ML20141M224
| ML20141M224 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1991 |
| From: | NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | |
| Shared Package | |
| ML20141M223 | List: |
| References | |
| NUDOCS 9204020236 | |
| Download: ML20141M224 (480) | |
Text
{{#Wiki_filter:I l I I PERFORMANCE INDICATORS FOR OPERATING g COMMERCIAL NUCLEAR POWER REACTORS Report for Fourth Quarter 1991 l Data through December 1991 I I OFFICE 120R ANALYSIS AND EVALUATION OF OPERATIONAL DATA I I PART I I -g I . I U.S. NUCLEAR REGULATORY COMMISSION (("'%
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, mCunvE su-v Tbs report picscots the eight (8) NRC Performance indicators tr'is) for the fuurth calender querir r of IW1. Data etc instuJcd for the calendar quarteri, El through 91-4 fos 111 commercial U.5 nuclear p=er plants. Addatumally, the IW1 an%si summary analpas of the l
I Pi data in indoded. "Iha analpis is consulent eith the Comentssion directrves tontained in e Start Requirements Memorandum of jurie 24.19M ($1'CY4tt.lM), $terus eLPerformanrt spjdyster Prover 3 The annual inhtry asetage values are shoun in hgure 1. Costnng the peru 4 IV6is Llacogh IW1. the>c values shoe an v4rall impratment, math the imptwement ratt sicmirig since 1968 2 lit IW1. the imprmement is evident in automane scrams while critical, signfuent events, and equipment forced outages per 1(xc eritual hours. The IW1 everage number of safety system sciu tams and safety eptem fat terts remained the karr.e as 19'N, while the for;ed optage rett tras somewhat highei but within tb4 tangt emperienced smte 19VL l>ata for adlectres radiation ty=surt isgs the other Pl data by ona quarter and therefore, no %st everage value lot IW1 is included in Ingurt lw llantscr. based on the data from the first thret quartets of IWl, its userall lWI svera *e should also show imprmtrnent frorn IWO Industry average values of the cause ndes are not computed, and therefore, not included n ligurc 1. Summanes ref quarterly , industry avtrage values and mcwir g tretid knes are shown in f*igure 2 for calendar years 19N and 1 N1. r FIGUltE 1 ANNUAL INDUSTitY l'EltFolt31ANCE INDICATOlt /NEllAGES , E e t um.< a,e sc,r,a m.e c, to 2 wes ,,,e,~, - s l 6 8 -v-* h y s e; 3. I' t j4. f2-5 L. -, _
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] g UNITED STATES {
%,'.c NUCLEAR REGULATORY COMMISSION
* . . ,( /
ANNOUNCEMENT NO. 200 DATE: November 28, 1989 TO: All NRC EMPLOYEES l
SUBJECT:
REVISED GUIDANCE ON THE USE OF PERTORMANCE INDICATORS This announcement revises the earlier guidance of HRC Announcement 30, l dated February 5,1988, regarding the use of the resalts of the NRC Perfomance Indicator Program. All NRC employees shall adhere to the following guidance. The Performance Indicator Progrcm provides an additional view of operational performance and enhances our ability to rer.ognize areas of I poor and/or declining safety performance of operating plants. However, it is only a tool and is to be used in conjunction with other tools, such as the results of routine and special inspections and the systematic assessment of licensee perfonnance (SALP) program, for providing input I to NRC management decisions regarding the need to adjust plant-s p cific regulatory programs, it should be recognized that perfonnance indicatorm have limitt.tions and are subject to misinterpretation. Therefore, caution is warranted L in the interpretstion and use of the data. The application of [ performance indicators f or purposes and in manners other than those stated above will be counter to the I;RC objective of ensuring operational safety. To avoid such situations, the following specific directives are provided: 1 The Performance Indicator Program for operating reactors is a l single, coordinated, overail NRC program under the direction of B AE00. NRC offices other than AE00 should not deviate from the NRC program without written permission of the EDO or the Director, AE0D. iii
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- 2. Performance indicators are intended as a tool for senior NRC management to monitor trends in over111 performance for a given plant. The performance indicators for a given plant should be viewed as a set. When viewed as a set, the performance indicators provide an additional measure of plant operational perfv sance.
However, they should not be used in communications with licensees as a measure of performance level. 3 Performance indicators are intended to be one of several tools for use by senior NRC management in decision-making regarding plant-specific regulatory programs. Senior management in each HRC of fice should have access to perfomance indicators for their assignedunit(s). Performance indicators are not to be overemphasized in relation to other measures of safety perfomance, l for this reason, no regulatory action should be taken on the basis of Performance Indicator Program results alone, g 4 Performance indicators do not provide a valid basis for ranking individual nuclear power plants and should not be presented in such a way as to imply " problem facility" status for individual plants.
- 5. The Performance Indicator Program is separate and distinct from the CALP program, although it is recognized that the indicators have relationships in varying degrees to SALP functional areas.
Indicators, such as failures of a plant's safety systems or frequent forced outages due to equipment failures, may be symptomatic of safety problems. Thus, the staff may recogniza events and failures captured by certain indicators in SALP g discussions and reports, but these SALP references are to be )ased 3 on the underlying causes of poor performance and not on the results of the Performance Indicator Program, either indivitaally or as a set. Regional Administratnrs should ensure that our decision-making process adheres to this guioance, especially in SALP discussions and documentation.
- 6. NRC senior management should bear in mind when evaluating performance indicator results that the indicators are assessment tools that aid in identification of unanticipated performance, 3 and that the underlying causes should be carefully assessed. E evaluated, and understood (factoring in other available information).
7 Quarterly compilations of Performance Indicator Program results should be placed in the Public Document Room following dissemination to NRC management and the Comission. l E iv I
"I
I I It should be recognized that in conducting reviews, inspections, and I evaluations of plants, it is often necessary to rely on plant data. Such information has been routinely used in our SALP, safety evaluation reports, and technical evaluation reports. The foregoing policy is I not intended to change th % process. NRC staff must be sensitive to inappropriate pressure from any source I which causes licensee personnel at individual nuclear power plants to
" manage the indicators" or to take any actions that are contrary to plant safety because of performance indicators, individually or as a set (such as inhibiting reactor trips). Any such instances shnuld be I promptly communicated to appropriate licensee management and brought to NRC management attention.
I ' I , pnes M. TayJ5r
#cting Executive Director for Operations I
I I I I I I I I I v l I l
1 I I I I THIS l I PAGE g i INTENTIONALLY E LEFT I BLANK I I t I I vi
F I l CONTl;NTS l'AllT I E EXECUTIVE SUMhtARY .. .. ., .. . . ... .. .... . . .. .. i l RiiVISED OUIDANCE ON Tile USE OF ITill ORhtANLE INDICA 10its . . . . . . . iii ANALYSIS OF Tile PERI ORhtANCE INDICATOR DATA TilROUGil DECEhtilER IV>l . .... ... ... ... .... . .. .. .. I
- 1. !! .!ODUCTION . . . . .. . .. . . .. . ,, . . . .......... . . 1
?. IIACKOROUND . . . ....... ...... . .. . . . ... .. . ... .. . ... 1
. 3. DITINITIONS OF Tile PEltFORhtANCE INDICATORS .. . . . . . 2 i 3.1 Automatic Scrams While Critical (Scramu . . . ..... .. ..... ..... . .... . . 2 3.2 Safety Sptem Actuations (SSA) . .... . ..... . ... . . . . . . 2 g 3.3 hignificant Events (SE) , ...... . .. ..... .. . . . ... .. . ... 3 g 3,4 Safety Sptern Failuscs (SSF) . ... . . .. ..... . ..... .. . . 4 3.5 l orced Outage Pate (I OR) . . . .... ... . .. . . . . . . . . . . 4 g 3 6 Equipment Forced Outages per 10W Commercial Critical llourt. (El0) . . .. .. . 4 3 g 17 Collective Radiation Expmunc . . . . . . . ..... .... .. .. .. .. .. .... ... 5 2 3.8 Cause Codes . . . ....... . ... .. .. .. . . ..... ... .. . . . 5 3Al Administrative Control Problems . .. , , .. .. .. . . 5 3A2 1.icensed Operator Errors .... . . ... . . . . . .. . . ...... . 5 3.83 Other Personud Errors ..... .... . .. . . ... . . ....., 6 I 3.84 3A5 3A6 hiaintenance Psoblems . ... . Design / Construction / Installation / Fabrication Problems Equipment failures (Electionic Piere Part or Erwironmental-Related Failures) 6 6 7
- 4. DISPl.AY OF PERFORhlANCE INDICATOR DATA . ... . . . ..... 7 i
4.1 Quarteri, Data .. . . . . . .. . .. .. . . ... .... 7 4.2 Trends and Dniations . . . . .. . . . . ... . .. . 8
- 5. COh1PUTAllONAI. CONVENTIONS . . . . . . . .. 8
- 6. QUARTERLY DATA AND TRENDS & DEVIATIONS FIGURES , .. . .. 11 I
I . I V11
i
- I 1,lST OF FIGURES 1 PARTI i
lIGUk! 1 ANNUAL INDlNIRY P1 RIOR\iANll!!NillCAIOR AV! RAGl3 i
- 110t'RI
- 2 OCARil Kl.Y INDLTIRY Pl Ri URMANCl? INDICA 10R AVI:RNLs b
, I IGURI: f.1 Al KAN;A% 1 12 11GURl: 6.56 MOVi1Cl I l.O 124 l'IGURI' 6 2 ARKANMS 2 14 11GUKl? 657 NINE Mil.1: l'T. I 1 26 110URL 6 3 lilAYl_R val 113 1 16 11GU RI, 6.% NINE Mll 1: l'!; 2 123 I 1100 R1! 6 4 Ill'AVI R Valli:Y 2 18 110U Rl! (t3Y NORill ANNA I l'O 110U RI: 65 ll!G ROCK PolVI D f lGU Rl! 6 f4 NPRill ANNA 2 132 110 0 RI. 6 f, 14RAIDWOOD I 22 11GURE 6 01 OCONI.l! 1 IM 1100kE 6.7 IIRAIDWOOD 2 24 1100 Rl! 6 62 OCONI'li 2 136 I i 16U RI' 6 8 likOWNS l'l RRY 1 26 110U Rl! 6 63 OCON!:l! 'v IM , 11bCRI'f,9 11ROWNS 11 RRY 2 28 1100 Rii 6 (4 OYSil!R CRI 1.K 140 1100 RI? fi lo IIROWNN ITRRY 3 30 11Gl'Rl! 6 65 PAllSADl3 142 11GU Rli 611 IIRUNSWICK l 32 '10U Rl! 6 66 pal O VI:RDi' 1 144 1100 Ri! 612 BRUN% WICK 2 M 110U PJJ 6 67 pal O Vl!RDI: 2 J46 11bl RI: 61) in RON 1 % 110URE 6 (A PAlO VI.RDI 3 148 l 116t'kl! 614 inYRe)N 2 34 110U Rl! 6 69 Pl% C11Ilo riO M 2 D0 l lGURI' 615 cal l AWAY 40 110UlW 6 70 l'1%(111tOITOM 3 152 , 1100 RI: 616 CAlNI:RI Cl111% I . 42 110URil 6 71 Pl.RRY 154 i i 16tJ Rl! 617 CAlVI:RI ClllTS 2. 44 110UREL?2 Pil GRIM .56 ' 110ERI: 61h CA1 AWilA 1 46 11GURl: 6 73 POLNr tilMCil 1 1% I 1100RI 619 CATAWilA 2. 4 110URE 6 74 PolMI tilMCll 2 160 l 1 IGt!Rl: 6 20 Cl.IVI O N 1 . 50 llGURl! 6 75 PRAIRit! ISl AND 1 H.2 1100Rl! 6 21 (OM ANClit PI AK 1. 52 11GURE 6 % PRAIRll! ISL AND 1 IM NGL Rli 6 22 COOK 1 56 110URl! 6 77 OUAD CTill31 1(e i lh0 R!i 6 23 COOK 2 58 11GU Rli 6 % QUAD ClllL% 2 ltA MGURI624 COOPER Kl A110N to 11GU Rl! 6 W RIVliR llEND . 170 116t'RI 6 25 010 SI AL RlVI R 3 L2 11GU Rl; 6 80 ROlllNSON 2 1 72 11GURI 6 26 DAViLillMl! M IIGURE 6 81 SAI I M i 174 - nbl Kli 6 27 D!Al 10 CANYON 1 f4 11GURl! 6 82 MiliM J . 14 1101 RI: 6 28 DIAltlu CANYON 2 68 11GURE 6 $3 SAN ONOl RE 1 178 11ht'RI:(.29 URF%DI.N 2 N 11GURl! 6 M SAN ONOl'RE 2 1hd 110U Rl! 6 30 DRI'hDl:N 3 72 110URl!6h5 $AN ONOFRI: 3 182 HOURI: 6M DUANE ARNO! D 74 11GURli hb6 slArtROOK 1M ' 1IGl'RI: 6 32 l'AR' "Y l 76 110URii f37 S!!OUOYAll 1 IM 1IGURI: 6 33 l'AIG JY 2 78 nGUni! 6 hk SEQUOYAll 2 l'E N, , l'IGURI: 6M ITRM12 110URii 6.35 IT17PA1 RICK
, 10 82 nGURE 6 59 Mi!MRON ilARRis nGURl!6% SOtJill 117A51 192 194 5 ,
110URI 6 36 1 ORT CAI llOUN M nGURl! 6 91 50Lrill TI!XAS 2 196 1IGUhl: 6 37 GINNA 56 110URf n92 Fr. l.UCll! 1 193 MGURl: 6 3R GRAND Gull' M M G U Rii h93 Nr. LUCIE 2 2m 11Gl'Ri? 6 39 IIADDAM NI CK 'M 11GURE 6 94 SUMMP.R 202 MOURE 6 40 11410111 92 nGURE 6 95 $URRYI. 204 11bt'RI:641 IIA 10112 94 1 (GURE 6.96 SURRY1. 200 11Gl;RE 642 1100E CRI:l'K % 11GURl! 6 91 SUh0Ul:llANNA 1 208 s nGURE ft43 INDI AN POIN! 2 98 DGUlW 695 $USQUl:llANNA 2 4 210 DOURI ( 64 INDIAN POlVI 3 100 11 G U Rl! L99 T11REE Mllli15L i 212 MOURI o45 Kl:WAUNI E 102 IlGURl! 6 tw 1 ROJAN 214 1100RI: 6 46 IAhA11I? I . IN nGURE 6101 TURKEY POINT 3 216 IIGURl! 6 47 I ANAL.11: 2 14 110URi? 6102 WRKEY POINT 4 218 11GL Rl! 6 48 1IM! luck 1 los flGURI! 6103 VI RMONi~ YANK! E 220 11Gl'Rl! f 49 1.!Mi id CK 2 110 11GU RE 6101 YOGT1 E I 222 IIGURE 6 *0 M AIN!! YANKl1 112 IlOCEI5UIO YOU^II II 2 - 224 PlGURI: 6 51 MCOUIRl! ! 114 110URE kl46 WASil NUCl.!AR 2. 226 11GURE f,107 WA'll:RFORD 3 22h 1100 RI: 6 52 MCOUIRi? 2 116 I IGUIW 610h WOLI CHI l.K 230 MGURI t.53 Mll.lNf0N1: 1 111' 11GURE 6100 YANKl%ROWii 11G U RI: 6 54 Mil.lNIONE 2 120 nGU Rl: 6110 ZION ! 232 2M l g HOURE 655 Mil 1510N!! 3 122 11GU RL : 6111 /lON 2 2% v1ii I, I
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1 ANALYSIS OF Tile l'EltFoltMANCE INDICATOlt DATA FilllOUGil DECEMilElt 1991 I 1. INTitODUCTION Th l1 Nuclear Regulatory Commission (NRC) report presents performance indicator data through December 1991 for 111 reactors. There are ;ipt indicators in the NRC Performance Indicator Program for Operating Commerci l Nuclear Power Planm (1) autornatic scrams while critical, (2) safety system actuations, (3) I signiGcant events, (4) safety system failures, (5) forced outage rate, (6) equipment forced outages per 1000 commercial critical hours, (7) colh clive radiation exposure, and (8) cause codes. I This fourth quarter 1991 report is based on performance indicator data that are ei. traded from Licensee Event Reports (LER) submitted in accordance with 10 CFR 50.73, in4 mediate notiGcations to the NHC Operations Center in accmdance with 10 CFR 50.72, monthly operating reports in anordance with plant inhnical I specifications, and screening of operating experience by NRC staff. Radiation exposure data are obtained from the institute of Nuclear Power Oper ations (INPO). Graphical presentations of each plant's data, including trends and deviatiens analyses, are prmid:d in Part I of this report; Part 11 provides tabulated summaries of the data.
- 2. BACKGitOUND Since hiay 1986, an interoffice ta L group has been working to deselop an overall NRC program for using I quantitative indicators of nudear power plant safety performance, in July and August of 19s6, the group conducted a trial program for 50 plants with 17 prmpective performance indicators. For the n,ost part, this trial program used data through calendar year 1984. The group then elected eight performance indicators to be I recommended as the best set for initial implementation. One of thes", corrective maintenance backlog, was deleted by the staff following consideration of industry comments.
I In October 19S6, a prototype repor t was prepared by expanding the trial propam data to 100 eperating reactors and including the data through the first half of 1986. The stalf's recommended program, the task group report, and the prototype report were documented in SECY 86 317," Performance Indicamic,drted October 28,19S6. I The Commission was briefed on the staffs recomn; ended pregram in November 1984 and approved the implementation of the program in December 1986, instructing the staff to delete the enfortement action indes from the set of indicators. In February 1987, the first quarterly PI report was issued and provided to senior management. This report covered the calendar quarters SS 1 through 86-4. In $1ay 1987, an annual collective I radiation exposure indicator was ineciporated into the liist quarter 1987 report. This was later revised to a quarterly collective radiation exposure indicator and incorporated into the first quarter 19S9 report. In 1989, as documented in SECY49-04d and SECY S9 211, the staff proposed that a new performance indicaror based on lg cause codes be added to the program. Through Staff Requirements hiemoranda (hRht) dated hf arc.h 15,1989, 3 and August 10,19s9, the Commission apprmed cause codes as a new singular perforr . nce indicator. The new l cause code indicator was subsequently incorporated by the staff into the program beginning with the second ,I quarter 1989 report.
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E 3.1)El?!NITIONS Ol' Tile l'EltFol(MANCE INI)lCATol(S The performance indicator data picwnted in this etport are cattroiirtd sturdine to spnifit dsfinitions. Ihe i definitiera of ths cight indi,4 tors sura ntly in the program are pimided bilow. 11 Aulonialle Scrams While C llical (Scrants) ,
'I hk indicator rnonitors the number of unplanned autornatic urams that va uricd while the ollutt d trattor was critical. Esamples of the types of urarns included in this indicator are lhose that resulted from unplanned transients, equipment failurcs, spurious signah, or human crror. Also indoded are thme that vuurred during the execution of procedurcs in which there w.o, a high chante el a stram occurring, but the ouurtence of a scram was not planncd. Scram data are primarily derived from 10 Crit 50.73 Licensce Esent litport (1. Ell)
, inforrnation and supplemented as necessary from to 0111 50.72 Iminediate Notification reports. The teattor was *ditical" if the n port so states. Otherwhe, uiticably k determined from a duailed revicw of the othc' E oper ational infor mation. lhk indicator is similar to the unplanned automatic wrams per 7000 oitical hours 3 indicator of INPO. In addition to the data for thh inditator, su ams abme 15"i powu pcr INO uithal boun and suams from 159 power or bclow are proviJed in Pan 11 Tahics R3 and K4 respecthcly, as supplementa' information 12 Safety Splent Actuallons (SS \) ' Safety splem aduations are manual or automatic ntuations of the lorit or equipment of either cenain Emergency Core Cooling Systcms (liCCS) or,in re(ponse io an a tuallow uitage on a sital bus, the Ernergency ' i AC Power Spiern input for this indicator are derhed frorn LElls and supplemented by 50 72 reports. In determining whkh events should be counted by thk indicator, the following consention., are used.
- 1. Only actuations of the liigh Pressure injection Sptem, low Picssure Injedion Sptem, or Safety injection i Tanks are counted for pressurized wat6 r reattors (PWits). I or boding water reactors (llWils), only i
auuations of the liigh Pressure Coolani injedion Splem, Low Pres (ure Coolant injection Sptem, High Pressure Core Spray Splem, or low Preuure Core Spra) Splcm are (ounted Actuations of the itcactor l Core Isolation Cooling Sptcm are not wutted.
- 2. Actuations of Emergency AC Power Systems are counted only if the) were in response to an attual low E E
voltage condhion on a vital bes.
- 3. Logic actuations of any of the equipment sociated weh the speofic ECCS or Emergency AC 1%cr Sptem g are considered necessary and sufficient to wnstitute a da6 munt. For cxample,if only a vahc in a splem 3, is mmmanded to mme to its emergency operational position, this is counted as an actuation. A pump does not hase to be commanded to go to its emergency mode of operation and fluid does not need to be injected for an occurrence to be counted.
4, Only one ECCS actuation is counted in any one occurrence, esen if multiple ECCS sptems actuate during the occurrence, for esampla actuation of both ti.e liigh Pressure Injestion and the Low Pressure injection l Sptems at a PWit during the same occurrence munts as only a single ECCS actuation. 58
- 5. Only one cmergency diesel generator (EDG) actuation is counted in any occurrence, even if multiple EDGs g actuate during the occurrence, for esaiaple, actuation of all four EDGs at a unit counts as only a single E actuation for that occurrence.
ft Occurrences imohing actuations of both an EDG on a dead bus and an ECC$ are given a count of Iwe. one for the EDG actuation and one for the ELCS actuation 2 I
1 !I i 7 At multi unit sites that share equipment (e g , a swing [D(i or shared buses? ~tuations are sounttd and , auigned to the unit at which the actuation signal or loss of power originaici .4 the sienal source cannot be auotiated with one unit, the actuation is auigned to both units. ,I 3,3 Significant thenis (SI:) i Significant events are those esents identified by NRC staff through detailed wreening and eutuation of opercing esperience. Tha urcening proccu indedes the daily review and diwuuion of all reported operating reactor events, as wtil as mhcr operational data such as special tests or construction activities An esent identified from i the arcening process as a ognificant event candidate is further evaluated to determine if any actual or potential ' threat to the health and safety of the public was invohed. Specific namples of the type of criteria are ; summariicd as follows: I 1. j)sgradationJd important 4Assyiprnsnt lhents a considered under this utegory indude situations that had the potential to reduce or actually reduced the operational capability of equipment. One esample is the identification of a comrnon cause failure rucchanism, which could uuse redundant components or multiple l independent wmponents to f ail in response to a test or actual demand signal. This category does not ! 1 include such items as a missed suncillance test,if the equipment was subsequently tested and determined j l to be operable, j l 1 l'.norIStfithDLr13ponse_lo a trandent, thents considered under this category indude situations in whkh I changes in reactor parametcrs represent unanticipated reductions in margins of salcty, For example, a rapid , plant couldown following a reactor trip cuterbated by a balante of plant malfunction or :m undesirable , sptem interaction. This category does not includ- minor differences in predicted and obsened conditions l that can be reasonably esplained by instrument erron or moJeling techniques and simphfying auumptions. jg 3. IAgr_ahtion of fac1 intecritygmuy coolant preuurrAundgirnpyrpnt auociatyd stingars thents considert d undct this category indude those of similar character to those identified in item 1 abme, related !g j to nuclear fuel, reactor wolant system containment,0: ' uportant plant structures.
- 4. p ram with wmpl ation i thents considered under this category are scrams that occurred while the affected l tcattor was critical, followed by an equipment failure, malfunction, or perunnel error. The failure,
- malfunction, or ctror generally does not indude those that lead to or directly caused the scram. Failurcs
} that boih cause the scram and reduce the capability of the mitigating system (e g , electric power, instrument j air, other audliary support functions, or delicient procedures) are counted, i d Exampics of equipment failure /mounctions i dude: , . }ji is,atinnystgm l f ailurr.3 Loss of redundancy due ta single failures, reductd capacity, or margin.1 his indudes components or trains out of senice for rnaintenance. l I . Failure addine to complaity of event - Erroneous sontrol spiem re.sponses, clectrical swiuhing difficulties, mitigating system and key plant parametce in3trumentation malfunctions / failures. 1 . Additional evtnt initiatort Stuck open primary or secondary relief / safety whes, pipe breaks, and j operating wrong equipment / trains. Eumples of personnel crrors include e improper control or termination of mitigating sptem. j . Mkdiagnosis of the event or failure to follow prosedures. l 3 ( iI 1
._..-.- - -.- - - - - - . - . . . . - - . , , - . - . - . , - . . , - , , . , ~ . . , _ . - , - - ,
i in addition to the situations dentibed in items I through 4 bose, olhu bioad categories comidcred for I significant evenh italudc E
- 5. ,L'igkrtnqitgket of rad; oat thitt thena considered under thh (uitges) include unplanned relea<es oi a radioactivity that had the potential to cuced or actually cuceded the hmits of the Tnhnical spuifkation' or Regulations.
I h 1)peration outsisinfhr linniudjht.Tnhniul $pmqu!inni ISena considen J und,r thh category include ouurrences when plant operation was conductcd incomktent with the license requirementt This utegory applies to risk significant deviations and most likcly does not include intidents imohing miued suncillances, small erron in setpoina, or other adminkiratively inaperable conditions
- 7. DJhtr, thents cor,sideral under thk utegory include a series of events or returring incidt nh that alone arc not signi6 cant but when considered collatively represent ineffecthe wrrective actions, or a dc6cicocy in the plant hardware or adminktrathc programs.
3.4 f afely Systent I?allttrn (SSil Safety sptem failures are any esenti or mnditions that wuld present the lulGliment of the safety function of I structures or sptemt lf a sptem ..inskn of multiple redundant subspicms or trains, failure of all trains wnstitutes a safety sptcm f anure. Failure of one of two or more trains is not muntcd as a tafety splem failute- 5 The dc6nition for the indit 4 tor parallek NRC reporting requirements in 10 CFil 50.72 and to Cl R 50 71 The E following h a lkt of the major safety spicms, subsptems, and components monitored for thh indiutor: Accident Monitoring Inittumentation low Tonperature Oscrprenure Protection Ausiliary (and Emergency) feedwater Sptem Main Sicam 1.ine it.olation Yahes Combustible Gas Control Onsite Emergency AC & DC Power w/Dktobution Component Cooling Water Sptem Itadiation Monitoring Instrumentation Containment and Containment isolation Reactor Coolant Splem Containment Coolant Sptems Reactor Core Isolation Cooline Sptem Control Room Emergency Ventilation Sptem Reacter Trip Sptem and instrumcn;ation Emergency Core Cooling Sptems Recirculation PumpTrip Attuation Instrumentation Engineered Safety l'eatures Instrumentation Residual lleat Remmal Sptems Essential Compressed Air Splems Safety Vahes M i Euential or Emergency Service Wate r Spent fuel S)stenn g Fire Detection and Suppreuion Systerm Standby 1iquid Control System is station Cordenscr Ultimate llcat Sink I> 3.5 Forced Outage llate (1 Olt) Forced outages are those required to be initiated no later than the end of the weekend following the dkmvery of an off-normal condition. flased on the data prmided in the monthly operating reports, the ioned outage rate is the number of forced ot,tage hours dhided by the sum of unit service hours (l c., generator on-line hours) and g forced outage hours, 5 3.6 Equipinent l'orced Outages per 1000 Cottienercial Critical llotirs (El'O) This indicator is the numba of forced outages caused by equipment f ailures per 1(m critical hours of commerci.d reactor operation. It is the inverse of the mean time betwccn foued outages caused by equipment failures. The imerse number was adopted to f acilitate calculation and dhpin. The source of thc- data arc the same as that for the foued outace rate 4 E
I 3.7 Collecthe l(adiation ihposure This indicator is the total radiation Jose acumulated by unit pctsonnel With the extcption of the Indian Point I and Mdhtone sites unit ulues at multi unit sites are obtained by dhiding the station total by the number of units contobuting to the esposute. 'Ihe Indi n Point and Milhtone sites report indhiJual unit uluet 1he radiation esposure data are obtained from INPO and because of the reporting techniques employed in gathesing the data, these data lag the other pctformance indicator data by one quarter. 3.8 Cause Codes Cause codes are intended to idcntify possible deficiencies in six procrammatic categoriet The (ame codes trcnd data are dercloped using the NRC's Sequence Coding and Scarth System (SCS$) database. Any esent can base any or all of the cause toks ,migned to it, but only one of each type can be awigned to any one event. This I database h deseloped from all 11Rs, not just those auotiated with spetific esents monitored by the other pts. The programmatic catep ies and their deGnitions are: 3,8.1 Administrathe Control Problents Management and supervkory deficienties that affect plant progrann or activities are included in thk tategory. I 1hk (ategory covers the implementation of the numerotn functional dkciphnes nuessary to operate a nutical power facihty tuch as operations maintenance, licensing. design, health physics, etc. thamples of a!Jminktrathe control probicms include poor planning, breakdown or lack of adequate management or supervisory control, inadequate interdepartmental coordination, poor communicat'.on between supenkors and staff or among I departments deG(icncies resulting in weak or incorrect operating, surveillante or testing procedures and departures from program requirements. The adrainhtrative control problems category n used if there is evidence that a particular problem is recurring and no effective corrective action has been taken $pecific cumples are: I . e No corretthe action after a design problem is dkcoveted. OA/QC problems. I . e Itadioacthe shipments withoat labeling. Unauthorized work acthity. Unqualified personnel performing plant tasks. I 10 Cl R 5039 review not performed.
. Personnel contamination due to lack of warning signs.
. T(chnical Specification suncillance not scheduled.
. inadequate proccdure resulting in inadsettent safety injection I 3.8.2 1.icensed Operator l'rrors I 1his programmatic cause category captures errors of omission or mmmksion by bcensed reactor operators during plant activities. These errors may initiate esents or may be committed during the course of an esent.
Licensed operator errors typicalh occur due to carelessness lack of experience or training, fatieue, strew, I attitude, or poor work habits. Impioper supervision n aho included wheneser the esent is the result ofimproper instructions ghen by a hcensed opcrator, such as an operations supenisor of control room shift supenisor. Not included in thk category are administrative wntrol problems such as incorrect procedures or inadequate planning acthities which causcd an operator te take inappropriate actions. Eumples oflicensed operator errors I include:
. Operator withdrew control rods out of oider.
I . Opciator failed to bypass suam discharge volume high lesel trip follow ng a trip A second trip resuhtd I 5 I
E 3.8.3 Ollier l'ersonnel Errors ) Thk programmatic unw uregory uptum ctrots of omiuion or wnumuion committed by non licensed personnelimolved in plant activities Induded in this category are plant stall (technidans maintenance workers, equipment operaton) and contiact personnd Not induded in thk category atc adminktrative < ontrol problems such as incoric(t procedurn or madcquate p!anning attivitics whkh uused psrsonnel to take inappropriate actiont Thk cause categor) k used in conjunition with the N1aintenan(e Probicms uttgory when an event is the result of a personnel crror irnohed with a rnaintenanc: acthily. Eumples of other pusonnJ cerors indude: i e Tcst personncl inadscriently shoried two cables while performing test. j e hiaintenance personnel omitted two fasteners while scauembling uhe epcrator. g e Steps in suncillame procedure performed out of order. g 3.8A Maltdenance l'roblems The intent of the maintenance problems uuse category is to upture the full ronre ul problenn which can be attnbuted in any way to programinatic defidendes in the maintename lunslional organiution A(thities , induded in this category are maintenance, testing, sunditame, ubbration, and radiation protectmn. 1 hc ' i deliciencies noted within thk category generally lead to inadequate or improper upkeep and rcpair of plant equipment and systems or inadequate programs to monitor equ pment and piam perio man;e as nctewar) to present hardwait failurci 3 E This is the broadest of all categorics and i intended to idenoly areas when improved plant perfortnance k possible through a program whidi indudes such thirgs as increased attention to d(tail, more frequently g performed surveillances or the use of better trained personnel.1hc hiaintenance Probicms Cauw category k g used to track the performance of plant management's capabdity to properly repair failed equipment and to prcdude equipment f ailurcs through improved presentative maintename programs. Additionally, as an indication of potential maintenance probb ms hardaare failures whkh unnot be rudily attributable to any preventable l uuse are ako induded in this utegory. Staintenance rekted errors are olien coupled with other cause categories such as Other Pctsonnd Errors or l Administrative Control Problems lhe N1aintenance l'roblems category is used in conjunction with other 5 catcgories when an error occurs while a maintename, suncillame, or test activity is in progress whether the error was the result of a delident procedme or a personnd error. 3 5 3.8.5 I)esign/ Construction / Installation / Fabrication l'roblenis This utegory covers a f ull range of programmatic ddiciencics in the areas of dedgn, construction,installatwn. and fabrication. It is used in wnjunction with other cause categories when necessary to capture all contributors to the esent. One eucption te the use of additional categories k that since the scry nature of the design proteu implies a personnel error,it is not neccuary to also induded one of the pusonnd error categories for the dedgn er ror itself. Eumples of the problems induJed in thh category are:
. Check valve installed backwards resulted in I(llit userpreuurication when isolation uhe was opened.
. 'lransmitter wnting lines rescased.
. Lou of control power due to undctrated fuse.
. the of wrong seal material resulted in soknoid malfunction.
- Equipment not qualified for the Unvironmcnt.
i + Dclect dkcosercd in pump cadng attributed to a manufacturing prou ss. , 6 4 I
- . _ , _ . _ . . - . . _ . _ . - , _ . . _ . . _ . . _ . . . ,, . - . . _ _ _ _ , _ . _ _ _ . . , .~
i l Tbc design modification prmess is an ongoing task at nudear power plants. thamples of deugn nmdification j problems it'duded in this category are: 1 j . Intorted interpretation of plant drawings led to an incorectt design modification padage.
- . Incorrco modification radage caused the installation of a component in an unlawrable configurat!
)l j i5 (e.g , incorred wiring, inwrrect location of instrumentation tubing. vahe installed in wrong line, etc.). Post modification test procedure is inwrred duc to inwtred information in the design modification package. j i i I This cause category may be used in conjunction with other cwe (amgc.,,es wh as administrative control I pr oblems. l l 18,6 Equipment Failures (Electronic l'iece l' art or Ensironinental I(elateti l' allures) !I l l This categoryis used for spurious or one time failures of eleuronic piccc parts and failures due to incteorological j conditians such as lightning, ice, high winds, etc. E)coronic wmponents which are induded in this category are i arcuit cards. uctifiers, bistaoic, fuses, capacitors, diodes, resistors, tran,du(cu, .onplifices, and computation 1 rnodules, i lg This category doe > m3 indude failurcs that can be attributed to other problems, such as maintenante problems ig or design /wnstruction/ installation / fabrication picblems. Additionally, failures of mechanical equipment for j whkh a cause can not be specifically identified are included in the maintetonec problems category, thamples of cledronic piccc part or emironmentabrelated failurcs include:
. I'lashovers occurred in switchyard due to high wind and rain from a thunderstorm.
jl . Capacitor failure in instrument power supp'y caused loss of signal from containment leakage detedion jW radiation monitor. 4 . Surges from lightning i.trike close to plant propgated through the plant cledrical system, causing the ! main generator to trip. I t l 4, DISL'IM OF l'EltFOltMANCE INDICATOlt DATA The performance indicator data are presented in this tcrort on charts and tables as di3cuwed in ti,e following sections. 4.1 Quarterly Data ) ? , l'igures 6.la through 6.111a provide indisidual charts of the quarterly data trends for each of the pis for each
- plant. Ilased on six quarter mming acerages, thew chans display long term plant trends for cath indicator.
- theept for the cause codes, these charts also display the industry six-quarter mming aserages to provide a j wmparatise performance lesel, with industry mean valun for safety system failures and collective radiation j$ exposure computed separatel3 for boiling water reactors and pressurized water reauors. Additionally,
- 5 distinctions in the industry average calculations are made based on plant age, l'or older plants, the industry averages are the older plant mean values; newer plants indude both the newer plant and the older plant mean salues. Also, except for the cause wdes, individual bars displaying the actual quarterly indicator data values are included. To present a picture of the plant's recent operating history, the plant's critical hours are included for automatic scrams while critical, safety system actuations. and collective radiation esposure.
I I 7 i
.l
- I 1 4.2 Trends and Desialions g
f igurcs 6.ib through ri.111b wntain two tharts that prodde plant profiles of the trends and dedations from wtresponding performance indicator d.act The Short Term Trcnds" chart dkplays the numbcr of standard g desiations by which the plantN mosing ascrage to the most recent two qu.oter pcriod saries from the plant's g moung average for the most recent duqu..nct per;oJ. ' Ibis information is prodded for all of the Pts eucpt wilecthe radiation exposure. The "Dedation from Older Plant Meane (harl displays the numbt of standard desiations by which the plant's modne aurage for the most recent sioquartcr period varies from the inJustry's idquarter moung ascrape Newt r plant Agures aho contain a ' Deviation from Newer Plant Meanc (hart that j displays the numbcr of standard denations by which the planti rnoung ncrage for the most rm nt duquarter ' period varies from the newer plant industr)N sioqu.utc r moving ascrage. 't hese desiation charts are provided l for all of the Pls excc1 t collatne rodiation esposure and uuse wdes.
- 5. COMPUTATION 41 CONVI:NTIONS g 5 ,
The following consentions are used in the calculations and displays for this report,
- 1. Ccriain plants are culuded from the report and calce!ations as follows
- With ie cucption of the collecthe radiation ciposure calculations plants in estended (i c., lone term) shutdown, whcre Commiuion approsal is required for cither rcyan or operation abuse low power, arc l N
culuded frorn the industry average calculations from the first full quarter alter shutdown through the last full quarter before startup. Additionally, to avoid distorting the forced outage rate industry aseran, since a singic pint un add almost a full percentace point to the merage, the shutdown plants are aLo g culuded from the forccd oulage rate industry merage cakulations for any quartcrs at the beginning or 3 i end of the shutdown pcriod when the plants were not shutdown for those entire quarters. Radiation l cxposure can be significant during outages, henct be industry ascrage for milettive radn. tion esposure g includes all periods, even those periods when a plant is in an estenacd shutdown- In addition to these g l selective culusions. Rancho Seco ceased commercial operation on lune 7, P>so, and is culuded from l all Pl calculations after the second quarter 1999 Likewise, fort St. Vrain ceased all operathms on l August 29.1989, and is culudcJ from all PI cahulations after the third quarter los9 Fin.dh, no data
- are capturcd or included for Shorcham. The following hsting tabulates the culuded plants and the I calendar quarters for which the ulculations werc eJ),sted for this report.
l e, I W1l'DI D Pl.R!OD l's W ! M i L. D1 D P1 IW il' PI Nel' I r Hu 'l () t it "I M .I' f( All l'()R r 11111 R Ph E Itrow n l'crn l I note Pc rmJ l'r.mc h ouJ ltrowns i cus 2 'l hrough 912 t hn+yh 91 1 Unm ns I crn .1 l'nnte Pen d I rnte Pcnm1 l'on $t Vron Ancr h13 Aner WM Peach ILotam 2 'ltrwgh W 2 lhmugh val Peach lionum 3 'l t rough vat through v'3 hlgnm 'llrudgh D-l lhrqh U *I Rancho Nco Aft cr W2 Ahcr W2 thruwph Fii
~
N abn.m >k throgh h L2 Neqw7 9ah I lhrough M 4 Il rogh 5d T dnk t(-!L m t Antr Vld Af k r 91-3
- 2. llepinning with the stwnd quarter lW) report, the comrncrcial operation date useJ for Clinton i3 l Nos ember 24,1W7. 5 1 New plants are delined at those plant s that har not wmpkted one I di caLndar year of operation after receising a full power license.
8 E
-- . - . - - - - - - , ~ , . . . - , - - - . . . ~ - - - - - - . , - - - . - - - - - - - - - - _ , _ . , , - - , - . . - -
l
- 4. 'NA* is used under the following conditions for newer plants:
e for safety sptem actuations, signiGeant events, safety sptem failures, and cause codes, until an initial I e operating license is first received. l'or automatic scrams, until critical hours are first reported. For forced outages and equipment forced outages, urail commercial operation is iledared. for collective radiatian esposure, until the beginning of the first full calendar
- car of commercial I
e opc r ation. Thereafter, numerical salves are used. For example, a plant shut down for an entire quarter after initial criticality has rero for scrams rather than *NA".
* 'NA* is used for collective radiation esposure for the most rceent quarter for all plants, because these data lag the other indicator data by one quarter.
6- For those plants in estended shutdown, *NA'is used for all displays in the Trends and Desiations charts with th, esception of the cause codes. 7, jndicator values of 'NA* are njd used in calculating averages and standard desiationt Zeros do count in such (alculationt R 't he Quarterly Data charts (1igures 6.la through 6.111a in Part 1) are based on: I e Older plant averages culude plants in long term shutdown and outliers greater than or equal to 2.5 sta ndard deviations above the quarterly mean. The averages for safety sysicm failures and collectisc radiation crposure are computed separately for liWits and PWits. e Newer plant averages are single numbers representing the eight-quarter averages of all plants meeting the definition of a new plant during each quarter of the eight quarter period.
. The plant's userage for the most recent siequarter period (if there are not at least two quarters of data, no salue is displayed on the chart),
- 9. The Trends & Deviations charts (Figures 6 lb through 6.llib in Part 1) are based on:
A. For the " Deviations from Older Plant Long Term Meanc and " Deviations from Newer Plant Meane charts; e The plant's average for the most accent siequarter period (if tl,cre are not at least two quarters of data, no salue is displayed on the chart).
. A recalculated mean of all older and newer plants' most recent sioquarter period averages
'I e (culuding those plant aserages greater than or equal to 2.5 deviations above the original mean and the averages of plants in extended shutdown).
'The standard deviation based on the most recent sivquarter period for older or newer plants (recalculated after escluding outliers and plants in estended shutdowns, as discussed above).
It for the 3hort Term Trends' chart
. The ptant's average for the rnost recent two-quarter period
. The plant's aserage for the most recent sivquarter period (if there are not at least two quarters of 4 data for this aserage, no value is displayed on the chart).
. A standard deviation based on the plant's most recent sicquarter period data.
I e I _. __. _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
I i 10. Report changes: l l l . lleginning with the Grst quarter 1h9 report, the indu(try arciage forced outage rate is higher than the ! I values reflected in earlict reports, primarily due to reclassinution of an extended shutdoan of Nine Mile , i Point 1 to a forced outage (from the licensee by Ictter dated March l',19s9).
. lleginning with the 6rst quarter 1989 report, the industry average for equipment fou ed outues per Itm ,
j commercial critical hours is cah ulated using industry totah of equipment forced outages and commercial i i critical bc.urs. ;
. 11eginning with the third quarter 1089 report, the industry ascrage forced outage rate is calculated uung j industry totah of forced outage hours and generator on lin: hours.
. lieginning with the third quarter lWO report, the hcr' field in the esent description uction of Part g,
] 11 has been renamed Tower llistory' and provides more av. urate information about the status of the g i plant at the time of the esent.
+ lleginning with the first quarter PNI report, the uuse codes data are included for all quarters covered i by the report.
. lleginning with the third quarter IW1 report, the collectisc radiation esposure data are reported beginning with the Grst full calendar year of cornmercial operation.
l l l 4 l l 1 E i I ~ I, I g. 10 8
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% -- r o t JC u . t n : v> 3 n< s., w su.s v < xa w . v.s n. m w na w. .
YPE = NgY lff 10M C%tr It*f O e
- 3. Sigraficant th erit s 4. Safet.t S3 atern U n t!u res I
# I i .
l s s
- 1. %93- j
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wi i . e*. 3 ~ p ;
- 7. * ., ! ., , ,
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e . i so . , e_3 w> . 9 s i s . aw a si. 4 j wt m? x.3 e s e.i e.,s 3 v s
,er Garte ; m - Ju te
_ . . . _ . _ . __ . _ . . _ . . - . . . - - . . . . . ~.- _ __.~. - __. - - . - - - . .
-{
(L Equipnient Forced Outages /
- 5. foremi Outoge Itate (t) , 1000 Corninercial Crit)ctd flours
-7 w . _ _ _ _ _ _ _ . . _ - . . , s e ,__ . ...
i
! f I i
.[ % n w_
; $A a ,ye b t4 y4 -
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._-:....__._,.- _ _ . . ~
l
- 7. Collmtive liadiation Exposure rio.. _.____._ - ___ ____..___,_g,>,, 6 C.au se ( odes I,c l..
I
,,9. y 7 '
LIC OPER W ,v,. .. 3.l
.,~. ~j
.y 'w ' r - - '-
ADMIN
-----p OTdEH PER
~ " - - - - -
e- . \. a i, . . j , i <
$ W iy (y. - ,%5l w.. -.. a : -- - J J
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-. f --
Y M C o 1, .n: - !; - . . M...A I N T.-. DFSIG N E F.Al_l I
+
- I 3 . .QU. ..l P__ -
a - t s J2+ t i 4 P i, I I i j i ,' e j ._ O Ca.-.. C J, L D..a.L,.! d. oE3.f,L l m a . < a , v. . Ja vem
- f. #
1 l (W 2 j l
.! .-_,_ t,
. . - m. _ ., 1 m . _ . - . _ _. _ . . . . - . . _ . _ . - - -
I l 1 E1
. _ _._. ._ _ _ .___.-..~.. _._._._ _. _ ..._. .____ _ _ _. ._. -
t it i >K f!GURE 6 2L iI l T
-- ~ ~ ~ ~ ~ ~ ~ ~ ~
4 Deviations l ! ARKANSAS ?- Sho't Term from cider
- Trends Plant i nna
! TRENDS & DEVAT!ONS lerm Mearis 4 l_ Dectirwuj iny>r oved Below Avg Above Avg. j 1 lI . - [ 1 Automotic Scroms WFW Critical .. p o7 . Ot , i - l , AL i m - I
\
2 Sofety System Actuations o. _ a; i ,.u . l 3 Sigccant Events - o - o7 i N a. i e ~
, :q
~~'39W ..
4 $0 etf I byStem IOdure$ - -05
'~
- ,f @2: -- 17 I?f W C<r'so co to Pwit ***
4 ,,.,,, - l l 5 Fvced Outoge Pcte - -o n ? . 07 1 . I a -
., e, i>
. 6. /[LUO Commercialqtypenent Crd colforced HoursOutoges
- 02 -04 q
- h. - D i
j 7 Cause Codes (All LERs) r i i i N mwniren cont e Ax n. :M1,, -25 "15 -05 05 15 25 4 teerwecreen er.s. , _ y c, 0 en *
- Om Pav W I 7c Otra= Fe sM E"o*_
7a w'e<m e ** a _ se asggnuswnweme era,~,_ gw e( q u T er n was (Woks ed b S'amourd Dtvot#M (6 Otr Avg eN 91-4) o n t w rau. , i r- i 7 15 -05 05 13 ^ 5 te mta a tocm cw v,t e or p w n ys i (h4w&s erf e $10sdnr G Dewetsong) (2 Otr Avg et 91-4) I 'S
- - r-w -- e
l fICURE 6jo
~"3
.i.-.
-,g q j i i
\/ k g- l- h. T.,
,-s , a bxotor De ht t Otr ums An"y I
LOQOM---- . . . . cr;t cu nus sammus Wrt (. as t er umy a.c.c p E 9G-1 to 91-4 QUARTERLY DAT A ltm k m *e g
- 1. Automatic Scrain.= Dhile Critical 2. f afety Systetu A-tuations 4-___ -
3 a .I _) am _::w E ___ _ _ _) 2suo .,:wb fg ~w pxo " 2(A _ xec " yz'~ g .] 0w f f(#M _ uw 3
.4 ; q wu # dJ '
rim m
'jx .
y 2_ \\ h < cso j- v *~e:_ .\ a rw & 4e um \ / s ou
.ma 5f, ,
\/ m3 d4 ," i / in y q2 3 \/ qA 3 L- pL 7.q--.7q_ y 4 / ._
Ni_ _ smessen - 0 2 T-'~' T ~~r __m
"'-'J0 1'
A 0 " a6 1 i s . j W 1 B)- ? W-3 9)--4 P- 1 9k2 gu3 Swa 6 7 b-3"si-4 964 962 963 9'4 , Y ear -- vuor ter ter - wr t e< P
- 3. Significant Event s 4. Safety Systern Failures ,
4 . . . _ _ , l l Ja H" s m 3 n 3'
%E
- 2. 1, <12- 9 Iy t- T
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.)
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a.- - s sa : * ) e4 9h1 s s? 9"3 P-4
, , .._$--.7- Q{ _.
I Y eQr Ckt:-t er f e.y - Quyla 6 Equi forced Out nges/ tu
- 5. Forced Out ag. Rate (t)
,g e .,_1060 o>pment ooncretal Critical flours i p.- l n e
hh *~ he_
%<te .-
n p a= g 3? *3 *r*- 5
g 40 7~
Ts b i ., , .., J[h 2 124
. !A . -."ame . 3 -
pp p oA R c . _.6.E L A.i y .4 a Q _J o _h., , SQ y , t r- --- Eri-1 90--2 90-3 W4 9h' 9b2 bb3 964 W 1 stw? W-3 W 4 9b1 94 2 9t-3 Wh4 Yey - Quwter 'f ear . Ny t er zoo -
- 7. Collactive Radiation Exposure
._ 2.zx . 8. Cauw ( odes I
I* 2* h .--ADMIN LIC- -OPER OTilER PER
~ " = . .
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,l .u., + M AINT ...E_QU_IP FAl,l, g
7 _ DES _I.G._N. - g 0 ,4 ) 25-0 a MM.I'.2_g L*'._J o g 3 ' 1 ' o . c;2 r.2_ __ i st 62 s3 64 v'- > 6 2 sc 3 ea.4 y ear - bate
! V l' ,
% wv .-v m---
{et - r-e-vv-,j { rvv+vm-4 .A-...-.--- -.%,._,.w.-..-----..- - d e R
I I I l j r c ure e an [ I Shor t Term Devictions BEAVER VALLEY l Trend; f{lont rom Long Oder i TRENDS & DEVtAitONS Term Mearis Declinecj inpt oved Below Avg Above Avg. l 1 Autorrati: Scroms WW Crttical - -09 ! - 01 Pg .y I 2 Sof ety Syttem Actuotion5 1 0 d' s to
--)
E 3 Sgrwficant [ vent 5 04 -
-09 a 26 e 3 4 Scie ty System f olures . ep
-04 -
-07 s' c
\
_ a W Civ4KFfd to DN M*W4 m - 5 f cir c ed Quicge Rot e - -o s
-11 e
?Y.
^'
.m lemmek
"?
&r/63bwant eu, Fr/ced Outoge> -O ', s Commercio! Coticot Hour s - -
~0 4 7 C ause Codes ( Ah Leks)
_a i
'o A&verertwe Cor4*ol A ote . 43 n$ ~ - ~b Nlb Ob I U
.I 't t r w 'e ms
- a _ f;S0T) _n LM"a 6 M" O'*' Pk)"t 10*3 J
4 m a4M irm wem 7t Otre Forsw (nor y -
- c. (hssed c waisc De,mtoss) u mm,s waen .. l: u (6 Ctr Avg end 91-4)
- .towja u.oame.. na F, go ns-.<.. ,gg i -25 15 -05 05 15 25 cmin i< a,= cr ent 6ce 4nst we *
(MJ3=A fd O b'3tWY J On desi ( l (2 C+r Avg e ,5 91-4) j
'L _ -.. . _ . - _ _ _ _ _ ._ ~ _ . _ _ l 17 l
1
1 FGURE 6.4o
..c_. _ . . _ _ _ . . _ , ,
1.""r3
. a atatx
-+.- __ AV _. R. . \W. L_r-.,Y e.. -
_L e a.e_e g ,, , % n
--~~
, emass hit 6 www u;< +, s ~e. .ge 90 -1 10 91-4 OUARIERLY DAI A j 0"i l ' ' "' h *'
._. .__-_.._._._....__----.,i_---.-__.---...--- _ ._ -
- 1. Autninatic Scrarum h bile Crit ical C. Safety Systein Actuations e . _ _ _ _ _ _ _ - _ . ~ .
7, nw . .
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, WI Db: W.1 t'b 4 9L1 th : 9b3 95- e i* r- 1 92- 7 W - 1 X.=- 4 Ob1 S t 9 F. 3 31-4 i Yey b ytM i e.ar Q.s t ot y- _-._ . _ . _ _-. - - _ _ . . _ . . - - . _ , - -
t
- 3. Significant Es ent s 4. Safety Syst ern f ailures a y 4 k l E tc&a _ g43 3 3
u t, s
-4 t
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59 4 Cd' b (ti_ r- - >
.e
a i.
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- 3 w-4 9i-i ob: 953 m4 >
1eV - O't.'Y l er ley - QofyIF
- 6. Equipinent Forced Outages /
5 Forced ')ut age Rate (t) 1000 Cornniercial Critic al hotirs ! sx ,_ . _ _ , . . _ _, A s, _ - . . . ._, j 7- c - l 1 3
- cs ,} b +gl e .,! I gR _
L 4; t-bd V UZ k' 5y # e' J ! E u q en
'S 6 pj-9 vi t i n iz 4 5 20 _ , ,
__ 0 46 e m- [~ y_L 7 q , ,
'a
. ] o .t_
_ r- r---'1 . . a) $ $3 -; ab 3 %- 4 $bt 94 2 SL3 9L4 's t W 2 W .1 W 4 Shi 9L. U-3 9b4 ! r ear - Ou v res
, . . _ _ - oo i e _ _ _ _
- 7. Collective Rachabon Exposure f !
- 00 syx.- B. Cause Coi.les j
- ,, 5 s . . . . .. ... . . . . . .
"y; i _A D_MI N , _l..l..C gt it 1',0 . u '
O_P_E__R...,O_T.l.i_E_R PER-4 h m t,4 .
,so
.1 y
O"u 4 - y- 750 ~ 4
-w t-~ - - , -
1 5- -
?i M AINT _. D w . Sa; 3 m._FSI EQU.IP Fall.
a_a A enaf Ni ! !1,_- G iNl-I
= !
e, m e3 m a., ,o s.3 e. i
- !: :i; i i
.-- - - - . . - - . - _ . . ~ . - - . - . . - - - . - . . -
.L.--
.m,
. . . , . , ~ . .
I E_
t 4 i iI; l i 5l ig _ fIGLrRE 6 4b i : !I i Deviations i AEAVER VAi LEY 2
~
Shut Tenn f rorn p&n Tr er.Js Plant tong TRENDS & DEVLATONS Terrn Means Dect;ned in7 roved Below Avg Above Avg j 1 Automatic Scroms wh;c Cntr.ol - -o4 - oi 4 i 2 Sately System Ac tuatons _ 04 _ 0.2 4 b 1 5 m ! 3 $ignahcant Events - o o7 (" X., m " l
- 4. Sof ety System f oetures - 09 -
-03
~
ssr etw<res to P** mr. 5 forr.ed Outoge Rote og - 09 t I. m ,& 1 ' WE 6 Enu. ment Forced Oatoges
-09 i%n 11 l / IdCJ ComrrerciT Cntico' Hour 5 -
n
- l. 2A i
e
- 7. Cause Codes (All LER3) i ,_.-.7 ,- ,, .
A n 4#v troi~ cwira we _ g3 ,, 15 -05 DL 15 25 i ^ I a tu s a. air p<w.m _ 3, t~nece tre h Pont tem T erm +res 7C c't w bFr $CFFWG I frDr _ .,g ) (McC5 deft h sf 0rWJd bes01.Org)
- l. 7d *rama **
- a (6 Otr Avg eni 91-4) j .r/ ,mi.or/r on,<ai e e,m.e j %'] ca S(
4 7 c w ra.me rave _ u f _
! 15 -05 05 15 2' h pra,ot.cra tram carev 5 ote vet unn 5
(Wud ed e 90<4rd Ot.iotum) 1 C Otr Avg cos 91-4)
; L_ -_ . _ . . _ _ .____ _ __a 10.
4 1
I FIGURE 630
- tra watu R,( 0,K EL~s Pt @ H- - Legend: . . . _ cc,to o ~ " -' <
wu, ot< - 4 ~ ~ ~ eswans F kr>t 6 Oux t e' hAzv ^) Av er o r 90- 1 to 91-4 OUARTEPLY DATA h ors le< a4 km i 4._ _ ,._ _ ,_ _ _ _.,._- _ . . _ l 1 Autornatic Scratus W hile Crit ical 2, Saf et" ' y Systein Actuationt 4_ m ., e 19e y _ _.__ - __,_. _ , _3 2 :a A '{ l N [g ~ " " *
- r. J;u d 3 ~ '
):ne ')
y[3" / .tw 2 .f g # - _ eso ,4
.a
_ tw u, <; sx +
, 2- - t:9 $t 1, y 2 / oc $
y? h i_ um
*$ y) 2i
/ _
n .> x f' 5x 6 i -j4wNo cl C . .- A 2s0 0_.._ [O.1!-l
. .l.-
i 7 .7._, , , , , ._ 0 , 7.__d0 uc. i m. ; w 3 w e p i. os : es3 ese A>->e-7903m 4 9s.i su r Su s o.. ; v ear - w ier to - w tv 3 q i
- 3. Sigmficant Events 4. Safety S) Aent failures 4 a
.____......_q f h3_
O a. 1, E
- 23. 8 s *I2 y l'
.y.H. s. .
k0 , {$ l d'$- g 2 '- .- j pq I '- ! e , f~, , ._ o. __..T4.___7__r j i j wi m2 #3 w4 n.i su: 953 Su. m i w # 3 90 4 wi 9u2 .,_7._. u s te- . Year - Qa t +w 'Nr - Q,s y ter {
.. __ ._. - .__ 4
- 6. Equir nent Formd out ages /
- 5. l'or&d Dutage Rate (t) 1000 Coinmercial Critical llours E ga g to y __
($M_ 6A66- j oo n l e0 4 5 Q .y-- *~ y. 4 4g _ U$ , 21 2% n 7 ..
$ <. 0 S 125 125 l 1 !. e i h pO c t' ' , T -- - - - > Y i' 0 L; i
-T m-- v-- t- ,
w t 90 7 w3 w e Ubi 91-: $L3 9b4 w t 3.b2 90-3 w4 91.-1 9k2 9') 9b4 Y eGr . Op t er Y ggr _ Quqr t er 4 _ _ q 1
- 7. Collective Radiation Expmire l i
tL L, aux Cmles i
- m__. , we. _ ;
I
#2" pg I ADMIN . Lit OPER, , -
OTilER PER c----... ! e 15 0 _ w$ - t
- 3 l
;4 m w
N,w p _ mp tcc _ .,,_ J
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ff ~ plJ mt 3 _ pe _ ;= _ sw j MAINT ,__DESIG N_,,_ p M JA!( c -_d2 6 ld E &E]3Pd;" M si e2 a 64 ,,u g 2 g 3 J4 y ear .- Os er I g
._._ u.-. { - -,,.
I E
LI I FIGURE 63b I oeviams BIG ROCK POINT snort Term from ouer Trends Plant Long i TRENDS & DEV!AllONg Term Means Dectired Irnproved Below Avg. Above Avg I
.A
- 1. Aut omatic Scrams V(hie Critico! - O -
14 N _g:- 2 Sofety System Actuutions 4 04 0.2 I ! 3 Sign 4fic ont Events - 04 _ _og
~
,I .' -m-4 Sofely System fodures _ o4 a 13 w t..we.s to ewe wr, 7
! V
- 5. Forced Outage Rate _ _o ;
I cy _
.f; s I
- 6. Jgupment Forced Outoqe a ~
07 7 KOJ Commercio! Criticot Hours - l0 M. I 7 Cane Ccas (Au LERs; To as,nwoi.., c e m r,w q g -2 I5 d5 5 b 5 I n, u.
, tw o e.e
,Lg C+mocru ;eom J.sw em tong l 7q Cve Pesarm ["re , 4, g l( OWMJ ed e Stasud Owectum)
M wc a P'ew* . _e . ; (6 Otr Avg enti 91+4) I
'e c.wr /was.<>tr er. cow er ou ,
a j n taw r.we 4 jg
! l I i i r 15 -05 05 15 25 texaces f*om Csvt s our Fe a wn I (%ss ed e St:rwo t e. u-ens) f ( .7 Otr A, g erd 91-4)
I ! I 21 1
E FIGURE 6.6a ns r- ,s -
.. c:a hotor f--.i i, f--. k-)- i b O@IN-
*#' I' * ""N " W Oacanas auseum hyd 6 Qucy tr M p.n; emap 90-1 to 9b 4 OUARTERL1 L%iA um W km j
- 1. Automatic Scratus While l'ritical 2. Saf et y S ,tuations
. ., 1_. _yst ern. . . _ . _ . .__._.,: . ..
gg0 3- - _'wr _ :9.m + ec )gg{ m j ::M )
; ;w "
; t b63- i i 'M T j
.] g ,; IN / ; q
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3 - \.
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tx p 1 y:- g._ i q inc ; j, tw - zy \ due t 3 *. _
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m3
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- 3; l
o_ ... LQI.,.I lJ _4^ t m ---O - U U'- - t- - #p- -- W ---- r-- --- r-- 0 w,-.i s u w 3 v 4 s u i 2i- 2 9 w . Si_4 m i + 2 90 -3 a;2 4 93_i o i. : 93 3 p-4 T P:V - Q2 t er M ety - D ir ter ; _ . - _ _ _ . _. - _ . _ . . _ _ .___--_-_._,j 1 Significant Events 4. Safety System Failures e _ _ _ _ - _ . _ - . _ _ _ _ _ _ _ . a,__._.__.-_._.._.._ __ . _ _ . m
- E k3- _.3- !
05 EG
'6 E x2 w!
~<2 r
i. 2. k, r. -
*$ % ,v E? i i a 3 i
*4= s~ i~
RC # I __ P I II I e i__..i. w t 90- 2 90 3 9)--4 9b- 1 91 2 9 43 9 L e a o__> 9.
. i 1
& ? 10-3 9C+4 9uf 91-7 91- 3 9t-4
%.- T-.__ _r-_J .
~
year - hay t er Y ear - Ouy t er l e H
- 6. Equipinent Forced Outages / I
- 5. Forced Outage Rate b) , 1000 Commercial C rit ic al licurs !
7 m g s _ _ _ _ v , ,l ;>
. 2
- E. oc .4l - o 26 l 9 y ee_
t , s- . yJ k 4 [4 E
%a **>4 4 6>43-# ,_ e' i 23 n. $5 ys "-
as:_ m ; f r 13
.'. R s
y
~
h r,D4 ( e 97 0_. _ a, . -
@ .__a ', 0 4_ y ..._., . . 9._.T < -T-
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--J 90 1 m w3 w4 p i si_ 91-3 9u4 n-t m z m 39,_. 951 su n. 3 sp4 Ye:1r Quyler 1 e<F - Quat ter
_ _,_m
- 7. Collective Radiation Exposure !
- ce , .._ _._ :sw - 0 (.ause Cudes ;
?.
... ~..,..
~
#h m A_D_M.. I N ,_. L_IC OP. _ER__ O_T.i.tE. H. .__PER. ., l i & " -- J gy b
., ISM ~ _ l e oc J _ rx s 1
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~
i % -- tl / y 42 DESIGN E M AIN.T__ 7--QUIP !
-- --Fall, m
- w. _ "1 _
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- q ;
c.1 wh, _b] 4 A m
.s,-,-3m.
[.N_I_l h [ 3 j g',%, ~ I i 1 i , . ,m v L,-,. ,,_ t . .
,,: ~,-,..,__s <
L___ . - . . _ . . _ - . . . _ . . ._--_,.__.-.....--..._--,.__.-_-...---~J I R.
, 5 FK;URE 6 6b I Devotions BRAIDWOOD 1 snor t Term tr om oider Trends Plant Lona .i TRENDS & DEVIATIONS Term Mearis Dedined impr oved Below Avg Above Avg I 1 Automatic Scroms Wne Critico' - c -
- t:
..s
- 2. SCf ety syste n Ac tuat.ons _ c4 _
_c s
-I 3 Sigs hc ant Events - e o7 , .25 L:'-
- 4. Sofety System ro bres _ a: . g 55F Cmw = Pwn umrs 5 Forced Outcge Rate - 0 (s -? s y -32 I. '
d.) ~4 I 6. Eqqmprt Forced Ostoges
/ lut. ; Lommercia! Critacci Hours - 0 ~ -09 b]
i I 7 Coase Codes ( All LER3)
?o wwv~. cere-a s a m _ , -25 -15
-05
, r 05 r
15 ;5 Bij g I 4- u er== h ow Pra m . botw feom cor e et tong a tem ue<r.
?c Ctrwr Pasarve t"U' d { g, iMew.r ed c Stoor d Dentions)
! l
't * * *
- P'***** J > n* (6 Ote A v g end 91-4) 4 Cevr/Wtmon/ramaton w oe m .
I 7f f aW Faure 0 7.- 7 , 15 -05 05 15 25 I De ew>eu f rom Currecit ( Ctr rewt Mrore (%mkrea e Seardcy1 De oes) (2 Otr Avg era 91-4) I I
I FIGURE 6.70
] gp ,- CJ WW Ct D/ 4
; % /k )g ! (")(q) .)
L.eGe n6 - f** ha"' C Q" Mw ' 9 b e o4* C r it acel Hws s
-- nya f u.ai eru Aer y 90u to 91-4 OUART ERL Y DAT A M Te m "+*m I, Autornatic Sciants While Critical 2. Saf ety
- Systern* Actuations 4 -
Wn .. 4,- _, r Oc .. AN h N 2M b A{A l [6A T. . . ,, _ :u " ! mc " h g, 3 - / IN E' 563 i 3
,\
j , 7y j q%e
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0 "- -*- - ", w' r .-7--T-w 3 W. 9 t. , ,s: va w. i'"E -- ---]a so ' Y egr - i mor t tw iect - (gmy Ier 3 Significant I' vent s 4. Safety Systern Failures 4 - _ _ . - . . _ _ _ . . _ 4 . . _ _ . _ _ _ _ _ . _ . _ . 1 : ,h .i
- sa, w
3E
>t- B n'I i
ib l (- a i 7f ' j{ a[( i lj 1 2^r~ 1 i e n FA _ . . .. n' .- i e-,...,. 90-1 9D-1 W3 W 4 9bt 96; 96, 91 4 c d d. W1 W2 W3 W4
. . _ , ', .h ',
9b; 9b 3 914 Yey - b7 Wf Tec JW1 ory t er i p _ __ _. _ % , l 6- Equipment Forced Outages / j
- 5. Forced Outage Rate (t) { e 1000 tomtnercial Critical Itaurs -
E
- ut .
; ga __
U
- 80 (f [
IK 5 c $ 6 -- !
}. W - kk l E
k 40 V* e*, . 5 Un ((6 ! ! f zo _ e s'2- m g, ? _._.._-_LQ , E c> r*1
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.._ ____, . ~ _ . _ _ _ _
l I l 7. Collective Radiation Exposure 8. Cause C, odes ce _ nc-E, , ch
- A DMIN 1.lc O_PE_R._ _OTIIER PER i v 10c .4 l
!?
s m .. 8 s, l .s C p *a n V 4 sa ! c. > n ec . . - , , , - w,, -,. , L r . , - - A
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I
I I F6GURE 6 7D l Deviations BRAiDV/OOr) 9 Short Terrn trorn Older I TRENDS & DEVtATIONS Dechned Trenas Impr ovea Piont Lenq Term Mearis Below Avg. Abme Avg
~ \
1 Automoti: Scroms wh* Criticai . _i4 - es
,_. m ,
T I x 2 SOf ely System A0!uotons - o _ ta D I 3 S gnficont Events . o4 - _o9 I 4 Sofety System f o:iures . _o 4 ! i - o_7 I ssr cmow to w w,.
~'
- m i f ceced Outo ,e Rate 3 oo I
_e 4 _ I l t 6 Eqeenent Forced Qutages
/ LOO Cornmeract wtica Hours - -05
-04 y
b I *
- 7. Cause Codes (Au LUb) u m,,,,,m. c*. ~ ~ _ pxg .o disxG
- : ', -15
-05
,M 0$
7- _d is 25 I l, 4 t. cms cw w.x pre , , De,,et e tror= Gier Pwt Lnj 1, .- 7c Othe Pe sor s e4 ( r or ,g , gn.j g e Slythd Dehs)
~--.~-J 4p , 3 m, A.g em s.,4 7 tow >m m,pam - wm Q
g - m. .~. . 4 gg 15 -05 05 1.5 25 I f Dm*.ess troen C.e r ent 6 cir P ,9 wears (MeOSJ apj c $t M ird De.ot: Orts ) (2 Otr Ag erd 91--4)
,=
-- - _ _ _ _ . . _ _ _ _ . _ . _ _ _ _ _ . _ J 4- d
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)
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spegue P.y.t 6 @,0y tee 1A; , , t, A v r a ge i 90-- I to 91-4 7UARTEPD DATn -N km * *' I p_..____. I
- 1. Automatic Scrains W hile Critical 1 Safety Systern Act u at ion s a.._ .nc- m:.
( 4.(
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- 3. Significant Events 4. Safety Systern Failures l j 4 - . _ 4 _ _ _ _ . _ _ , ;
I
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- Qun t er y -. _ _ _ - _ .L._ __.-.-
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- 6. Equipnient Formd Outages / i
- 5. Forced Outage Rate (4) 1000 Cotamer cial Critical 11ours !
7" ioo M * {e 2 __.._..)> i (~ te I;'
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, - _ . - l Tem - ovorty % - cur t er j
- 7. Collective Radiation Exposure B. Cause Codes mo r. wo_
S ADMIN LIC OPER OTl!ER l'ER r;e E4 4i u = r i . i 1 1 ]
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em m w
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, . _ . . , _ _ _ , _ , - ._.___,a ;
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._ .._.___u._ _. _ _ . _ . . _ _ _ _ _
s I B ,
E RGI.RE 6.Sb I Deviations BROWNS FERRY 1 short Term troen cuer Trenda Plant Lono B. TRENDS & DEVIATONS Term Mearis Ded:ned imp oved Bebu Avg Above Avg
~
T ] g
- 1. Auttentic $Uoms Wh4 Ctificol _. m . y 2 Sof ety System Actuatens , y ,g I
I 3 Sigrwficant Events - S _ m I 4. Sclety System Tr'Ju r es . y _ y I sv cm*> w to s** iwn 5 f er:ed Outoge Rote . m _ y I. I 6 [rqqcment Forced Qutoges OJO Commercial Critical Hour s - ** -
! 7 Cause \_oces ( Al L ERs) i , ~ . . ,
u u,,em . cm sm _ ogggg -25 - t s -o s os n := I m _ e_ __ . , ce _ ,_ m, ,_ m , f er m wme h Ot* E emvw4 tsw - u ,g , (*c>sJ ed 6- ',t rord Oew:'uns'. N wme.wcerm e j .y - 0 (6 Ctr A v g erd 91 -4 ) h Desp/w 'va wis aacoson o<ota b ,,
-E ,, e - ,_e _
g ,,
-25 55 -03 05 ;; 2.s I Dnoere ' cra c ar e-e 6 otr Pkr* ww.
( W 9J9C e St}WN d Ch<ut tes) (2 Qh Aug end 91-4 )
- I ,
- _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ . _ _ _ . . _ _J 27
I I C URi. C30
.. . _ _ . ~ . - . . . ~ . . . _ _ _
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- $*.a wn,b gueues Myt ( Quy t y ).t wg Aarage 90-1 to 01-4 0;mRIER Y Dri A R:q te= hew 1 I
^
. . . - - , . _ _ . - _ - . .f l
1, Aut omatic h rumt While Crit ical 2 Shf et y SY ht em Act u ntion s
< . - . . . . . - . _ - - , u, 4 . .:._ __ .- _ _ ... ._ , :u .
y a :29 is [ q:ta b h !T 3. ,/ J [_" . k ,$' a ,/ "_[_. m 1
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. _ - . . . - - . - - - ~ . _ . . . - . .
I
- - . ~ . - . . . . - - - . _ _ . . - , ._.f 1 Sigm ficant Es ent s ! 4. Saf et y System Failures i 4
s,......-..-..-_, - . _ _ - . . < j m . . - l ( Tb, l i
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. - -ed m-J 9 b ? 91-3 91 4 i
l 4 eas - }>.x t er tear -- V{lb rat t1er t. _______.-r. I es
- 5. Forced Outnge Rate B) l 6 D tiprocat 1000 'ommercial formd Cntmat Octafour/ t s t
w .I n5 ' d mj -'. . _ . s .[ ! !
- 2. u 2 ET e 3[b ," 6 .
e'- t 'i t kJ W - $4 l I j *? t in _ s . 4 "r*-
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s tu to 3 b e w 0' ,O,93 jiWM ""! '
+
- c. ; ,
1_. . . .- C _ - c;;ag _.a o.._- , .A. _ 4 a4_ m- 1 10-2 4-390-4 9 :- ! 91 2 9 E.3 91 4 l 59 - 1 90-'903904 9bl 9b2 96 3 9b4
'f eaf' - Owyler ^f gGr - Os& t e'-
- 7. Collective Radiation Exposure 8 L,a u se Codes
;m . ysx; . .- ,s
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+. ; w-: ns m u w na ne
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-- _ _. - .. ___. - - . . - . -- -- -~ -. . .
i
) , FGURE Cn9b y-i l."' Deviaticns
! BROWNS FERRY 2 shor t Ter m from Older 'g Trend.s Plant Long
- 3 TRENDS & DEVIATIONS Term Means
, Declired Irnpr oved Below Avg. Above Avg f;ll
^ " ~
i
! Automatic $croms WNe Critical - _o? _
_i; ,y {I m a .aC
.m .
l l
- 2. Sofety System Actuottons _ o to i @s 2A l
l - fM1 3 Sqn ficant Event s - o _ o7 4 . .e I d m , l 4 Sclety Sy st em F c 'ur es - og . og ) m: ssr cmen to swa um
- . my j
, 5 T c<ced Outoge Rate . o . s oy i ' C., I , - m ,. 6 i Forcea Outoges iOpi b 07 ;' ' jE / tbbbmentCommar cio: Crrticci Hours - -24
~ -
{ e ' gw: e . l 7 C:ose Codes (A: LERs)
.-- e , -
gy. 7n Amstrot. e Cortrat praem _ g -25 +- 15 -05 05 15 2.5_ wv.C 'I I % LCeted Ct4rator Nem , =$ fevic?cre trorr Okjer Pt;nt Lorg I 4, d Term kems 7c Other Pnrscrees Errot = 04 (MWE fd 80 S'Etlard Cemt.cng) 7* " "** "* (E Ctr Avg end 91-4) {
>. ,-, _ . .._' "p_ : .. g kg(f so I 7ei m raue, i
15 -05 Y e 05 J J 15
~
2.5 I l l l Ductic+s f om Cw er:t 6 Ott Par 4 kwn
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(2 Ott A sg e vj 91-4)
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4 WRE 6100 3 g1 , . , 7 - ,.3- , a ha e, D I\ ..- J I Ll l' ) -[ -b-DOIN b o *u " m" s6
" ' I ' "#
Mates I i ir d 6 G r y t er L4]. r; Adrcp 90- 1 to 91--4 QUAPif RD DAIt i.org T er m benesi
- 1. Autornatic Wrn ms While .__-.:=,.. Cri'ical 2. Saf et *y Sy st em Act u a t ion s s,--._.._.__. a
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- 3. Significant Esents i 4. Safety System Failures 4 ,-
l 4 l l r T 3 E
- h3. 6 e. n 3 u; g IM> i <i :.
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- 4C.wr t e:
new % ter _ ' -l - _ . . . _ . _ _ _ _ _ _ . . t l 6 Equipment Forced Out ages / l S. Forced Outage Hate p) ; , 1000 Commercial Critical Hours 7 m _ , g a __ _ _ , v
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Yew - Uta w yer - v a- t e r i
.____._..._j
- 7. Colixtive Radiation Eymu.e i 2m vu, _ B Cause Codes .
i b l f w g ," *, g , ADMIN l !C OPE.R_, - OTHER PER j i e 0.7 - " 3, X. 1 Ig [ Ya $.
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_.._._-.____._.-.__.,--_.____.____-._____._._a-.--- -- - --- -,-------_ .- I l B_
. . - - . - - _ _ . - . _ _ . . _ - . . . _ _ _ . _ _ _ _ _ _ . _ . . ._ __ __.r.__.____-
s !I t iljg- _- FCURE 6=_10b -_ _. . . ___ i lI l snor t Tenn Deuations orn car BROWNS FERRY 3 f(iant tong lE Trenas e Terrn Means 5 TRENDS & DE/LATIONS l Dechoce Irrpr oved Bebw Avg Atiove Avg. lI i i
- 1. Autom0 tic Scrams Whk Critical . y y 2 Safety Sy stem Actuations . y y
+ t k I 1 I 3 S gn.hcant E v ents - 9 J v { i f 4 Safety System Fcav ees _ y y 4 D (N'46 9tl lO NN MN45 f 5 Forced Outage Rote m y i) in 6 fqsnment For:ed Ou'ars
/ luGD Commerctoi Critcol H;3ur s - M -
M ,w i 7 Cause Coaes N LERs;
. _ _ - , , c , _
j . 7 u,,,-~. u,u wm _ y' ,, v -$ -o s os is 2$ + e.ss l % Lgersal C(cots PerAem , g Qwat.org, ff 0m Cadgy Pkst Lyg ( , l ar m ><> s j 7c OtPe N torvet ("or . . o, (wwsed n sto,osa Dutve) 7a umstee %*"'- % is (E Otr A<g erd 91-4) ll 7-, w,+.tu.o.vr 2, - % _ ,,
,, . . - , ~ . .
3 ,,
, l., 7-I -25 ~1$ -0.5 OS 15 25 i tw,oters from Cirr ect e C tr emt t%rs
]. (WM J ed e bfGFVRE J C8' Wrons) (2 Ctr Avg enc 41-4) I I 31 i
I f h_' URE 6.113
)
mg ,-m t" 3 Mc au bN
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4
- 1. Autoinntle % rarns While Crit ient 4
- Saf et y '
- ' Svetern At u nt lan h u .. g 4_- _ . . _ .__..-._..m. s..__.-.
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=- . - - . _ . _ _ . . _ , _ . . . _ . . . _ _ _ _ . - . - . _ _ - . , _ . -
4 N fety Syst ern f ailures I 1 Signif trant Events 4 _ _ . . . . . ___ _ ___, 4, _ :__L_.___._..___.. ..q l t, E i E T3. ? s 5. .L
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wi w: 90-3 we 94., v.: si-3 w 4 w3 m; m3 w4 wi w: w3 we l Y car QmW M Y e9f - Ouef t(*r _ _ _ _ _ _ _ _ _ _ .._ j l 6 ':auipinent Forced Outnges/ t
- 5. Forced Out age Rate N I 1(O) tornrnercial Critical llours }
m I e______..__.. , 7 (8 l l 4 % yfn O$ w 1, a 6 ._ 9m y a n
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't e :f - Quarter Y e ar - DSw t er
- 7. Colbrtive Radiation Expwure 3
2x . . _ _ _ ., so 8 Ca u se O.xles
' 2*
m I 5 ~ ADMIN 1.1C OPER OTilEh PER, a 1j 43 LO g I i
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kx/ . M- f* I i s , i 4 - l Tex -ww [' ~ ~ ' _.f ~~T.Ti.{1" ZZ' E.. _ L_. _ _ _ _ _ _ . _ ____.m._ x I E
I I FIGURE 6.110 Deviations BRUNSWICK 1 Shor t T enn f t orn Olde Tr ends Plant Lorq i TRENDS & DEVIATIONS Term Mea 6s Declined Impr oved B @ w Avg Above Avg. _7 1 Aut.omotic Scr oms While- Critical - 0 -
-06
- 2. Sciety System A tuotens . _og o; I 3 Sigrec oot Events d ,
o or rtghw 4 Sofeh System Folures o -
-07 sv uenneioe*a wo.
5 f trced Ouu ge Rote I ot -
-i3 1
I 6 f [100U Comrreccialqapment Cr +:6fHoa orced r s Outnes
* ~0 2 0' I / Cause Ccdes (All LERs) h m% ist ots.e c,a tr 5 b esmen' *M k .
_ __ 7. _ 7.A _,.. ,_ _ 15 -00 0S 15 2t 5'Md@ " I 4 twset a m_,s m _ , on,ot.ma t om Wer Pet i m I(W fTi bil'L98 h P' Ier tervel ( reer .. gg (bWsig m .e $tmuyv1 Dmjtainy) i b r>"" **w w (6 Otr %g ere 14-4)
,.s..,._,,_.__ g,.
I ; i
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L._ _
- s _n -as os r :-
I Cecot.(v1 f r 3m (3 pr.t 6 Qtr F t et Laemg I (w a *o < srvos 1 Dwc, <<C i (2 2tr A v g eed 91 -4 ) I i e I
- - - - - _ ~ , - . _ . . . . - ~ . . , - . - _
. - - _- . . . _ . . _ _ _ _ _ . . . . . . - . . ~ . - _ .
I FIGUW 6.120 r3 3 CZJ hr ct z D T L ,jls drjl-iib Leaend
- u -- ..
o m ,,,,, w r c" e am assume h 6 brter M >mrq Aiemp 9, 0 - 1 to 91.-4 OUARTE T3 DATA pr.2 Tem ' ' e~m
- 1. Automatic Scrntnn__,_.___.n M bii. G hical 2. Safety Systen Actuations 4.c..._-._. . 4 .% . W
.j.rw" 4 PM h eA j 22% .ue" W
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- 5. Tnreed Outage Rate b) , 1000 Cornmeretal Crit ical Hours i
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- - FIGURE 6.12b i l
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- oevianons i BRUNSWICK 2 Shor t Tern fron O!;.ier
- hend, s t.ong j TRENDS & DEVIATIONS 'erm Means
- Declined improv ed Debw Avg Above Avg.
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- / uol l Commercial Critrchi Nours - 09 -
02 ' i l .b 1 1 4 7 Cause Codes (All LERs)
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___ _ _ %n M Pky tt b Q AyiOf $4]vog A v t167 90-1 to 91-4 OL%RT E RLY DMA M*'**
- l. Autornatic 97arns While Critical 2. Safety System Actuations 4._. .__...__.__._,N. 4 _
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- 3. Significant Events 4. Safety % tern Foilures 4_._ _ . _ . - - _ . . _ e.,____ _ _ _ . ' _ _ - _ . _ . . ...__.-_q n, i i ch' To 2x3- '
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- g f'IGURE 6.13b r
- D.eviations BYRON 1 short Term from ouer Trends Plant Lorm
} TRENDS & DEVATIONS Term Mea 6s i Dedred impr o sed Bebw Avg Above Avg. 1 Automohc Scf om$ Whrie Cratical _ 07 c) i f - l _
- 2. Safety System Actuatens . _o g ,
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I FIGURE 6.14b Devia00ns BYRON 2 short Terrn frorn ouer I TRENDS & DEVATIONS Declined Trends trnpr oved Plant Long Tei rn Mearis Below Avg Above Avg. I - ,- 1 Automotic Scroms whoe Crit; cot . .a9 c7 i:a 2 Sofety System Actuotions _ [ c4 _ og I 3 S.gNficont Ev ent s - o4 -
-a s {
_ ..l xI 4 Sof ety System Fodu es _ c o . o3 I ssr tenysco ., ewe m i f orced Outage Rate .
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g, Tem w rs 7c. Otte Pesuve t'ror l gy (Wms ed o $'omky d Deve!a's)
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!,I Il i E - ~ ~ . - - - - . FIGURE ilSt> r iI I Deviations CALLAWAY short Term f rom OHer i E Trends Plant Long i g TRENDS & DEVIATIONS Term Means ) i Decliried impr oved Below Avg Above Avg l.i I i l' i i
- I"
' L 1.' Automatk Scroms Whde C r itic al - o . .og i WW . I n l' , 2 Safety System Attuatons - 04 - 02 I ] I v
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- 3. Significant Events 4. Saf ety S,nt ern Failuras i
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!nyar ov ed Plant L ong Term Mearis Below Avg Abo.e Avg I {
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(2 Ctr Av, end 91-4) a I 71 I
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I nGLTsE 6.30t; Deviations Shqrt Term f r c,m Older gqc;ggq 3 - 1 rends Plant Long I TRENDS & DEVIATIONS Declined Irroroved I"rn Wons Bebw Avg Above Avg. -l -s ~m y 1 Automatic Scroms Whe Crito * - -o g I 07 y il I 2 Sofety System Actuations o - 10 M I 3 Sign hc ont Events - -o s -
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4 f L FIGURE 6 31b 3 Devia! ions DUANE ARNOLD SnPrt T e' n f'orn Older Ir 4;r ds r>lant Long TRENDS & DEVIATIONS Tenn Meam Dec hr <:d impr oved Below Avg Above Avg t Automotic krams Wh le Critic al - 12 - PA } .
- 2. SWty System A:tuations .e4 _o s
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-._._.-.__3 i 6 Equipruent forced Outnges/
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FGURE 6.rb l L 7 Deviations t FARLEY 1
- rt * "' f rom Older Trends Plant Long
; TRDJDS fe DEVATIONS Tenn L'eans Declired &,; roved 8 tion Avg Above tsvg 1 AutomoR Scr ams Wh4 Cr 6c oi _ _o4 _
3p 2 Safety system Actuations _ _og op i l LL - I f t 3 $ignif:C ont [ vents -
~
o q o7 I 4 Safety Spiem fcJures - 0 - 13 s S/ c. ~sovo se Fwe wn f*3 l 5 f orced Outoge Rote - -c i c3 5 4 i n 6 j['qbpptr;nt for ced Outoges 0 *9 .l 03 t j tomrre aa! Crihcol Mc'ur s - 1 j U i
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l i 7 C ause Codes (M LEst)
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(2 Ott A ] e d 91 --4) l l
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- 1. Autoinatic Scratnw While Critical 2. Safety Sutern Actuations 4_..,________.____ 4 __
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- 4. Safety Systern Fai;ures i tA $ ! !
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- 6. Equiptnent Foren! Outages /
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( 71 1 c l 1 Automotic Scrams Wnk Criticci - o - _c c, F] ! :!s ' I w { 2 Sofety System Actuatons . ca o.2 q l J. !W 3 S:gesfu. ant Events - o - & 07 1 i , LJ i m W l
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