ML20151J686
| ML20151J686 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/08/1988 |
| From: | De Agazio A Office of Nuclear Reactor Regulation |
| To: | Shelton D TOLEDO EDISON CO. |
| References | |
| DB-88-019, DB-88-19, NUDOCS 8804210172 | |
| Download: ML20151J686 (22) | |
Text
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g UNITED STATES NUCLEAR REGULATORY COMMISSION l WASHINGTON, D. C. 20555 l
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Docket No. 50-346 Serial No. 08-88-019 i Mr. Donald C. Shelton Vice President - Nuclear Toledo Edison Company Edison Plaza - Stop 712 300 Madison Avenue Toledo, Ohio 43652
Dear Mr. Shelton:
SUBJECT:
TRANSMITTAL OF PERFORMANCE INDICATOR DATA The NRC Office for Analysis and Evaluation of Operational Data (AE00) issues on a quarterly basis, a report entitled "Performance Indicators for Operating Comercial Nuclear Power Reactors." The latest report dated February 1988, was issued in two parts; the first part contains plots of the more important perfomance indicators for each operating plant for the eight quarters ending on December 31, 1987. The second part provides tables containing detailed data as well as a description of the report contents. In accordance with the policy guidance provided in SECY-87-207, a copy of this report has recently been placed in the Public Document Room (PDR).
We are providing for your information, a two-page set of graphs pertaining to Davis-Besse which was extracted from this report (Attachment 1). The first page is a plot of the six performance indicators initially approved for implementa-tion in the NRC's performance indicator program. These are: automatic scrams while critical; safety system actuations; significant events; safety system failures; forced outage rates; and equipment forced outages per 1000 critical hours.
The second page is a statistical plot of the trends of these six performance indicators for each unit against itself (i.e., deviations of the last two quarters from the means of the previous four quarters). Deviations of the six plant specific perfomance indicators from the industry average for older plants are also presented on this page.
In reviewing this data, it is important that you recognize that the perfomance indicators are intended only for use as one of several tools which the NRC utilizes to monitor trends in performance for each plant. The SALP program, for example, is another independent approach for determining licensee and plant perfomance. Our approach to these performance indicators is that they can be used as assessment tools to identify poor performance, but only when the underlying causes of this poor performance are carefully assessed, evaluated and understood. Without this understanding, use of performance indicators can lead to a misinterpretation of the data.
8804210172 880408 PDR ADOCK 05000346 P PDR
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j To assist you in understanding our use of these indicators, Attachment 2 l contains a set of definitions for the six indicators cited above, plus the 1 definition of a seventh indicator, the collective radiation exposure. This I attachment also provides some additional guidance in the form of precautions and explanations.
Attachment 3 contains a seven-year history of the collective radiation exposure for your plant (Table 11.1) and a three-year moving average of this same data (Table 11.2). In Attachment 4, the latest SALP data for your plant is contained in Table 11.3 as well as two four-quarter averages of the basic six performance indicators. Finally, Attachment 5 contains the numerical values by quarter for the six performance indicators plotted in Attachment 1 (Tables 11.4, 11.7, 11.8, 11.9, 11.10 and 11.11). Table 11.12 contains the unit critical hours for each of the eight quarters considered in this report.
You should note that the notation "PREDECISIONAL" has been crossed out on each page of the report. With placement of this report in the PDR and issuance of the pertinent pages to the holders of operating licenses, this designation is no longer applicable.
If you have any questions on this matter, please contact me promptly at (301)492-3063.
Sincerely,
/s /
Albert W. De Agazio, Project Manager Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects DISTRIBUTION:
Docket-Files NRC & Local PDRs PDIII-3 r/f GHolahan KPerkins PKreutzer ADeAgazio OGC-WF1 EJordan !
JPartlow ACRS(10)
PDIII-3 Gray fil s Office: S E PDIII-3 hk PM/PDIM-3 PD/PEIII-3 Surname: MjLynch/tg ADeAgazio KPerkins Date: CV/c)/88 /88 t/ / y/88 l
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- 5. PETAILED DEFINITIONS OF INDICATORS The definitions of the seven indicators currently in the program are provided below.
5.1 Automatic Scrams while Critical (SCRAMS)
(IA) Total Scrams Total scrams are the number of unplanned automatic scrams while critical.
This indicator is the same as the corresponding thPO indicator. Examples of the types of scrams counted are those that result from unplanned transients, eouipment failures, spurious signals, or human error. Also included in the total scrams are those that occur during the execution of procedures in which there is a high chance of a scram occurring, but the occurrence of the~ scram is not planned. Scran data are primarily derived from LER infomation and supple-mented as necessary from 50.72 reports. The reactor is critical if so stated in the reports. Otherwise it is determined from the review of the information.
(IP) Scrams Above 15 Percent Power per 1000 Critical Hours 1 This subset of total scrams includes t'he automatic scrams occurring above 15 percent reactor power per 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> of critical operation.
I (IC) Scrams at or Below 15 Percent Power This subset of total scrams includes the automatic scrams occurring while the reactor is at or below 15 percent power.
5.2 Safety System Actuations (SSA)
Safety system actuations are actuations of the emergency core cooling system (ECCS) (actual or spurious) and the emer response to low voltage on a safety bus)gency. This indicator ac power systems is the same as the (actual, in corresponding INPO indicator. Input for this indicator is derived from LERs and supplemented by 50.72 reports.
In determining what items should be included in the data for this indicator, the following conventions are used:
- Only actuations of the high pressure injection system, low pressure l l
injection system or safety injection tanks are counted for PWRs. For BWRs, only actuations of the high pressure coolant injection system, the low pressure coolant injection tystem, the high pressure core spray system, or the low pressure core spray system art counted. No actuations of the reactor core isolation cooling system are counted, j Actuations of emergency ac power system due to loss of power to a safe, guards bus are captured primarily based on indications of low voltage signals in the emergency power system.
Actuations of any of the ecuipment associated with the specific ECCS or emergency ac power system are considered necessary and sufficient to These data are available as supplemental indicator data in Tables 11.3 and 11.4.
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. Attachment 2 constitute a data count. For example, if only a valve in a system is comanded to move to its emergency operational position, this is counted as en actuation. A pump does not have to be comanded to go to its emer-gency mode of operation, or fluid does not need to be injected for an occurrence to be counted.
- Only one ECCS actuation is counted in any one occurrence, even if multiple ECCSs actuate during the occurrence. For example, actuation of both the high pressure injection and the low pressure injection systems at a PWR during the same oc:urrence counts as only a single ECCS actuation for that occurrence.
Only one EDG actuation is counted in any one occurrence, even if multiple EDGs actuate during the occurrence. For example, actuation of all four EDGs at a unit counts as only a single EDG actuation for that occurrence.
- Occurrences involving actuations of both an EDG on a dead bus and an ECCS are given a count of two, one for the EDG actuation and one for the ECCS actuation.
- At multi-unit sites that share eouipment (e.g., swing EOG or shared buses), actuations are counted and assigned to only one unit, even if multiple units are involved. This count,is assigned to the unit where the actuatier, signal or loss of power originated. If the signal source cannot be determined to be associated with one unit, the actuatinn is assigned to the unit with the lowest unit number unless the licensee has specifically assigned the reported occurrence to a higher number unit.
5.3 Sionificant Events (SE)
Significant events are those ey?nts identified by the detailed screening and evaluation of operating experience by the NRC staff. The screening process includes the daily review and discussion of all repcrted operating reactor events and operational data such as special tests being conducted or construc-tion activity.
An event identified from the screening as a candidate significant event is further evaluated to determine if there is an actual or potential threat to the health and safety of the public involved. Specific examples of the types of criteria are sumarized as follows.
(1) Deg radation af important safety equipment. Events that will be considered uncer this classification include situations where either there existed the potential for or there was an actual reduction in the operational capability of equipment. For example, identification of a comen cause failure rechanism which could cause failure of redundant components or multiple independent component failures in response to a test or actual demand signal. This category would not include such items as a missed surveillance test where the equipment was subsequently tested and deter-mined to be operable.
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(2) Unexpected plant response to a transient or a maior transient. Events that will be considereo under this classification include situations where changes in reactor parameters represent unanticipated reductions in margins of safety. For example, a rapid plant cooldown following a reactor trip exacerbated by a balance of plant malfunction or an undesirable systems interaction. This category would not include minor differences in predicted and observed conditions that can be reasonably explained by instrument errors or modeling techniques and simplifying assumptions.
(3) Degradation of fuel integrit> > primary coolant pressure boundary, or important associateo structures. Events considered under this category would include those of similar character to those identified in item 1, above, related to the fuel, RCS, containment, or important plant structures.
(4) Scram with complication. A "scram with complication" is an RDS actuation, when critical, followed by an eouipment failure or malfunction or personnel e rror. The failure, malfunction, or error is generally not to include those that cause the transient which leads to the RPS actuation, or those that directly cause the scram. Failures that both cause the scram and raduce the capability of the mitigating system (e.g., electric power, instrument air, other auxiliary support functions, or deficient procedures) will be counted.
Examples of eouipment failure / malfunctions include:
- a. Mitigatina system failures - loss of redundancy due to single fail-ure, reduced capacity or margin. This includes components or trains out of service for maintenance,
- b. Failure adding to complexity of event - erroneous control system hsponses, electrical switching difficulties, mitigating system and key plant parameter instrumentation malfunctions / failures.
- c. Additional avent initiators - stuck open primary or secondary relief /
safety valves, pipe breaks, and operating wrong equipment / trains.
Examples of personal errors include personnel:
- a. Improper control or termination of mitigating system,
- b. Misdiagnosis ef the event or failure to follow procedures.
In addition to the situations described in items 1-4, above, other broad categories considered for significant events are as follows:
(5) Unplanned release of radioactivity. Events considered under this category include an unplanned release of radioactivity that had the potential for or actually exceeded the limits of the Technical Specifications or the Pegulations.
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4 (6) Operation outside the limits of the Technical Specifications. Events that will be considered unoer this classification incluoe situations where plant operation was conducted inconsistent with the license requirements.
This category would apply to risk significant deviations and mesi likely not incluoe an incident involving a missed surveillance, small errors in setpoints, or other administratively inoperable conditions.
(7) Other. For example, a series of events or recurring incidents that when considered collectively represent ineffective corrective actions, or a deficiency in the olant hardware or administrative programs.
5.4 Safety System Fail ~ures (SSF)
Safety system failures are any events or conditions that, by themselves, could prevent fulfillment of the safety function for structures or systems. Where a system consists of multiple redundant subsystem or trains, failure of all trains constitutes a safety system failure. Failure of one of two or more trains is not counted as a safety system failure. The oefinition for the indi-cator parallels NRC reporting recuirements in 10 CFR 50.72 and 10 CFR 50.73.
The following list gives the major systems and subsystems which are monitored for this indicator:
Peactor Trip System and Instrumentation ,
Engineered Safety Features Instrumentation Recirculation Pumo Trip Actuation Instrumentation (BWR)
Accident Monitorino Instrumentation Radiation Ponitoring Instrumentation Reactor Coolant System Safety Valves Emergency Core Cooling Systems ,
Auxiliary (and Emergency) Feedwater System (PWR) l Reactor Core Isniation Cooling System (BWR)
Isolation Condenser (BWR)
Standby Liquid Control System (BWR)
Main Steam Line Isolation Valves Component Cooling Water System Essential or Emergency Service Water Ultimate Feat Sink Control Roun Emergency Ventilation System Onsite Emergency AC and DC Power and Associated Distribution Containment and Containment Isolation Containment Coolant Systems Residual Heal Removal Systems Comt'ustible Gas Control Fire Detection and Suppression Systems low Temperature Overpressure Protectim (PWP)
Spent Fuel Systems Essential Compressed Air Systems
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l 5.5 Forced Outage Rate (FOR) l Forced outages are those required by the end of the weekend following the l discovery of an off-normal condition. The forced outage rate is the number of fcreed outage hours divided by the sum of unit service hours (i.e., generator online hours) and forced outage hours. This indicator is the same as that of INPO and the NPC monthly operating report. The data are generalty obtained from the monthly operating reports. In some cases when the reports are not available, the data are obtained directly from the licensees.
5.6 Equipment Forced Outaces per 1000 Critical Hours (EFO)
This is the number of forced outages caused by eouipment failures per 1000 critical hours. It is the inverse of the mean time between forced outages caused by equipment failures. The inverse number was adopted to facilitate calculation and display. The source of this data is the same as that for the forced outage rate.
5.7 Collective Radiation Exposeye.
This is the total radiation dose at the site for a given period. The site total is divided by the number of units at the site contributing to the radia-tion exposure to obtain unit values. This indicator is the same as that of INPO.
- 6. PRECAUTIONS The data for this report were obtained from relfable NRC sources as discussed earlier and were reviewed by NRC personnel in headquarters and the regions for completeness and accuracy. The data for the fourth quarter of 1987 will be reviewed again in preparation for the next quarterly report in order to ensure that late information, if any, is accounted for.
Although certain NRC perfonnance indicators are the same as those of INPO l overall performance indicators, the criteria for including the data in the l calculations for industry average are not the same in all cases. For example, '
INPO does not include scram values for a plant with cumulative capacity factor of less than 25 percent during the time period being considered in calculating the industry average. The NRC does not exclude such plants. Therefore, the industry average values of the coemen indicators are likely to be different.
Tables 10.1 to 10.109 provide listings of each plant's Automatic Scrars Fhile Critical, Safety System Actuations, Significant Events and Safety System Failures for the third and fourth quarters of 1987. Beginning with this report, event descriptions in the listings cre being provided for both the current and previous quarters.
For scrams above 15 percent power per 1000 critical hours, the results for plants with less than 1000 critical hours in a quarter can be distorted. For this report the degree of distortion has been reduced by using at least a minimum value of 200 critical hours in the calculations for any given quarter.
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The results for equipment forced outages per 1000 critical hours can be distor-ted in a similar manner. This distortion has also been reduced by using at least 200 critical hours in the calculations.
I Forced outage rates that are based on licensee monthly operating reports do not I always appear consistent for plants undergoing long shutdown periods, l There are two additional categories of information that are included in the program for collection, monitoring, and future development, but are not inclu- '
l ded in this report. They are causes associated with scrams, safety system actuations, significant .tvents, and safety system failures such as personnel Grror, maintenance problems, eouipment failures and design / fabrication /
construction error; and the number of forced outages.
in addition, the staff is developing indicators in several areas. The highest priority areas for development are maintenance and training. Other important areas include limitino conditions for operations (LCO) action state-ments, number of items out of service and causes of events as well as risk-based and programmatic indicators.
- 7. ANNUAL COLLECTIVE RADIATION EXPOSURE DATA Because the collective radiation exposure data are currently available only on an annual basis, the information displayed is for the annual data through 1986. Table 11.1 provides the annual cuwlative doses in person-rem for 1980 through 1986. Table 11.2 provides the 3-y0ar moving averages of the data in Table 11.1 for the 3-year periods ending with 1982, 1983, 1984, 1985, and 1986.
Data on a quarterly basis are in the process of being obtained.
- 8. COMPUTATIONAL NOTES
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_ The following computatiora. notes describe some of the detailed methods used in l calculations and displays for this report. In future reports, the details may change as improved techniques are obtained.
8.1 The report addresses plants licensed for operation in the fourth cuarter l of 1987 or earlier. The data extend through the fourth quarter of 1987.
8.2 Blanks are used under the following conditions for newer plants:
(1) For all indicators until an operating license is first received, (2) For scrams until critical hours are first reported, or (3) For forcec etages until power generation is first reported; thereaf ter, numerical values are used. For example, plants shut down for an entire quarter after initial criticality have zeroes for scrams rather than blanks.
8.3 Blanks are not used in calculating averages and standard deviations.
Zeroes do count in such calculations.
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.7-8.4 For the plant sumaries (Figures 4.1 - 4.109 of Part !),
(1) The top chart, "Trends," is baseo en the following numbers:
(a) The plant's moving average for the latest two quarters, {
(b) The plant's moving averace for the four quarters previous to thelatesttwocuarters(iftk ' are not at least two quarters i of data for this moving averim no value is displayed on the I chart),and (c) A standard deviation based on the plant's previous four quarters of data (if the standard deviation is zero, an average of values for older or newer plants, as appropriate, is used);
(2) The bottom chart, "Deviations from Older Plant Means" or "Deviations from Newer Plant Means," uses the following numbers:
(a) Moving average of the plant's latest four cuarters (if there are not at least two quarters for this, no value is displayed on the chart). -
(b) Average of the latest four-quarter moving averages for older plants or newer plants (outliers more than 2.5 standard deviations from the mean on the first calculation were discarded and the mean and standard deviation were recomputed), and (c) Standard deviation based on the latest four-quarter moving averages for older or newer plants (outliers were discarded as discussedabove);and (3) Moving averages (average of four cuarterly values) are used throughout rather than calculating true means (e.g., annual averages) for ratios such as equipment forced outages par 1000 critical hours.
8.5 The following parameters were used for detailed plant analysis charts of each plant's quarterly data (Figures 4.1 through 4.109 of Part I).
(1) Older plant averages are the averages of older plant values calculated quarter by quarter.
(2) Newer plant averages are single numbers that span all quarters, the average of all new plant values in the data set.
8.6 For certain plants in long-tem shutdown, such as Browns Ferry, Sequoyah, Pilgrim and Pancho Seco, Scram Forced Outage Rate, and Eouipment Forced Outages bars were suppressed in the plant summary charts.
- 9. REVISION OF DATA CONTAINED IN THE HOVEMBER 1987 REPOPT An intensive review of data sources and application of detailed screening criteria have ref.alted in scee changes to the data previously reported in
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1 November 1987. These changes are sunnarized in Tables 9.1 through 9.5. In aggregate, tney do not significantly alter the overall picture presented in the November 1987 report.
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e TABLE 11.1 COLLECTIVE RADIATION EXPOSURI ; --- YEARLY DATA UNIT 1980 1941 ~1982 1957 1984 1985
..................... ..... 1986 ....
ARKANSAS 1 171 551.'
ARKANSAS 2 402 693 403 155 571 171 351'i 402 699 SEAVER VALLEY 1 553 403 155 571 229 T12 BIG ROCK Po1NT 354 c599/ 504 N 827 RRAIDWOOD 1 160 < / 328 e
' 243 155 > 291 84 AROWNS FERRY 1 s ,
604 793 740 3111 ,
RROWNS FERRY 2 608 793 / 647 386 525 740 1131 647 386 525 BROWNS TERRY 3 608 793 740 I BRUNSWICK 1 M21 ,. 647< 386 525 1935 1319 1896 3 7.38 16*,0 BRUNSWICK 2 1935 1319 1402 955 BYRON 1 1896 1738 ISX 1402
' 955 BYRON 2 ' 104 CALLAWAY ^
CALVERT CLITTS 1 339 304 70 225 529 33i NC 347 '
CALVERT CLITTS 2 339 304 529 334 ,MC 174 CATAWBA 1 347 174 CATAWBA 2 '
,r 143 CLINTON 1 t
' g 143 COOK 1 247 328 COOK 2 350 329 '
381 >\ G73 247 328' 350 i
373 COOPER STATION 859 329 1 381 473 37;t 579 542 1*i93 799 CRYSTAL RIVER 3 625 408 177 3333 320 DAVIS-BESSE 154 b5? 49 689 472 58 164 80-DI Asw CANYQN 1 ~~'""""" 177 71 124 DIABI4 CANYON 2 m DRESDEN 2 702 ?34 i
DRESDEN 3 $74 1194 595 N3 702 934 974 1398 DUANI ARNOLD 1194 591 SO 1394 671 790 ;:29 1135 FARLEY 1 435 256 189 1%22 187 FARLEY 2 242 511 451 1276 256 142 429 '
FERMI 2 511 451i 1276 c29 FITZPATRICK 2040 1425 1190 FORT CAIJIOUN 1090 471 1M5 All FORT ST. YRAIN 668 458 217,
< ' i m .463 632 74 i i GINNA 708 /,
4E5 114C 855 GRAND GULF 394i' 426 357 .
MADQAM NECK 1353 1036 436 MATCM 1 126 . 13ti 1225 7M 225 669 730 1967 MATCH 2 e30 1109 44! 749 225 669 730 65L HOPE CREER 1109 J48 749 INDIAN FOINT 2 971 2731 1635 486 INDIAN POINT 3 308 2844 / 192 1250 364 1226 , 407 200 XEWAUNEE 165 141 .170 202 ZASALLE 1 101 165 139 / 176 169 LASALLE 2 25.4 343 475 252 ,143 475
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TABLE 11.2 COLLECTIVE RADIATION rxPOSURE (Three year moving averages ending in) .
NAME 1s42 1983 1984 1985 1986 ARKANSAS 1 375 551 501 419 376 ARKANSAS 2 ; 375 551 501 419 7,76 REAVER VALL1r:Y 1 ,440 533 425 445 397 BIG ROCK PCINT 0.51 250 249 236 177 BRAIDWOOD 1 f 4
' RROWNS FERRV 1 71,g 885 836 718 519 BROWNS FERRY 2 2 714 885 836 718 519 BROWNS .71 RAY 3 , ,714 885 836 718 519 BRUNSWICK 1 l'il 7 1651 1755 1590 1329 BRUNSWICK 2 1717 1651 1755 1590 1329 BYRON 1 EYRON 2 ' .
CAL 1AWAY '
CALVERT C?,ITTS 1 391 389 368 307 254 CALVERT CLITIS 2 391 389 368 307 254 l'.
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CATAWBA CATAWBA 2 '
CLINTON 1 '
COOK 1 308 336 353 394 409 COOK 2 308 336 353 394 409 COOPER STATION 660 805 878 1142 817 CKYSTAL RIVEJ: 3 403 379 259 430 403 3 AVIS-RESEE _
125 101 140 109 124 JIABLO CANYON 1 DIAB 14 CAkiCN 2 DRESDEN 2 870 1034 920 476 944
, DRESDEN 3 ,
470 1034 920 876 944 .
DUANE M NOLD 563 718 518 812 496 i FARLEY 1 311 336 401 746 719 FARLEY 2 249 336 401 746 719 FERMI 2 FIT 2 PATRICK 1552 1235 1084 1302 1076 FCPT CA1MOUN 448 369 404 543 423 F03rf ST. VRAIN GIN 3a 834 443 796 558 392 GRAND GULF
,R W At NECK 838 849 909 900 961
< flMTM 1 541 683 830 735 768
& LATCH 2 541 683 830 735 768 s
McFE CREEK INMAN POINT 2 1779 1617 1588 1107 1362 INDIAN POINT 3 CJ3 732 488 469 334 KEWAUNEE < 136 136 135 140 161 IASALLE.1 357 IASALLE .1 357 c 134 f
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Attachment 5
_m--mm e m..i
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TABLE 11.4 AUTOMATIC SCRAMS WHILE CRITICAL --
QUARTERLY DATA (The 11itest quarter data are preliminary)
NAME 86-1 86-2 86 3 86-4 87 1 87-2 87-3 87-4 AMANSAS 1 0 1 0 1 0 0 2 0 ARKANSAS 2 1 3 1 0 0 0 1 1 BEAVER VALLEY 1 1 0 1 0 2 2 0 0 BEAVER VALLEY 2 7 7 BIG 3OCK POINT 0 0 1 0 1 0 0 0 BRAIEMOOD 1 0 1 3 1 BROWNS PERRY 1 0 0 0 0 0 0 0 0 BROWNS FERRY 2 0 0 0 0 0 0 0 0 BROWNS FERRY 3 0 0 0 0 0 0 0 0 BRUNSWICK 1 1 2 2 1 0 1 1 0 83UNSWICK 2 0 1 1 0 2 0 0 0 BYRON 1 3 0 1 0 0 0 4 0 BYRON 2 4 2 1 2 CALIAWAY 0 4 2 0 0 0 0 1 CALVERT CLITTS 1 1 0 1 2 0 0 3 1 CALVERT CLITTS 2 1 1 1 0 1 0 2 1 CATAWBA 1 1 5 2 0 1 1 2 0 CATAWBA 2 1 1 2 3 0 2 0 CLINTON 1 0 1 5 1 COOK 1 0 1 3 1 0 1 0 1 COOK 2 1 0 1 0 0 2 2 1 COOPER STATION 1 0 1 0 4 1 0 0 CRYSTAL RIVER 3 1 0 0 0 0 0 2 0 DAVIS-BESSE 0 0 0 1 2 0 2 1 DIABI4 CANYON 1 1 0 1 1 3 1 0 1 DIABI4 CANYON 2 4 2 4 0 2 1 1 0
. DRESDEN 2 1 0 3 0 0 1 2 1 DRESDEN 3 0 0 1 4 1 1 2 0 DUANE ARNOIb 0 0 0 1 0 0 0 0 FARI2Y 1 1 1 2 0 2 1 0 0 FARLEY 2 1 2 1 0 1 0 0 1 FERMI 2 0 0 1 1 2 2 2 1 FITZPATRICK 0 1 1 0 0 1 3 2 FORT CAIJiOUN 0 0 1 0 0 0 0 0 FORT ST. VRAIN 0 1 0 0 0 1 0 1 GINNA 0 0 1 2 0 0 0 0 GRAND GULF 3 0 2 0 0 1 1 0 HADDAM NECK 0 3 0 1 0 1 0 0 HATCH 1 0 2 1 3 2 0 2 0 MATCH 2 1 3 3 0 1 1 2 0 HOPE CREZK 1 6 2 1 0 3 1 INDIAN POINT 2 1 2 2 2 1 1 0 0 143
.. Attacha2nt 5 MMM% $l 0O% 4 TABLE 11.7 SAFETY SYSTEM ACWATIONS --
QUARTERLY DATA (The latest quarter data are preliminary)
NAMI 46-1 46-2 86-3 86-4 87-1 87-2 87-3 87-4 ARKANSAS 1 0 0 0 0 0 0 1 0 ARKANSAS 2 0 0 0 0 0 0 0 0 BEAVER VALLEY 1 0 1 1 0 0 0 0 0 BEAVER VALLEY 2 0 3 2 BIG ROCK POINT 0 0 0 0 0 0 0 0 BRAIDWOOD 1 0 0 0 2 0 BROWNS TERRY 1 1 0 0 0 1 0 0 0 BROWNS FERRY 2 0 0 0 0 0 3 0 0 BROWNS FERRY 3 0 0 0 0 0 0 0 1 BRUNSWICK 1 1 1 3 0 1 1 2 0 BRUNSWICK 2 1 1 1 2 2 0 0 0 BYRON 1 0 0 0 0 1 0 1 0 BYRON 2 0 0 0 1 2 CALI.AWAY 0 0 0 ,0 0 0 0 2 CALVERT CLIFFS 1 0 0 0 0 0 0 1 0 CALVERT CLIF?S 2 1 0 0 0 0 0 1 0 CATAWBA 1 0 0 0 2 0 0 0 1 CATAWBA 2 0 1 1 0 0 0 0 0 CLINTON 1 0 1 2 2 1 1 C00K 1 0 0 0 0 0 0 0 0 C00K 2 1 0 0 0 0 0 1 1 C00PER STATION 1 0 0 0 2 0 2 0 CRYSTAL RIVER 3 0 1 0 0 0 0 0 6 DAVIS-BESSE 2 1 1 0 0 0 1 0 DIABI4 CANYON 1 2 0 1 0 1 0 1 0 -
DIABI4 CANYON 2 1 3 3 1 1 1 2 0 DRESDEN 2 1 1 0 0 0 0 0 0 DRESDEN 3 0 2 1 0 0 0 0 0 DUANE ARN0LD 0 0 0 0 0 2 0 0 FARLEY 1 0 0 0 0 0 0 0 0 FARI2Y 2 0 0 0 0 0 0 0 2 FERMI 2 0 1 1 2 0 1 0 0 FITIPATRICK 0 0 0 0 0 1 1 0 FORT CAIJIOUN 0 0 0 0 1 0 0 0 FJRT ST. VRAIN 0 O O O 1 0 0 2 OINNA 0 0 0 0 0 0 0 0 GRAND GULF 0 0 0 1 0 1 1 1 HADOAM NECK 0 0 0 0 0 0 0 0 NATCE 1 2 1 0 0 0 0 2 0 MATG 2 1 0 1 1 1 1 2 0 HOPE CREEK 11 10 3 1 0 5 0 INDIAN POINT 2 1 2 2 0 1 0 0 4 152
Attactment 5 mmmmm^ p @ t_ t A. t )
aw
- ABLE 11.8 j
l I SIGNIFICANT EVENT FREQUENci .-
QUARTERLY DATA (The latest quarter data are preliminMY) i NAME 86-1 86-2 46 3 86-4 87 1 87-2 87 87 4 ARKANSAS 1 1
.............3 .......
1 0 1 0 0 1 0 ARKAsSAS 2 0 I 1 1 0 0 1 0 0 BEAVER VALI2Y 1 0 0 0 0 0 0 0
)
0 )
BEAVER '/ ALLEY 2 0 1 1 BIG ROCK POINT 0 0 0 0 0 0 0 0 BRAIDWOOD 1 0 1 0 0 0 BROWNS FERRY 1 0 1 0 0 0 0 0
' 0 l BROWNS FERRY 2 0 1 0 0 0 0 0 1 )
BROWNS FERRY 3 0 1 0 0 0 0 0 0 1 BRUNSWICK 1 i 1 1 0 0 0 1 0 BRUNSWICK 2 0 0 0 1 0 0 0 BYRON 1 s 0 1 0 0 2 0 0 BYRON 2 0 0 0 0 1 CALI.AWAY 0 0 0 0 0 0 1 0 CALVERT CLITTS 1 0 0 1' O 1 2 1 0 CALVERT CLITTS 2 0 0 1 0 1 2 1 0 l CATAWBA 1 0 2 1 0 0 0 0 0 CATAWBA 2 0 2 0 0 0 1 0 0 CLINTON 1 0 1 0 0 0 0
COOK 1 0 0 0 0 1 0 0 0 COOK 2 0 0 1 0 0 0 0 0 COOPER STATION 0 1 0 0 0 0 0 0 CRYSTAL RIVER 3 1 0 0 0 0 0 0 1 DAVIS-BESS E O O 0 0 1 0 1 0 DIABLO CANYON 1 1 Q Q U 1 v 9 v DIABIA CANYON 2 2 0 2 0 0 1 0 0 DRESDEN 2 0 1 0 0 0 0 0 0 DRE.SDEN 3 1 1 0 0 0 0 1 0 DUANE ARNOLD 0 0 0 0 0 0 0 0 FARIJrY 1 0 0 1 0 0 0 0 i
0 l FARI2Y 2 0 0 0 0 0 0 0 2 FERMI 2 1 0 0 0 0 1 1 0 FIT 2 PATRICK 0 0 0 0 0 0 0 0 FORT CAIROUN 0 0 0 0 1 0 1 0 FORT ST. VRAIN 0 2 0 0 0 0 0 1 GINMA 0 0 0 0 0 0 0 0 GRAND GULF 1 0 1 0 0 0 0 0 NADDAM NECK 2 0 0 0 0 0 0 0 HA'N R 1 0 1 0 1 0 0 0 0 NATC5 2 1 0 0 1 0 0 0 0 HOPE CREEK 0 2 0 0 0 0 1 INDIAN POINT 2 0 2 2 2 3 0 0 0 155
Attachment 5 1
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TABLE 11.9 o
SAFETY SiSTEN FAIL #RES --
QUARTERLY DATA (The latest quarter data are prelisinary)
NAME 86-1 86-2 86-3 86-4 87-1 87-2 87-3 87-4 ARKAJESAS 1 1 0 0 0 0 0 0 0 AlbtABSAS 2 1 1 0 0 0 0 0 0 BEAVER VALLEY 1 0 0 0 0 1 0 0 0 BEAVER VALLEY 2 0 2 0 BIG BDCK POINT 0 0 0 0 1 0 0 0 BRAIDWOOD 1 2 3 0 1 1 BROWPS FERRY 1 0 0 0 0 1 1 1 0 BROWNS FERRY 2 0 0 0 0 2 0 3 0 BROWNS FERRY 3 0 0 0 0 2 1 1 0 BRUNSWICK 1 0 0 1 1 3 2 2 2 BRUNSWICK 2 2 0 0 0 6 2 0 1 GYRON 1 0 0 0 0 0 5 1 0 DYRON 2 0 1 2 0 0 CALIAWAY 0 1 0 0 0 1 3 2 CALVERT CLIFFS 1 1 0 0 O 3 0 0 0 CALVERT CLIFFS 2 0 0 0 0 0 1 0 0 CATAWBA 1 1 0 1 0 2 1 0 1 CATAWBA 2 0 0 0 0 1 1 0 1 CLINTON 1 1 0 0 1 3 3 COOK 1 1 1 0 0 0 0 2 0 COOK 2 1 1 0 0 0 1 0 0 COOPER STATION 2 1 0 1 1 0 1 0 CRYSTAL RIVER 3 1 0 0 0 1 0 2 1 DAVIS-BESSE 1 0 2 2 0 0 0 1 DIAZID CANYON 1 0 0 1 0 0 1 0 1 . l DIABI4 CANYON 2 1 0 0 0 1 3 0 1 1 DRESDEN 2 0 0 0 0 0 2 1 2 1 DRESDEN 3 0 0 1 0 2 0 7 0 DUANI ARNOLD 2 2 1 3 1 2 1 1 FARI2Y 1 0 0 0 0 1 0 0 1 FARI2Y 2 1 0 0 0 0 0 0 0 FERNI 2 0 1 0 1 3 4 4 1 i FITEPATRICK 2 2 2 2 1 0 3 0 1 FORT CALHOUN 0 0 0 0 1 3 0 0 FORT ST. VRAIN 0 0 1 1 2 0 0 0 l OINNA 0 0 0 0 3 0 0 0 CRAND GULF 0 3 0 1 1 0 0 0 HADDAM NECK 2 2 1 0 0 0 1 0 NATCE 1 0 1 1 1 0 3 2 1 NATCE 2 0 0 3 2 0 2 3 2 H2PE CREEK 1 1 3 1 2 2 0 INDIAN POINT 2 C 0 0 0 3 3 0 0 158
.- Attachment 5 m m-m-me,% 4
. 4 rm _-_m .-
TABLE 11.10 FORCED OUTAGE RATE (4) --
QUARTERLY DATA (The latest quarter data are preliminary)
NAME 86-1 86 2 86 3 86 87-1 87-2 87-3 47-4 ARJUJISAS 1
....4 ....- ....................
20 1 0 79 11 0 4 ARKANSAS 2 1 2 3 18 5 0 36 BEAVER VALLEY 1 12 1 2 0 23 1 2 3 0 0 BEAVER VALLEY 2 BIG BOCK POINT 29 27 6 0 12 0 0 4 6 9 BRAftNDOOD 1 BROWNS FERRY 1 56 11 0 100 100 100 100 100 BROWMS FERAY 2 0 100 100 '00 100 100 100 100 100 100 BROWNS TERRY 3 0 100 100 100 100 BRUNSWICK 1 100 100 100 7 8 13 4 0 33 4 0 BRUNSWICK 2 0 54 2 3 16 BYRost 1 4 0 0 6 0 24 2 0 0 BYROft 2 5 0 5 7 21 4 CALIAWAY 0 19 5 0 1 3 0 5 CALVERT CLITTS 1 2 1 2 6 13 62 16 11 CALVERT CLIFFS 2 2 2 12 0 1 0 CATAWBA 1 1 6 8 30 33 2 18 1 9 90 CATAWBA 2 86 45 54 15 14 33 6 CLINTON 1 i COOK 1 37 18 2 0 37 20 1 0 COOK 2 17 0 1 10 0 3 0 0 2 l
COOPER STATION 23 11 2 0 2 0 5 1
11 0 0 CRYSTAL RIVER 3 99 89 0 40 24 1
0 7 0 DAVIS-BESSE 1CO 100 100 92 9 !
0 14 2 DIABID CANYON 1 J Q 4 0 lo l
J U 7 DIAB 14 CANYON 2 14 5 5 0 15 DRESDEN 2 90 0 7 14 34 8 0 0 6 DRESDEN 3 18 3 0 0 25 13 6 16 DUANE AANOIb 39 0 0 6 0 10 0 98 l FARI2f 1 0 98 2 1 3 0 3 i
FARIEY 2 1 0 11 l 2 2 6 0 17 FERMI 2 0 0 67 98 91 36 66 76 12 FIT 2 PATRICK 0 5 2 2 0 2 11 3 FORT CAIJIOUN 0 0 5 0 0 0 0 0 FORT ST. VRAIN 100 50 100 100 100 24 GINNA 73 49 I 0 0 2 1 0 0 C*'.AND GULF 0 0 15 5 13 0 0 1 HADDAM NECK 6 0 i 0 12 26 15 1 2 HATM 1 0 9 0 12 1 1 3 5 MATG 2 3 0 5 5 8 9 1 2 6 0 HOPE CREEK 63 29 9 0 7 22 INDIAN POINT 2 4 35 3 12 3 3 0 0 161 .
4 Attachment 5
' n-,-n.,.,~ .
TABLE 11.11 EQUIPMENT FORCED OUTAGES /1000 CRITICAL MRS --
QUARTERLY DATA (The latest quarter data are preliminary)
NAME 86-1 86-2 86-3 86-4 87 1 87-2 87 3 87 4 ARKANSAS 1 0.58 0.46 0.00 0.00 2.07 0.00 0.92 0.64 ARKANSAS 2 0.47 1.15 2.36 0.48 0.00 0.71 1.02 0.46 BEAVER */ ALLEY 1 0.47 0.00 0.00 0.46 0.47 1.56 0.00 0.00 BEAVER VALLEY 2 13.27 4.67 BIG itOC'K POINT 0.49 0.00 1.02 0.00 3.45 0.C3 2.13 1.56 BRAIDWOOD 1 1.89 1.00 BROWMS FERRY 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 BROWNS FERRY 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 BROWNS FET.RY 3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 BRUNSWIC% 1 0.49 0.47 1.00 0.92 0.94 2.56 0.47 0.00 BRUNSWICK 2 0.00 3.46 0.48 0.54 2.78 0.47 0.00 0.00 BYRON 1 0.56 0.00 0.59 0.46 0.00 0.00 0.47 0.00 BYRON 2 0.00 2.51 2.72 1.29 CALIAWAY 0.00 2.58 1.87 0.00 1.40 0.81 0.00 0.89 '
CALVERT CLITTS 1 0.50 0.46 0.46 0.00 0.52 0.00 1.07 0.50 CALVERT CLITTS 2 0.47 0.93 2.03 0.00 1.15 0.00 0.94 1.44 CATAWBA 1 1.97 3.11 4.26 1.85 4.41 0.47 1.48 8.77 CATAWBA 2 4.79 0.83 2.85 11.99 1.55 3.30 0.52 CLINTVN 1 1.11 1.61 ') . 8 5 '
COOK 1 0.00 0.73 '. 63 0.46 0.00 2.29 0.00 0.48 I
COOK 2 0.74 0.00 0.50 0.00 0.00 0.60 2.59 0.00 COOPER STATION 0.00 0.00 0.00 0.00 0.50 0.00 0.00 0.00 j CRYSTAL RIVER 3 42.37 0.00 0.00 1.68 1.21 0.00 1.34 0.00 DAVIS-BESSE 0.00 0.00 0.00 16.85 0.99 1.54 0.52 0.46 DI.Asw wuxun A o.4/ v.99 v.co 9.vu v.ww v.ve v.vu v . U" .
DIABLO CANYON 2 3.54 0.94 0.94 0.00 1.46 0.00 0.00 0,49 DRESDEN 2 0.97 0.00 1.43 0.00 0.00 0.61 1.22 0.00 DRESDEN 3 0.00 0.09 3.95 0.50 1.69 0.97 2.07 0.00 DUANE ARNOLD 0.00 0.00 0.00 1.80 0.00 0.00 0.00 0.55 FARLEY A 0.47 0.46 1.39 0.00 1.40 0.00 0.00 0.00 FARIEY 2 0.47 0.00 0.95 0.00 1.11 0.00 0.00 2.91 FERMI 2 3.45 4.86 1.49 2.57 1.54 0.00 FITZPATRICK 0.00 0.00 0.47 0.50 0.00 0.61 1.47 0.47 FORT CAIfoUN 0.00 0.00 0.94 0.00 0.00 0.00 0.00 0.00 FORT ST. VRAIN 0.00 0.00 0.00 0.00 0.00 0.58 2.44 4.04 GINNA 0.00 0.00 0.72 0.00 0.00 0.00 0.00 0.00 GRAND GULF 0.S2 0.00 0.00 0.00 0.00 0.46 0.00 0.00 MADDAN NECK 0.00 1.54 2.J8 0.00 0.46 0.47 0.00 0.00 HATCH 1 0.00 2.29 0.47 0.48 0.47 0.00 0.92 0.00 MATCR 2 0.48 0.98 2.29 1.74 0.00 0.46 1.00 0.00 HOPE CREEK 2.62 0.00 0.50 0.00 1.12 2.49 INDIAN POINT 2 0.00 4.67 0.46 2.04 0.00 0.47 0.00 0.00 164
.- Attactrent 5 N [C[ClE!CI 4 TABLE 11.12 CR.ITICAL HOURS --
(The latest quarter data are preliminary) QUARTERLY DATA NAME 86-1 86-2 86-4 87 1 87-2 87-3 27-4 ARKANSAS 1 1728 2173 46-3..................................
1564 ARKANSAS 2 72 1935 214J 2177 2116 1738 423 2093 1561 l BEAVER VALLEY 1 2160 1413 1956 2186 2117 1104 842 2182 2124 l BEAVER VALLEY 2 1278 2208 1727 i BIG ROCK POINT 2032 2183 603 1714 !
1963 2209 579 1597 2117 BRA.IDIPOOD 1 1921 BROWNS FERRY 1 0 369 1060 2000 0 0 0 0 BROWNS FERRY 2 0 0 0 0 0 0 0 0 BROWNS FERRY 3 0 0 0 0 1
0 0 0 0 BRUNSWICK 1 0 0 0 2028 2122 2004 2163 1064 BRUNSWICK 2 0 391 2125 2209 289 2093 1851 18C1 BYRON 1 1778 2110 2208 2209 2183 1691 2169 1058 BYRON 2 815 2128 2209 CALIAWAY 1723 1592 1468 1549 1416 1548 2135 2209 2138 CALVERT CLITTS 1 1993 1240 1724 1126 2183 2170' 559 1909 857 CALVERT CLIFFS 2 2119 2142 1866 1983 1973 2205 1733 0 CATAWBA 1 2031 1610 2121 2085 704 1080 1816 2116 2029 CATAWBA 2 418 1209 114 CLINTON 1 1052 1836 1941 1515 1623 COCK 1 509 1799 1869 1173 2160 1367 1822 2187 COOK 2 2160 1749 0 2092 1353 0 1999 2209 COOPER STATION 1479 1679 1158 1966 2132 2183 2177 78 CRYSTAL RIVER 3 24 2009 1998 2208 2209 266 2208 1193 1657
. DAVIS-BECSE _ 0 2183 1494 0 0 0 178 2016 "OIAnw GAnIvN 1 21zy 1301 1933 2176' z 1ti J 1943 227 2013 DIABI4 CANYCH 2 447 21J4 JJU5 2121 2119 2121 2209 2061 72 DRESDEN 2 2067 1512 2208 2058 2097 1434 0 1649 1637 DRESDEN 3 0 0 760 2183 DUANE ARNOLD 2006 1778 2067 1449 2209 1767 1903 2016 1662 FARIEY 1 1894 83 2069 1822 2126 2168 2166 816 2136 FARLEY 2 2130 1957 2208 2007 1110 2100 2209 1803 2183 FERMI 2 0 0 580 2208 344 FIT 1 PATRICK 823 1345 1168 449 1986 1832 2105 2124 2015 356 FORT CALHOUN 1945 1645 2041 2148 2183 2129 2209 1571 421 FORT ST. VRAIN 1091 1366 2208 2209 0 0 0 1710 GIMMA 1170 2183 763 495 2176 2188 1415 2183 2208 i
GRAND GULF 1923 2097 1437 2209 '
MADOAM NECK 167 2026 2157 2119 891 87 1297 1679 1998 MATS 1 2160 2149 420 0 '
0 1311 2132 2078 HATG 2 2136 678 2169 2209 2091 2036 1750 574 2141 HOPE CREEK 2165 2005 2209 32 1144 1494 1989 INDIAN POINT 2 321 2183 1788 1609 643 2174 1964 1924 2119 2204 96 i
167
._ . _ _ _ - - -