surveillance monitoring programs to conform with the direction given. Finally, the licensee was instructed to 1
respond to the NRC. ,The Re uested Actions in Supplement 1 to NRC Bulletin 90-Ol supersede the original NRC Bulletin 90-01 Re uested Actions.
In responding to Supplement 1 to NRC Bulletin 90-01, the licensee is directed to address three items.
- l. A statement either committing the licensee to take the NRC Bulletin 90-01, Supplement 1, Re uested Actions or taking exception to those actions.
- 2. Addressing the actions committed to in the above statement, provide:
a ~ a list of the specific actions, including any justifications, to be taken to complete the commitment,
- b. a schedule for completion, and C. after completion, a statement confirming the actions committed to are complete.
- 3. A statement identifying the NRC Bulletin 90-01, Supplement 1, Re uested Actions not taken, along with an evaluation providing the basis for exemption.
In implementing the replacement'ption of the NRC Re uested Actions, plant shutdown exclusively for replacing the transmitters is not required.
This allowance infers that replacements can be scheduled. With replacement in a timely manner, enhanced surveillance monitoring for interim operation is not required.
The Florida Power and Light Company, the licensee for Unit Nos. 1 and 2 of the St. Lucie Plant, responded to Supplement 1 of NRC Bulletin 90-01 with a letter dated Harch 5, 1993 (Reference 3). The licensee provided additional information on March 9, 1994 (Reference 4). The licensee notified the NRC that their transmitter replacements were complete on August 18, 1994 (Reference 5). This technical evaluation report evaluates the completeness o' 2
those submittals. It also determines whether proposed surveillance methods are adequate to determine fill-oil loss-caused degradation of the transmitter..
Finally, this report addresses the interval of surveillance proposed by the licensee for 'any transmitters included in the enhanced surveillance monitoring program.
Hany Rosemount transmitter failures have been attributed to the use of stainless steel "0"-rings between the sensing module and the process flanges.
Rosemount improved the manufacturing process for transmitters manufactured after July ll, 1989. Those improvements included a limit of the torque applied to the flange bolts. This limits the stress caused in the sensing module by the "0"-ring. Post-production screening, including pressure testing of the sensing module for this potential latent defect, was also implemented at that time. Therefore, as described in Supplement 1 of NRC Bulletin 90-01, those Rosemount transmitters manufactured after July 11, 1989, are not subject to this review.
- 2. NRC SPECIFIED REQUESTED ACTIONS The NRC staff specified the following Re uested Actions of licensees of operating reactors.
- 1. Review plant records and identify the following Rosemount transmitters (if manufactured before July 11, 1989) that either are used in or may be used in either safety-related or ATWS mitigating systems.
Rosemount Hodel 1153, Series B Rosemount Hodel 1153, Series D Rosemount Hodel 1154 Following identification, the licensee is to establish the following:
'a ~ For those identified transmitters having a normal operating pressure greater than 1500 psi, and are installed as part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter in an expedited manner, or monitor monthly, for the life of the transmitter, using an enhanced surveillance program.
If the identified transmitter exceeds the 60,000 psi-month or the 130,000 psi-month criterion (depending on the range code of the transmitter) established by Rosemount, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be based on the service record and the specific safety function of the transmitter. That justification can be based on high functional reliability provided by redundancy or diversity.
- b. For those identified transmitters having a normal operating pressure greater than 1500 psi, and are installed as part of a safety-related system other than reactor protection trip systems, ESF actuation, or ATWS mitigating systems, either replace the transmitter or monitor quarterly, for the life of the transmitter, using an enhanced surveillance program.
If the identified transmitter exceeds the 60,000 psi-month or the 130,000 psi-month criterion (depending on the range code of the transmitter) established by Rosemount, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be based on the service record and the specific safety function of the transmitter. That
justification can be based on high functional reliability provided by redundancy or diversity.
For boiling water reactors (BWR)--
For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and are installed as part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter, or monitor monthly with an enhanced surveillance monitoring program, until the transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code).
For transmitters that provide signals to the RPS or ATWS trips for high pressure or low water level, the enhanced surveillance must be monthly. For other transmitters in this classification, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be based on the service .record and the specific safety function of the transmitter. That justification can be based on high functional reliability provided by redundancy or diversity.
For pressurized water reactors (PWR)--
For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and are installed as. part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter, or monitor with an enhanced surveillance monitoring program, until the transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code) on a refueling (not exceeding 24 months) basis.
For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and are installed as part of a safety-related system other than reactor protection trip systems, ESF actuation, or ATWS mitigating systems, either replace the transmitter, or monitor with an enhanced surveillance monitoring program, until the transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code) on a refueling (not exceeding 24 months) basis.
- e. Those transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and have accumulated sufficient psi-month operating history to exceed the criterion established by Rosemount, may be excluded from the enhanced survei.llance monitoring program at the discretion of the licensee.
However, the licensee should retain a high'evel of confidence that a high level of reliability is maintained and that transmitter failure due to loss of fill-oil is detectable.
Those transmitters having a normal operating pressure less than or equal to 500 psi may be excluded from the enhanced surveillance monitoring program at the discretion of the licensee. However, the licensee should retain a high level of confidence that a high level of reliability is maintained and that transmitter failure due to loss of fill'-oil is detectable.
- 2. Evaluate the enhanced surveillance monitoring program. The evaluation is to ensure the measurement data has an accuracy commensurate with the accuracy needed to compare the data to the manufacturers drift data criteria. It is this comparison that determines the degradation threshold for loss of fill-oil failures of the subject transmitters.
The Supplement also states the NRC may conduct audits or inspections in the future to verify compliance with the established requirements.
- 3. EVALUATION The licensee responded to Supplement 1 of NRC Bulletin 90-01 on March 5, 1993. The licensee provided additional information on March 9, 1994. The licensee notified the NRC that their transmitter replacements were complete on August 19, 1994. Those responses were compared to the Bulletin ~Re ortin d d i d ib d b 1 . Th having Rosemount transmitters that are subject to the Re uested Actions of the Supplement. Other Rosemount transmitters are'outside the scope of the Supplement due to replacement or refurbishment.
- 3. 1 Evaluation of Licensee Res onse to Re ortin Re uirements The licensee states, in Reference 3, that they intend to implement the Re uested Actions detailed in Supplement 1 of NRC Bulletin 90-01. Included with that statement is clarification, interpretation, and the limits placed on that commitment. The licensee described the specific actions taken to execute the Re uested Actions. The licensee provided a statement that the ~Re uested Actions are complete on August 18, 1994.
The licensee submitt'als conform to the Re ortin Re uirements of Supplement 1 of NRC,Bulletin 90-01.
3.2 Evaluation of Licensee Res onse to Re uested Actions Supplement 1 of NRC Bulletin 90-01 requested licensee action to resolve the issue of fill-oil leakage in Rosemount transmitters. This Technical Evaluation Report summarizes the Re uested Actions and the associated transmi'tter criteria in Section 2. Rosemount transmitters manufactured after July 11, 1989 are not subject to the Supplement requirements or an enhanced surveillance monitoring program. The licensee'esponse to the Supplement is discussed in the following sections.
3.2. 1 Licensee Res onse to Re uested Action 1.a Unit No. 1 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 1 of the St. Lucie Plant. The licensee scheduled the subject transmitters for replacement in the spring of 1993.
However, the licensee commi.tted that if a delay in transmitter installation occurred, the licensee will monitor that transmitter monthly as part of their enhanced surveillance monitoring program. The licensee stated they will not increase the surveillance interval from monthly without providing justification to the NRC. The licensee actions for transmitters in transmitter classification l.a at Unit No. 1 are acceptable. As noted in Reference 5, the licensee actions for this transmitter classification are complete, and the transmitters replaced as scheduled.
Unit No. 2 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 2 of the St. Lucie Plant. However, all Unit No. 2 Rosemount transmitters in this transmitter classification were manufactured after July 11, 1989, and are exempt from the Supplement requirements.
3.2.2 Licensee Res onse to Re uested Action 1.b.
Unit No. 1 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 1 of the St. Lucie Plant. The licensee scheduled the subject transmitters for replacement in the spring of 1993.
However, the licensee committed, in Reference 3, that if a delay in transmitter installation occurred, the licensee will monitor that transmitter
quarterly as part of their enhanced surveillance monitoring program. The licensee states they will not increase the surveillance interval from quarterly without providing justification to the NRC. The licensee actions for transmitters in transmitter classification 1.b at Unit No. 1 are acceptable. As noted in Reference 5, the licensee actions for this transmitter classification are complete, and the transmitters replaced. as scheduled.
Unit No. 2 The licensee states there are Rosemount transmitters from this transmitter classification at Unit No. 2 of the St. Lucie Plant. The licensee scheduled the subject transmitters for replacement in the fall of 1993. The licensee committed, in Reference 3, to monitor these transmitters quarterly as part of the enhanced surveillance monitoring program until replaced. Some of the Unit No. 2 Rosemount transmitters were manufactured after July ll, 1989, and are exempt from the Supplement requirements. The licensee actions for transmitters in transmitter classification 1.b at Unit No. 2 are acceptable.
As noted in Reference 5, the licensee actions for this transmitter classification are complete, and the transmitters replaced as scheduled.
3.2.3 Licensee Res onse to Re uested Action 1.c The licensee states there are Rosemount transmitters from this transmitter classification at the St. Lucie Plant. The licensee states that these transmitters will participate in an enhanced surveillance monitoring program on a refueling basis. The interval will not exceed 24 months. Either replacement or successfully achieving the psi-month maturity threshold will remove a transmitter from the enhanced surveillance monitoring program.
Replacement with a transmitter manufactured after July 11, 1989, removes the transmitter from the Supplement requirements. Successfully achieving maturity transfers the transmitter to transmitter classification l.e. See Section 3.2.5.
3.2.4 Licensee Res onse to Re uested Action 1.d The licensee states there are Rosemount transmitters from this transmitter classification at the St. Lucie Plant. The licensee states that these transmitters will participate in an enhanced surveillance-monitoring program on a refueling basis. The interval will not exceed 24 months. Either replacement or successfully achieving the psi-month maturity threshold will remove'a transmitter from the enhanced surveillance monitoring program.
Replacement with a transmitter manufactured after July 11, 1989, removes the transmitter from the Supplement requirements. Successfully achieving maturity transfers the transmitter to transmitter classification l.e. See Section 3.2.5.
3.2.5 Licensee Res onse to Re uested Action l.e As transmitters in transmitter classification 1.c and 1.d exceed the psi-month maturity threshold, the licensee will remove those transmitters from the enhanced surveillance monitoring program. The Supplement'ermits this action.
The Supplement requires the licensee to maintain a high degree of confidence that these transmitters remain highly reliable. The licensee states that before removing a transmitter from the enhanced surveillance monitoring program, the transmitter will exhibit no excessive drift or sluggishness. The licensee states that existing maintenance and surveillance programs can detect future failures due to the loss of fill-oil.
3.2.6 Licensee Res onse to Re uested Action 1.f The licensee states there are Rosemount transmitters from this classification at the St. Lucie Plant. At licensee discretion, these transmitters are not part of the enhanced surveillance monitoring program.
The Supplement permits this action.
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The Supplement requires the licensee to maintain a high degree of confidence that these transmitters remain highly reliable. The l,icensee states that existing maintenance and surveillance programs can detect future failures due to the loss of fill-oil.
3.2.7 Enhanced Surveillance Nonitorin Pro ram The licensee described the monitoring'intervals for the different transmitter classifications. The licensee, in addressing Re uested Action 2 of the Supplement, states their enhanced surveillance monitoring program uses the guidelines of Rosemount Technical Bulletin No. 4. Following the guidelines of Rosemount Technical Bulletin No. 4 satisfies the requirements of the Supplement and is acceptable.
- 4. CONCLUSIONS Based on our review, we find the licensee has completed the reporting requirements of Supplement 1 of NRC Bulletin 90-01. Further, the licensee conforms to the Re uested Actions of Supplement 1 to NRC Bulletin 90-01.
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- 5. REFERENCES NRC Bulletin No. 90-01: "Loss of Fill-oil in Transmitters Manufactured by Rosemount," March 9, 1990, OHB No. 3150-0011.
NRC Bulletin No. 90-01, Supplement 1: "Loss of Fill-oil in Transmitters Manufactured by Rosemount," December 22, 1992, OMB No. 3150-0011.
Letter, Florida. Power and Light Company (D. A. Sager) to NRC, "NRC Bulletin 90-01 Supplement 1 Response," March 5, 1993, L-93-61.
Letter, Florida Power and Light Company (D. A. Sager) to NRC, "NRC Bulletin 90-01 Supplement 1 Additional Information," March 9, 1994, L-94-061.
L'etter, Florida Power and Light Company (D. A. Sager) to NRC, "NRC Bulletin 90-01 Supplement 1 Additional Information," August 18, 1994, L-94-210.
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