ML20141C866

Nonproprietary Special Study Fire Events - Feedback of Us Operating Experience

ML20141C866
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Issue date:	06/30/1997
From:	Houghton J NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
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SPECIAL STUDY l

FIRE EVENTS - FEEDBACK OF U.S. OPERATING EXPERIENCE JUNE 1997 i

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l Prepared By:

l James R. Houghton i

I Rellability and Risk Assessment Hranch Safety Programs Division Office for Analysis and Evaluation of Operational Data U. S. Nuclear Regulatory Commission 9706260056 970619 PDR ORG NEXD

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W EXECUTIVE

SUMMARY

e This report (special study), on fire events covering operating experience from 1965 through 1994, characterizes the frequency and nature of fire event data from U.S. operating plants and examines the potential impact this updated data s

could have on fire risk assessments.

This report upd'ates the Sandia fire events database (1965 through mid-1985) with fire event data from Ucensee Event Reports (LERs), the proprietary EPRI l

l fire events database (1965-1988), and fire-related component failure histories i

l from the Nuclear Plant Reliability Data System (NPRDS) database (also l

proprietary).. Appendix A - Tables I and ll, "Overall Fire Events Data," contain proprietary fire event data from the EPRI fire events database (coded in the j

tables as "+ +"). The consolidated fire events database and other appendices

}

developed for this study provide a comprehensive and up-to-date compilation of j

information on fire events, their calculated frequencies, and severity as they have affected U.S. nuclear power plants.

The study reviewed and compared plant location fire frequencies with those j

i used in selected probabilistic risk assessments (PRAs), including the Control i

Room, the Cable Spreading Room, the Auxiliary Building (Pressurized Water j

Reactor plants only), the Reactor Building (Boiling Water Reactor plants only),

the Switchgear Room, and the Turbine Building.

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With the combined and updated data for 1965-1994, the following analyses i

were performed:

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Usting of fire events data, as input to an updated fire events database.

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Apportionment of fire events by number, major cause, and plant location.

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Evaluation of the duration and frequency of fire events that occurred during power and shutdown operations.

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Grouping of fire events by severity during power operations.

Comparison of calculated fire frequencies with PRA data and recent e

2 industry and NRC sponsored studies for the potential effect on fire j

induced core damage frequency estimates.

Comparison of the duration and fire frequency of shutdown fire events with power operations fire events.

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[4._ _.. _ __ _

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1 Listing of smoke events, including attributes similar to fire events data, as

.4 input to a smoke events database.

This report identified the following major findings and conclusions:

A compa,ison of fire events in the pre-Appendix R period (1965-1985) with fire 4

F events in the' subsequent period shows that event frequencies have declined slightly, while the. safety significance of events has also been lower. This finding l

is shown graphically in figures ES-1 and ES-2. The most significant fire event occurred at Browns Ferry in March,1975 and was a pivotal incident in the recognition of fire. safety concerns. It resulted in a scram and propagated without suppression to affect multiple redundant trains of safety equipment.

Since the implementation of Appendix R modifications and other industry i

[

activities (1986-1994), there were no fire events with similar safety significance.

There were only two fire events resulting in a scram and loss of one safety l

l related train or loss of offsite power (LOOP) during this period compared to 10 events previously. Other fires have been severe in terms of the magnitude and l-duration of combustion (such as some turbine building fires), but their severity in terms of challenges to safety systems operation has been limited. However, j

i such fires could be important if redundant safety trains or decay heat removal systems were dependant on equipment located there.

The fire durations during power operations were generally short (less than 10 l

minutes). The information available on these short duration fires was not sufficient to evaluate probability of fire detection and suppression used in recent l

PRAs.

l The fire durations during shutdown were also generally short (less than 10 minutes). Shutdown durations in plant locations that contain systems necessary for decay heat removal during shutdown, were the same or lower than fire durations for the same plant locations during power operations.

i The 1986-1994 (post-Appendix R implementation) fire event frequencies at l

power-operations were lower for the Control Room and the Cable Spreading i

Room, approximately the same for the Auxiliary Building (PWR) and the Reactor Building (BWR), and higher for the Switchgear Room and Turbine Building than j.

those values used in most PRAs reviewed for this study. A sensitivity study, i

based solely on changes to the initiator frequencies, did not indicate the

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potential for substantial changes to the overall CDF due to fires. Other aspects

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of fire analyses may be more critical to their risk assessment, including: the i

mechanics of combustion, combustible loading, and means of detection and suppression. The data in this report was not suitable for addressing these j

issues.

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For the 1986-1994 period, the shutdown fire frequencies varied in comparison to the fire frequencies at power for most risk significant plant locations used in PRAs. Since some plant locations were higher (Containment, Reactor Building, Auxiliary Building, Switchgear Room, and Diesel Generator Building), a more

' detailed review of shutdown fire events resulted in the following conclusions:

Containment fires were predominantly caused by welding operations and did not affect decay heat removal.

There were a limited number of fire events that affected the functional operability of Residual Heat Removal (RHR), Decay Heat Removal (DHR),

and Emergency Diesel Generator (EDG) system trains. The number of fire events and fire frequencies and corresponding plant locations are as follows:

Shutdown No. System Plant Shutdown Shutdowr* Mean Location System Fire Events Reactor Vepfrjj!

Fire Frecuenev*

Reactor Bldg RHR 2

90.4 2.7x10' Auxiliary 8tdg RHR &

DHR 2

139.8 1.8x10' Switchgear Room RHR 1

230.2 6.5x10' Diesel Generator-Building EDG 7

230.2 3.2x10'

• Indicates Sayes method mean, with noninformative prior.

Therefore, the operating experience indicates that the frequency and duration of shutdown fire events appears to be similar or less signifi6aint than for fire events occurring at power operation. This finding is somewhat tentative considering the limitation ir *eatment of fires in currently available shutdown risk essessments.

Although archival data is retrievable from the NPRDS database, no new nuclear plant failure history data is available through the NPRDS database after 12/31/96. It is not clear whether there will be an industry initiative to replace it with another data source that would be useful in compiling fire event and smoke event data.

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OVERALL FIRE FREQUENCIES TOTAL PLANT Overall Fire Frequency a E 1 7-65 85 AVE.

P 6 r -(3.8E 1) i I

f COMBINED 65 94 S'

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FIGURE ES-1 2

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Operating Years l

SAFETY SIGNIFICANCE GROUPING POWER OPERATIONS FIRE EVENTS - 1965 1994 NO. FIRE EVENTS 140[OTHER-l s

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FIGURE ES-2 OF SAFETY TRAIN j

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SCRAM AND LOSS j

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SCRAM AND LO ES

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Cat E Cat D Cat C Cat B Cat A i

C 19651985 Z 1986-1994 Post Appenden R wnplementerson 1986-1994 Mt. Oper Yrs.1965-1985: 850 Plc. Oper. Yes. 1986 1994.816 iV

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CONTENTS 1.

I NTR O D U CTIO N........................................... 1 1.1 Purpose of Study.

.. 1 1.2 Background...

.1 2.

S C O P E O F STU DY......................................... 1 2.1 Data S ou rces......................................... 3 2.2 Description of Terms and Assumptions Used in Study........... 4 3.

APPROACH AND METHODOLOGY............................. 6 3.1 Updating the Sandia Fire Event Data Base..

.......... 6

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3.2 Reconciling the EPRI Database for Fire Events Used in This Study... 6

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3.3 Apportionment of Overall Fire Events By Cause and Location..... 7 3.4 Overall Fire Frequencies......

.7 3.5 Power Operations Fire Events and Duration By Plant Location...... 8 3.6 Plant Average Unit Availability Factors and Power Operations Fire Frequencies

.................................8 3.7 Fire Severity and Risk Implications.

................. 8 3.8 Shutdown Fire Events

.................................11 3.9 Overall Smoke Events 11 4.

RESULTS...............................................

12 4.1 Update of the Sandia Fire Event Data Base - Overall, Power Operations, and Shutdown Fire Events....

.................12 4.2 Apportionment of Overall Fire Events By Cause and Location.....

14 4.3 Overall Fire Frequencies...............................

14 4.4 Duration of Power Operations Fire Events By Plant Location......

18 4.5 Power Operations Fire Frequencies.............

19 4.6 Fire Severity and Risk Implications....

.... 20 4.7 Shutdown Fire Events

...... 23 4.8 Smoke Events...................

...............25 5.

CONC LU SION S.......................................... 26 6.

REFERENCES........................................... 29 APPENDICES v

APPENDICES Descriotion APPENDIX A Overall Fire Events Data APPENDIX B Overall Fire Event Apportionment By Cause and Location APPENDIX C Overall Fire Frequencies APPENDIX D Power Operations Fire Events Average Durations By Plant Location and Comparison of 1965-1985 Durations with 1986-1994 Durations APPENDIX E Plant Average Unit Availability Factors and Power Operations Fire Frequencies APPENDIX F Risk insights - Severity Grouping of Power Operations Fire Events and Comparison of Power Operations Fire Frequencies with Selected Plant PRA Data By Plant Location APPENDIX G Shutdown Fire Events - Average Duration By Plant Location and Comparison with Power Operations Fire Events Duration APPENDIX H Shutdown Fire Events - Shutdown Average Fire Frequency By Location and Comparison with Power Operations Average Fire Frequencies APPENDIX J Overall Smoke Events Data I

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g FIGURES Flaure No.

Description Page 1

Number of Overall, Power Operations, and Shutdown Fire Events

- Total Plant (3 bar charts).

A-2 2

Overall Fire Event Apportionment By Cause [1365-1985, 1986-1994, and 10656-1994 - 3 pie charts]

. B-2 3

Overall Fi'e Events Apportionment By Location " Electrical Failure" [1365-1985,1986-1994, and 1965-1994 - 3 pie charts]

.. B-4 4

Overall Fire Events Apportionment By Location " Overheated Material (1965-1985,1986-1994, and 1965-1994 - 3 pie charts].... B-5 5

Overall Fire Events Apportionment By Location " Explosion"

[1965-1985,1986-1994, and 1965-1994 - 3 pie charts]...

.. B-6 6

Overall Fire Events Apportionment By Location " Welding Sparks"

[1965-1985,1986-1994, and 1965-1994 - 3 pie charts)

.. B-7 7

Overall Fire Events Apportionment By Location [1965-1985, 1986-1994, and 1965-1994 - 3 pie charts]

.. B-8 8

Overall Fire Frequencies - Total Plant...

...........C-2 9

Overall Fire Frequencies - Containment, Reactor Building, Auxiliary Building, and Turbine Building [4 bar charts].......... C-3 10 Overall Fire Frequencies - Control Room, Cable Spreading Room, Diesel Generator Building, and Switchgear Room [4 bar charts].... C-4 11 Overall Fire Frequencies - Service Water Pumphouse, Switch Yard, Battery Room, and Other Buildings [4 bar charts)......... C-5 12 Overall Fire Frequencies - Offsite and Temporary Buildings

[2 bar charts]

... C-6 13 Power Operations Fire Events Duration - 1965-1985 - Containment Building, Reactor Building, Auxiliary Building, and Turbine Building [4 bar charts].....

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FIGURES (CONTINUED)

Floure No.

Description Page 14 Power Operations Fire Events Duration - 1965-1985 - Control Room, Cable Spreading Room, Switchgear P.oom, and Diesel Generator Building [4 bar charts]

......... D-3 15 Power Operations Fire Events Duration - 1965-1985 - Battery Room, Other Buildings, Service Water Pumphouse, and Switch Yard [4 bar charts]

.... D-4 16 Power Operatior.s Fire Events Duration - 1986-1994 - Containment Building, Reactor Building, Auxiliary Buildin0, and Turbine Building [4 bar charts]................................. D-8 17 Power Operations Fire Events Duration - 1986-1994 - Control Room, Cable Spreading Room, Switchgear Room, and Diesel Generator Building [4 bar charts]

... D-9 18 Power Operations Fire Events Duration - 1986-1994 - Battery Room, Other Buildings, Service Water Pumphouse, and Switch Yard [4 bar charts]

............... D-10 19 Power Operations Fire Frequencies - 1965-1985 and 1986-1994

- Containment, Reactor Building, Auxiliary Building, and Turbine Building [4 bar charts]

.........................E-2 20 Power Operations Fire Frequencies - 1965-1985 and 1986-1994

- Control Room, Cable Spreading Room, Switchgear Room, and Diesel Generator Building [4 bar charts]

.. E-3 21 Power Operations Fire Frequencies - 1965-1985 and 1986-1994

- Service Water Pumphouse, Switch Yard, Battery Room, and Other Buildings [4 bar charts]........................... E-4 22 Risk insights - Severity Grouping of Power Operations Fire Events

[1965-1985,1986-1994, and 1965-1994 - 3 pie charts)......... F-2 23 Power Operations Fire Frequencies Comparison With Selected Plants

[ Control Room and Cable Spreading Room - 2 high/ low charts)... F-5 viii

FIGURES (CONTINUED)

Floure No.

Description Paae 24 Power Operations Fire Frequencies Comparison With Selected Plants (Switchgear Room and Reactor Building (BWR) - 2 high/ low charts]

F-6 25 Power Operations Fire Frequencies Comparison With Selected Plants

[ Auxiliary Building and Turbine Building - 2 high/ low charts]..... F-7 26 Shutdown Fire Events Duration - 1965-1985 (Containment, Reactor Building, Auxiliary Building, and Turbine Building -

4 bar charts]

.. G-2 27 Shutdown Fire Events Duration - 1965-1985 [ Control Room, Cable Spreading Room, Switchgear Room, and Diesel Generator Building -

4 b a r charts).......................................

G-3 28 Shutdown Fire Events Duration - 1965-1985 [ Service Water Pumphouse, Switch Yard, Battery Room, and Other Buildings

- 4 bar charts]....................................... G-4 29 Shutdown Fire Events Duration - 1986-1994 [ Containment, Reactor Building, Auxiliary Building, and Turbine Building - 4 bar charts]

. G-8 30 Shutdown Fire Events Duration - 1986-1994 (Control Room, Cable Spreading Room, Switchgear Room, and Diesel Generator Building

- 4 bar charts]...................................... G -9 31 Shutdown Fire Events Duration - 1986-1994 (Service Water Pumphouse, Switch Yard, Battery Room, and Other Buildings - 4 bar charts)..................

G-10 32 Smoke Events Density [1965-1985,1986-1994, and combined period 1965-1994 - 3 pie charts]..............

...... J-1 33 Smoke Events Causes (1965-1985,1986-1994, and combined period 1965-1994 - 3 pie ch arts]............................... J-2 34 Smoke Events Location [1965-1985,1986-1994, and combined period 1965-1994 - 3 pie charts).....................

.. J-3 l

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TABLES Table No.

Description Page Appendix A-Table i Overall Fire Events Data - 01/01/65-12/31/85

. A-3 Appendix A-Table ll Overall Fire Events Data - 01/01/86-12/31/94 A-27 Appendix B-Table l Overall Fire Event Apportionment By Cause

- Total Plant.............................. B -3 Appendix B-Table II Overall Fire Events Location Apportionment By Causes - Period: 1965-1985................... B-9 Appendix B-Table lli Overall Fire Events Location Apportionment By Cauces - Period: 1986-1994.................. B-10 Appendix B-Tab le IV Overall Fire Events Location Apportionment By Causes - Combined Period: 1965-1994.......... B-11 Appendix C-Table l Plant Operating Years - 01/01/65-12/31/94........ C-7 Appendix C-Table ll Overall Fire Frequency By Total Plant And Plant Location - 1965-1985...

....................C-8 Appendix C-Table ill Overall Fire Frequency By Total Plant And Plant Location - 1986-1994....................... C-1 2 Appendix D-Table i Power Operations Fire Events Duration By Plant Location - 1965-1985

........................D-5 Appendix D-Table ll Power Operations Fire Events Duration By Plant Location - 1986-1994....................... D-1 1 Appendix D-Table lli Comparison of Average Power Operations Fire Events Mean Duration By Plant Location - 1986-1994 With 1965-1985.....

................ D-14 Appendix E-Table i Plant Average Unit Availability Factor - 1965-1985.... E-5 AppendN E-Table il Plant Average Unit Availability Factor - 1986-1994... E-5 x

e TABLES (CONTINUED)

Table No.

DescrictlOD Page Appendix E-Table ill Power Operations Fire Frequency By Total Plant and Plant Location - 1965-1985.................... E-6 Appendix E-Table IV Power Operations Extrapolated Fire Events By Total Plant and Plant Location - 1986-1994.

........ E-10 Appendix E-Table V Power Operations Fire Frequency By Total Plant and Plant Location - 1986-1994 E-11 Appendix E-Table VI Power Operations Fire Frequency By Plant Location -

Bayes 90% intervals........................ E-13 Appendix F-Table i Risk insights - Severity Grouping of Power Operations Fire Events - 1965-1985

......................F-3 Appendix F-Table ll Risk insights - Severity Grouping of Power Operations Fire Events - 1986-1994

.... F-4 Appendix F-Table lli Risk insights - Comparison of Power Operations Fire Frequency With Selected Plants PRA Data - By Plant Location F-8 Appendix F-Table IV Risk insights - Comparison of Selected Plant Fire PRA Data with 1986-1994 Operating Experience........... F-14 l

i Appendix G-Table i Shutdown Fire Events Average Duration By Plant Location - 1965-1985

........................G5 l

Appendix G-Table 11 Shutdown Fire Events Average Duration By Plant Location - 1986-1994 G-11 Appendix G-Table lli Mean Duration Comparison Between Shutdown and Power Operations Fire Events - 1965-1985..

... G-14 Appendix G-Table IV Mean Duration Comparison Between Shutdown and i

Power Operations Fire Events - 1986-1994....... G-15 q

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e TABLES (CONTINUED)

Table No.

Description Page Appendix H-Table !

Shutdown Fire Events - Average Fire Frequency By Plant Location - 1965-1985 and Comparison with Power Operations

......................H-2 Appendix H-Table 11 Shutdown Fire Events - Average Fire Frequency By Plant Location - 1986-1994 and Comparison with Power Operations,.........................

H-3 Appendix H-Table 111 Shutdown Fire Events - Average Fire Frequency By Plant Location - Combined, 1965-1994 and with Power Operations.......................... H -4 Appendix J Table i Overall Smoke Events Data - 01/01/65-12/31/85.... J-5 Appendix J-Table ll Overall Smoke Events Data - 01/01/86-12/31/94... J-15 xii

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c SPECIAL STUDY l

FIRE EVENTS - FEEDBACK OF U.S. OPERATING EXPERIENCE 1.

INTRODUCTION 1.1 Purpose of Study i

This study characterizes the frequency and nature of fire event data from U.S.

operating plants and examines the potential impact this updated data could have on fire risk assessments.

1.2 Background

The NRC's " Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities" (NUREG-1407, Reference 1), referenced the NRC sponsored Fire Risk Scoping Study (NUREG/CR-5088, Reference 2), as a confirmation that fire continues to represent a dominant.isk contributor. Of the six items listed in the " Internal i

Fires" section of Reference 1, item 2. addressed fire frequency data as fol!ows:

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"Most initiating event frequencies wero increased based on a much more

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complete data base available on fire occurrences in nuclear power plants. Under currently applied risk assessment methodologies, this increase in initiating event frequency alone results in a direct increase in overall fire-induced core damage frequency with all other factors i

remaining constant.

The fire events data used for the Fire Risk Scoping Study was limited to i

previous industry gathered data, such as the Sandia Laboratories data base (1965-mid 1985 - NUREG/CR-4586, Reference 3). Therefore, an update of this i

data was done to evaluate whether PRA insights about fire frequency and consequences were consistent with a comprehensive review of more recent operating experience.

i 2.

SCOPE OF STUDY This study updates the Sandia database (1965 through mid-1985) with fire event data from Ucensee Event Reports (LERs), the EPRI database (1965-1988), and fire-related component failure histories from the NPRDS database. The new database covers the period from 1965-1994.

With the combined and updated data for 1965-1994, the following analyses were performed:

1

Listing of tire events data, as input to an updated fire events database.

Apportionment of fire events by number, major cause, and cianilocation.

e Evaluation of the duration and frequency of fire events that occurred during power and shutdown operations.

Grouping of fire events by severity during power operations.

Comparison of calculated fire frequencies with PRA data and recent industry and NHC sponsored studies fer the potential effect on fire induced core damage frequency estimates.

e Comparison of the duration and fire frequency of shutdown fire events with power operations fire events.

i Listing of smoke events, including attributes similar to fire events data, as e

input to a smoke events database.

Exclusions from Scope:

Several significant attributes, that were used in the estimation of fire induced core damage frequency by the nuclear power industry, could not be included in the scope of this review due to the limitations of data. These included: the determination of fire suppression probability from the reported fire durations, i

information on the ignition and damage thresholds of cable insulation, and plant

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modifications as a result of Appendix R. Other exclusions included the following:

A review of the requirements of Appendix R was not included in the scope of this review. Reduction of operating plant fire frequency is dependent on a combination of fire protection elements, including:

adequacy of initial fire hazards analysis, plant modifications in compliance with Appendix R, reduction of combustibles, and other factors in Appendix R. For this study, 1965-1979 is considered as the pre-implementation period for Appendix R, 1980-1985 is considered as the implementation period, and 1986-1994 is considered as the post-implementation period.

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Although international Commercial nuclear reactor plant fire experience may provide risk insights to U.S. fire experience, this data was also excluded from this study due to the limitations of consistent, available data.

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Domestic and international non-Commercial reactor facilities fire experience were excluded.

2.1 Data Sources Fire event data for this study was initially obtained from the Sandia database for 1965 through mid 1985 (Reference 3). Updates were made from later Sandia data in NUREG/CR-4832 (Reference 4); Sequence Coding and Search System (SCSS) for fire event Licensee Event Reports (LERs) during 1980-1994; the Nuclear Plant Reliability Data System (NPRDS) for component failures that occurred with a fire event during 1965-1994; and the EPRI fire event database (proprietary) for fires that occurred during 1965-1988.

Sources for selected plant PRA fire induced CDF values and fire frequency values were obtained from PRA review documents of selected plants (see References 5 through 12). Other sources included review of EPRI fire requantification for Seabrook and Peach Bottom plants (Reference 13),

Kewaunee IPEEE (Reference 14), and the Fire Risk Scoping Study (Reference 2).

The data sources for this report were sufficient for estimating fire frequencies for general plant areas and for characterizing the overall nature, severity, and duration of fire events. However, the level of consistency in reporting items such as the system affected, the means of detection, the size of the fire, the amount of smoke produced, etc. varied among and within +9 particular data sources. These factors limited the ability to analyze the inipant of operating experience used to assess fire risk, such as the severity ratios, probability of 4

non-suppression, or component specific fire frequencies.

curther, these sources are expected to change in the near future, which may make updating this analysis or deriving additional risk related factors problematical. For example, since LERs are expected to continue as before, fires less than 10 minutes duration are not reportable. A significant number of I

fires in this assessment come from non-LER sources. One of these sources, the NPRDS database, is expected to be replaced by the Equipment Performance Information Exchange (EPIX) system. It is not presently clear if the same level of fire related information from the NPRDS will be captured in EPIX. The proprietary EPRI database and the newer Nuclear Electric Insurance Limited (NEIL) database may or may not be continued in the future. As none of these data sources were sufficient alone to characterize fire events, changes or deletions may affect the ability to extract risk related insights from the data sources in the future.

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J 2.2 Description of Terms and Assumptions Used in Study l

Overall Fire Events - The number of fire events that was reported during plant preoperational testing, power operations, and shutdown. Also included were j

reconci!ed EPRI database fire events that included fire events from plant-specific questionnaires that were not reported in LERs or in NPRDS. Excluded from the e

SANDIA fire database were construction phase fire events. Events where smoke occurred, but no fire occurred were excluded as fire events from all sources. The reporting methods used for review and update of the initial Sandia fire event data base were LER reported fires, NPRDS component failure histories involving fire events, and EPRI database fire events. In general, 1

events where fire or explosion occurred were counted as fire events, regardless of duration. Smoldering was considered as fire and not smoke, where there was indication of fire combustion. Fire events from the questionnaire portion of EPRI database were included after being reconciled (see 3.2 for reconciliation of j

EPRI database).

Operating-Years - The cumulative number of totai plants calendar years of operation for the period reviewed (i.e., 1965-1985, 1986-1994, etc.) on an annual basis and as a sum of the period reviewed. New plant starts (commercial operation date) and termination dates for plants were factored into the determination of plant operating-years.

Overall Fire Frequency - The number of overall fire events divided by the plant operating-years for the period reviewed.

Average Unit Availability Factor - The percentage of plant operating-years at power operation. NRC " Grey Books", NUREG-0020 was used for annual nuclear plant industry average availability factors from 1974 through 1994 (see Reference 14).

Reactor-Years - The product of plant operating-years and the Unit Availability factor. For a specified period, the average Unit Availability factor for the years within the pericd is used. For this study, when the period begins prior to 1974, each prior year was assigned the 1974-1585 average Unit Avaiiability factor.

Power Operations Fire Events - The number of fire events that occurred during power operation only.

Power Operations Fire Frequency - The number of power operations fire events for the period divided by the number of reactor-years (or divided by the product of operating-years times the average unit availability factor for the period). This value is used for comparison with plant PRA and other data sources, applicable to fire laitiated core damage frequency estimates.

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Shutdown Fire Events - The number of fire events that occurred when the plant was shutdown (i.e.,0% power).

Average Shutdown-Years -The result of plants average operating-years minus plants average reactor-years for the period reviewed.

Fire Duration - The time that the fire burned before it was suppressed. This i

time was established either directly or evaluated from reported data. Fire durations that were reported as a specific time in an LER were entered directly with that time. The other event durations used in this study were estimated from the fire data and grouped within 5-minute intervals (see Appendix A -

Tables I and 11). The maximum duration used was 100 minutes (similar to the maximum time used on probability of manual suppression curves used in the NUREG/CR-4832 for LaSalle Unit 2 (Reference 4).

Note: Some of the reported durations may be based on the dispatch of the fire brigade as opposed to the onset of the fire. This would introduce a bias toward shorter durations being reported. However, based on a qualitative review of the event narratives, this bias appears to be small.

Therefore, these estimated durations are provided as a qualitative perspective of the apportionment of fire durations within plant locations, between periods, and between power operations and shutdown.

Fire Extent - The size of the fire, characterized as follows:

Small - nominally one minute to 19 minutes in duration and may include an explosion.

l Mefum - nominally 20 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in duration. However, when contained and controlled, longer durations may be used.

.Lar_ge - Usually greater than one hour in duration, except when contained and controlled.

Fire Safe Shutdown Equipment - Pump trains used to safely shutdown the nuclear power plant in the event of a fire. This equipment may include nonsafety-related trains or components.

Smoke Events - Events that were reported from direct observation or that were

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evaluated as smoke residue on a component. This excludes fire and

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odor / smell. When both fire and smoke occurred, the event was categorized as l

a fire event.

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3.

APPROACH AND METHODOLOGY 3.1 Updating the Sandla Fire Event Data Base The Sandia Fire Event data base contains 354 fire events during a period from 1965 to mid-1985. The listed fire events occurred during the construction phase, preoperational testing phase, and operational phase for U.S. nuclear power plants. Most of the information provided was sufficient to identify the plant location (i.e., building, room, area), ouration of the fire, cause of the fire, and effect on the plant operation. When information could not be determined, it was left blank in the tables ("- "). No other reconcliation was made to this fire event data.

The fire event data base update included a review of existing Sandia data for the 1965-mid 1985 period, using NPRDS (1965-1985), SCSS (1980-1985), and other fire event updates made by Sandia and identified in the LaSalle PRA (Reference 4). Construction phase fires were excluded in the update.

The 1986-1994 period was added to the data base, using fire event data from LERs (SCSS) and fire events from component failure histories (NPRDS).

3.2 Reconciling the EPRI Fire Event Database for Fire Events Used in This Study The proprietary EPRI Fire Events database (1968-1988) included the SANDIA database fire events through mid-1985, except for construction phase fire events. A reconciliation of this database was made using the following basis:

Generally, the EPRI fire events, not reported from other sources, that were included in this study had the following attributes:

Resulted in or were associated with a SCRAM or Loss-of-Offsite Power (LOOP).

Explosions, except for Recombiners identified below.

Fire events with duration of 5 minutes or longer in plant areas that have safety-related systems or systems necessary for continued power operations.

EPRI database fire events (predominantly previously unreported fire events from plant-specific questionnaires) were excluded based on the follaving:

Reviewed and evaluated as not a fire or explosion (i.e., smoke or odor).

Not significant, due to at least one of the following:

l l

6 l

l l

4

+

Duration less than 5 minutes (except explosion, SCRAM. or loss of safety-related train or system).

+

Located in a plant area that is not adjacent to or could not propagate to a plant area that contains a safety-related system or system that could cause a plant shutdown (such as a stockroom, hallway trash can fire, warehouse, trailer, temporary building, etc.).

+

Located outside the plant area without affecting the switchyard area (i.e., a non-encroaching forest fire or brush fire).

+

Recombiner explosions (with no corollary fire 5 minutes or longer) that did not affect any plant power operations or safety-related t

systems that are needed for plant shutdown.

!.3 Apportionment of Overall Fire Events by Cause and Location Overall fire events were apportioned by major causes, and by location (for each major cause) as follows:

Major causes included: Electrical fakure (shorts, faults, grounds, etc.),

overheated material (oil, bearing lubrication, insulation, etc.), explosion (hydrogen gas ignition, etc.), W6!dind sparks / arcing, and other (unknown, personnel error, component failure, etc.).

Locations included: Reactor Building (BWR), Auxiliary Building (PWR),

Turbine Building, Switch Yard, Switchgear Room, Diesel Generator Building, Control Room, Cable Spreading Room, Containment, Service Water Pumphouse, Battery Room, and Other Buildings.

3.4 Overall Fire Frequencies Overall fire frequencies (i.e., number of overall fire events divided by number of calendar operating-years within the time period) was plotted to provide:

A plot of overall fire frequencies over the 1965-1994 period for possible i

trends, Mading a comparison of the 1965-1985 average overall fire frequency and the 1986-1994 average overall fire frequency for significance of difference.

Plots of the overall fire frequencies by plant location over the 1965-1994 period for possible trends.

7

3.5 Power Operations Fire Events and Duration of Power Operations Fire Events by Plant Location The number of power operations fire events and apportionment of these fire events by duration intervals were determined for tne two periods by plant location. Plots were made of these power operations fire event duration intervals distribution, including means, to provide a basis for:

Comparing durations in areas in different time periods.

Comparing power operations versus shutdown durations by plant locations.

3.6 Plant Average Unit Availability Factors and Power Operations Fire Frequencies it was necessary to determine the power operations fire frequencies by plant location to allow comparison with fire PRAs and other studies, where fire frequency is an used in the calculation of fire induced core damage frequency (CDF) estimates. For this determination, the plants Unit Availability Factor for each year of the two periods (1965-1985 and 1986-1994) was calculated using the " Grey Book" (Reference 14) data and averaged over the period of interest.

These averages were used to adjust calendar years to reactor-years of power operation. The power operations fire frequencies were plotted to provide:

)

A means to identify trends in power operations fire frequencies over the 19651994 total period by plant location.

A comparison between 1965-1985 and 1986-1994 average fire frequencies by plant location.

Bayes 90% intervals were developed for the power operations fire frequencies for both periods and the overall period by plant location, using a Jeffreys noninformative prior and the area specific data to develop the updated posterior interval. These frequencies were compared with plant fire PRAs and industry studies to determine whether the use of operational fire event data had a significant impact on the fire-induced CDFs or for the total plant fire-induced CDF.

3.7 Fire Severity and Risk implications Fire risk assessments generally use the following steps to produce an estimate of core damage frequency due to fires:

(1)

Estimate fire frequencies for particular locations in the plants.

8

l I

(2)

Estimate the probability of non-suppression of the fire in a given location, depending on factors such as detection and suppression systems, operator response, and combustible loading.

(3)

Given a fire that is not suppressed before the equipment in a particular plant location is considered to be failed, the effect of the fire on the PRA model is developed (causes a plant trip or not, causes a LOCA or not, and list of damaged equipment assumed to be unavailable).

(4)

With the information on trips, LOCAs, and/or equipment out-of-service, the PRA model is requantified to provide the conditional probability of core damage, given the effects predicted in (3), above.

(5)

Combining the frequency of fires with the probability of non-suppression and the conditional probability of core damage produces the core damage frequency estimate due to fire events.

The operating experience data on fire events in this report is suited to providing estimates of fire frequencies and some insight into non-suopression i

probabilities. However, it does not contain models and data for the other steps.

Therefore, this report uses two means of evaluating risk significance as noted in the next two subsections. One is to group operating experience into severity groups and the other is to evaluate existing PRA results (prior to IPEEE submittals) by a sensitivity analysis based solely on differences in fire frequency estimates.

3.7.1 Power Operations Fire Events Severity Grouping The apportionment of power operations fire events among five severity group categories was performed as a qualitative means of judging the significance of these fire initiators. The five categories used in this study are:

Category A - Fire events that caused loss of more than one train of a safety-related system or loss of multiple single-train safety-related systerns.

Category B - Fire events that resulted in a SCRAM and LOOP.gr resulted in a SCRAM and a loss of one train of a safety-related system and had a duration of 5 minutes or longer,.or resulted ;n a SCRAM and a loss of one train and had an explosion, regardless of the f;ie's duration.

Category C - Fire events that resulted in a SCRAM, regardless of the fire's om ation, but no loss of safety-related train occurred.

Category D - Fire events that resulted in a loss of one train of fire safe shutdown equipment, regardless of the fire's duration, but without SCRAM.

Category E - All other reported fire events.

9

}

l i

i 3.7.2 Comparison of Power Operations Fire Frequencies with Selected Plant PRA Data and Other Data by Plant Location i

in order to determine whether updated fire frequencies support the Fire Risk l

Scoping Study (FRSS) contention that fire events continue to be a dominant j

contributor to overall plant risk, a sensitivity analysis was performed. Since the data on fires did not provide sufficient information to assess the probabilities of detection and suppression, this sensitivity analysis only addresses potential changes in the fire event frequencies.

]

l The fire locations in PRAs and other analyses (such as the Kewaunee IPEEE j

and the FRSS) are often different from one analysis to another. These 1

differences may be due to plant-specific features, analysis assumptions, or screening criteria. However, five plant locations (Control Room, Cable i

l Spreading Room, Switchgear Room, Reactor Building (BWR), Auxiliary Building (PWR), and Turbine Building] are common to most analyses. The sensitivity l

analysis in this study focuses on these plant locations. Appendix F - Table.a i

and Figures 23,24 and 25 compare fire frequencies developed from operating fire events with the fire frequencies used in individual PRAs and other fire analyses considered in this sensitivity analysis.

i The first step in the sensitivity analysis was to compare the operating i

experience to the mean values used in the PRAs and other analyses. A generic fire frequency for each of the areas noted above was derived using a Bayes 90% interval, based on a Jeffreys noninformative prior and the poofed data from all plants (see Refe,ence 16 for methodology). Point estimates from PRAs and other analyses that fall completely outsidn this range are indicative of a significant difference between the generic frequency and the PRA estimate.

Conclusions regarding the generic frequencies being higher or lower than the

[

point estimates in the PRAs and other analyses are dependent on a finding of significant difference as noted above.

The next step in the sensitivity analysis was to compare how the resulting CDF of a particular analysis would change if the generic mean for the post-1986 period was subsduted for the plant-specific PRA fire frequency mean values. In Appendix F - Tabh Ill, the ratio of the generic mean of the post-1986 period to the existing fire frecuency is displayed. The ratios for the pre-1986 and overall 1965-1994 periods are also displayed as information. The use of the post-1986 ratio would produce the new CDF for that plant location, had the operating experience fire frequency been used and all other aspects of the analysis remained unchanged.

The last step in the sensitivity analysis was to determine the significance of the

}

resulting CDFs. Although plant-specific analyses varied, many used screening 10

l criteria such as tnat found in tne fee induced Vulnerability Evaluation (FIVE) methodology when calculating fire induced CDF for a specific plant location.

This study used the FIVE methodology-threshold of 10 as the basis for concluding whether the resulting change in the existing CDF for that plant location would be significant or not 3.8 Shutdown Fire Events Fire initiator frequencies in plant PRAs, including IPEEE internal fire CDF estimates, used fire events that occurred during power operations. However, there are no currently available shutdown PRAs that include fire risk. In light of what is known about fire risk analysis at power, it was decided to review fire events that occurred during plant shutdown, including calculations and evaluation of the following:

Mean fire durations during shutdown, by plant location, and compared these means with mean fire durations during power oporations for each of the two periods (1965-1985 cnd 1986-1994).

Average fire frequencies during shutdown, by plant location, and compared th.ese averages with average fire frequencies during power operations for each of the two periods (1965-1985 and 1986-1994).

3.9 Overall Smoke Events Smoke events include incidents where either a flame was not visible or evidence of a fire was not found, but smoke was present or smoke residue was found.

They were compiled from LER data (SCSS database) and from the NPRDS database for component failures for each of the two periods. These data have been attributed in the same manner as Fire Events data for the two periods, 1965-1985 and 1986-1994 as an input to a Smoke Events database as information. However, the " extent of smoke" was used instead of " extent of fire" and "cause of smoke" was used instead of "cause of fire."

Three densities were used to characterize the " extent of smoke": Heavy -

where a room or area evacuation was necessary; Medium - where room may be filled, but evacuation was not necessary and local action was not impaired; and Ught - where smoke or smoke residue, including burning odor (with evidence of component degradation or failure) was at a density less than the other smoke density categories.

11

a o

4.

RESULTS 4.1 Update of the Sandia Fire Event Data Base - Overall, Power Operations, and Shutdown Fire Events The Sandia Fire Event Data Base, for the period 1965-mid-1985, identified e

354 fire events,144 of which were evaluated by this study as Construction Phase fires and excluded. In the update review through the eno of 1985, additional fire events reported in LERs, NPRDS, the LaSalle PRA (Reference 4), and the EPRI database identified additional events, resulting in a total of 319 overall fire events for 1965-1985. The fire events were apportioned among plant modes as follows (see Appendix A

- Table I and Figure 1):

Pre-Operational Testing (Subsequent to Construction Phase, but prior to Power Operations):

23 Power Operations:

199 Shutdown (0% power):

97 The balance of the update, for the period 1986-1994, resulted in an e

additional 232 overall fire events (including extrapciated fire events) The sources for these events included component failure histories from the NPRDS database, LERs, and the EPRI database. These events were apportioned as follows (see Appendix A - Table il and Figure 1):

Power Operations (including extrapolated events):

142 Shutdown (including extrapolated events):

90 Since the period before 1989 contained fire events from the SANDIA and EPRI databases that were not reportable in LERs or NPRDS, it was necessary to extrapolate the count of these events for the period after 1989. This was necessary for comparisons of fire frequencies between the pre-1985 and post 1985 periods for a consistent basis. For this extrapolation, the SANDIA database unreported fire events in the 1979 -

mid 1985 period were reconciled in the same manner as the EPRI database reconciliation (see 3.2) This extrapolation resulted in 30 additional fire events for Power Operations and 30 additional fire events i

for Shutdown (average of 5 fire events per year each) and were included for 1989-1994 frequency analysis to account for fire events that were nonreportable through NPRDS or LERs.

e No trend is evident in the total number for fire events after 1975 for each of the plant modes and overall fire events (see Appendix A, Figure 1).

i 12

_ _. ~.-. - _ _ _ -. _... _. -

s

.m O

e 4

NUMBER OF POWER OPERATIONS NUMBER OF SHUTDOWN FIRE EVENTS TOTAL PLANT FIRE EVENTS - TOTAL PLANT No et town o,nei.ene Fue evente he se snute wn Fee svents i

25 20 4

30 f

1s 19 10 10 s

1 4

0"

^ '

O^

^^'

• i 111111111111111111111111111111 111111111111111111111111111111

!!,2,!.!!!,.!!!!,s!! ::::::::::

9.

,<9.>.9.,as.

9 as...,.9.,ss.

..,.9.

i Calender Years Calender veers C PheEvents SS SS C FWeEvents to 64 C PheEventa 86 SS C Feefvents 9&D4 i

No. Pwf Oper Fee Events.1845 1985. 194 No. SN*eewn,% Events. 1996-1985. 9, No. Pwe Oper Fue 8venes.19061994142.

he. $hteewn Ph Svente. 1984 1994. 90.

I 1

Inududes leye eneap. events.194$ 1994)

IWuduese 5t,# estab as ents.194& t 9943 1

NUMBER OF OVERALL FIRE EVENTO TOTAL PLANT No ei Total Fire Events 35 li n 30 25 n

e.

8 1

l i

15 10 5

0"'"

111111111111111111111111111111 999999999999999999999999999999 666667777777777888888888899999 567890123456789012345678901234 Calender Years Revised:19651985 Update:19861994 Rre Events.65 85: 319(ind 23 PreOpTst)

Fire Events, 86 94: 232 (includes 10/yr FIGURE 1 extrapolated fire events,89 94),

(FROM APPENDIX A) l 13 I

4.2 Apportionment of Overall Fire Events by Cause and Location The overall fire events were apportioned to gain insights in fire causes and plant locations, regardless of plant power levels. This data is intended for overall fire i

event concerns, but not directly applicable to risk assessments without adjustment to power operations only. The following provides the apportionment determined by this study-Overall fire events were apportioned among four major causes: Electrical Failure, Overheated Material, Explosion, and Welding. For the overall l

period (1965-1994), Electrical Failures and Overheated material l

comprised 69% of the causes (see Appendix B - Table I and Figure 2).

Electrical Failure (38%) was the predominant cause of fire events during all plant operations (i.e., overall) for the combined period 1965-1994, with an increase in apportionment (to 50%) during the update period,1986-1994; while the apportionment of the other causes (Overheated Material, Explosion, and Welding) decreased slightly during the update period.

Overall fire events, apportioned by location only were similar in apportionment for each of the two periods (1965-1985 and 1986-1994).

For the overall period, the fire event locations apportionment was predominantly in Auxiliary Building (PWR,15%), Turbine Building (18%),

Diesel Generator Building (15%), and Reactor Building (BWR,13%)(see Appendix C - Tables ll and lil and Figure 7).

4.3 Overall Fire Frequencies As in the review of overall fire events, the overall fire frequency provides the l

inclusion of operating (calendar) years in the overall fire review. The following provides a comparison between the two periods, 1965-1985 and 1986-1994, for both total plant and specific internal plant locations:

l The average total plant overall fire frequencies for the update period

)

e (1986-1994) were approximately one-third less than for the 1965-1985 period (see Appendix C - Figure 8).

The overall fire frequencies in most internal plant locations reviewed had a lower average frequency for the updated period (see Figuies 9-11 and Appendix C - Tables 11 and Ill. Figure 12 depicts Offsite and Temporary Buildings overall fire frequencies for information only).

14 l

i

=

e a

4 a

OVERALL FIRE EVENT APPORTIONMENT OVERALL FIRE EVENT APPORTIONMENT BY CAUSE - 1965 1985 BY CAUSE - 1986 1994 omHT MATL 32%

ovg,g7 y,yg,,g ExeLosos tog p

A

• N om 11%

ELEC FAA 32%

ELEC 8 A4 60%

WfLOING 1S%

l 010'. :2.,,,,

- a '- 2 ' '

t OVERALL FIRE EVENT APPORTIONMENT BY CAUSE - 1965-1994 EXPLOSION 9%

. ' ~ ~

OVEr.HT MATL 31%

l

/

\\\\

OTHER 10%

i ELEC Fall 38%

l WELDING 12%

i No. Fire Events: 492 Excludes extrapolated data, 1989 1930.

(FROM APPENDIX B) l i

15 i

4 4

OVERALL FIRE EVENT APPORTIONMENT OVERALL FIRE EVENT APPORTIONMENT 8Y LOCATION. 1965-1985 BY LOCATION - 1986 1994 Aua8ldg 10%

Auspdg 14 %

R.actawg 13%

n,ggg,,3g TurbWdg 24%

N

~Ti c.1

)

com., io%

N com.n e%

Tu,b8tdg 14%

,u ;

--y Niiv on 7%

.m

%g, g i g bachg,Rm l%

sechgram S%

4 Mw 5%

otnflidge 6%

oG 8eg 17%

oc adg 12%

8*'icMd 12%

ese Fe. E,.nas 319 Total N. F.. Ev.nts. 173 m.a cone n. em se,e n,.. sw e.,a m,.cm c.ms.,,on

. a.nn e.n n. on.t.. a r.m. Swg.

c m..no s.,w.e., rumon OVERALL FIRE EVENT APPORTIONMENT BY LOCATION - 1965-1994 AuxBidg 15 %

ReactBidg 13 %

TurbBid9

\\

Cont ain, 18%

8%

Offsite 3

SwchgrRm k g,

K OthBidgs 5%

9%

,,,,n -

Misc 6%

Swch Yd 8%

DG Bldg 15%

No, Fire Events: 492 Misc: ContlRoom, CblSprdRoom, BattRoom, FIGURE 7 ServWtrPmphse, & Temporary Bldgs.

(FROM APPENDIX B) 16

i

- - - -.. =

OVERALL FIRE FREQUENCIES TOTAL PLANT Overall Fire Frequency x E-1 7

65-85 AVE.

E j

6 (3.8E-1 )

s COMBINED

?

65-94 5

E AVE.

86-94 s

1 8

j (3.3E-1)

AVE.

i 4

E (2.8E-1) s s

c s

E E

q {-

l 3

E G

E s s

s s

1 E s $

s

~

/

I

! l l 6

~

G s

8 s

G 1

s s

s e

2 7 e

s s i s

s ;s E 4

1 s

E

,6 s

3 s

8 s s E

s 8

s s

s s

l 's s

s s

E G

G 1

l E

5 s s 6

s s s j

3 s 6

?

l E

6 s

s s

s s

E 3 !

G s

l l

s s

s y

0' 111111111111111111111111111111 999999999999999999999999999999 666667777777777888888888899999 567890123456789012345678901234 Operating Years Overall Freq:65-85 I

I Overall Freq:86-94 No. fire events: 65-85, 319; 86-94, 233 (inci 60 extrapolated events).

FIGURE 8 Cal.oper.-yrs:65 85, 850.4: 86 94, 816.3 (FFIOM APPENDIX'C) 17

i a

4.4 Duration of Power Operations Fire Events by Plant Location e

For the 1965-1985 period, the majority of fire events (78%) in plant locations with safety-related systems were less than ten minutes duration; while 68% of these fire events were less than five minutes duration. Mean durations were longer than 10 minutes in some plant locations due to the occurrence of a few long duration fires. The following provides a summary of the durations at the plant locations with safety-related systems:

Plant No. Fire Events Mean Location

< 5 Min.

<10 Min.

10 Min. or >

Total Duration control Room 3

3 0

3 2.5 Containment 3

5 1

6 5.6 Reactor Bldg (BWR) 12 13 5

18 15.3 Auxiliary Bldg (PWR) 26 31 9

40 8.6 Cable Spreading Room 0

0 3

3 52.7*

Switchgear Room 7

7 2

9 17.4 Battery Room 3

3 0

3 2.5 Diesel Gen. Bldg 26 30 7

37 6.4 Serv. Water Pw phse J

2 0

J 2.5 Total No. Events:

82 94 27 121 Percent of Total:

68 78 22 100

• includes Browns Ferry fire, but limited to 100 minutes.

Two nonsafety-related locations, the Turbine Building and Switch Yard, had a higher average duration af approximately 20 minutes (see Appendix D - Figures 13-15 and Table 1). For most plants these locations have less risk significance. However, for some plants, the Turbine Building includes fire safe shutdown equipment.

e For the 1986-1994 period, the majority of fire events (58%) in plant locations with safety related systems were less than ten minutes duration; while 44% of these fire events were less than five minutes duration.

Mean durations were longer than 10 mint?. :n some plant locations due 1

to the occurrence of a few long duration faes. The following provides a Summary of the durations at the plant locations with safety-related systems:

Plant No. Fire Events Mean Location

< 5 Min

<10 Min.

10 Min.or >

Total Duration I

a control Room 1

1 0

1 2.0 Containment i

1 1

2 18.2 Reactor Bldg (BWR) 3 3

6 9

14.8 Auxiliary Ridg (PWR) 3 4

5 9

9.2 Cable Spreading Room 0

0 2

2 13.8 Switc'igear Room 2

2 2

4 28.2 Battery Room 0

0 0

0 0

Dieset Gen. 8tdg 5

10 1

11 6.6 Serv. Water Pwphse 4

4 1

5 4.8 Total No. Events:

19 25 18 43 Percent of Total:

44 58 42 100 18

-. _... ~

e 4

Two nonsafety-related locations, the Turbine Building and Switch Yard, had a higher mean duration of approximately 25 minutes (see Appendix D -Figures 16-18 and Tables ll and Ill). However, for some plants, the Turbine Building includes safety-related equipment or fire safe shutdown equipment.

The comparison of power operations fire events by plant location between the 1965-1985 and the 1986-1994 periods showed somewhat similar durations, except that the latter period was lower for the Cable Spreading Room and higher for Other Buildings and Containment. The lower duration was due to no long-term fire (i.e., no Browns Ferry fire type duration), while the higher duration in the Other Buildings was due.

predominantly to charcoal fires in the waste and off-gas treatment building. The high duration in the Containment was due to one event caused by welding (see Appendix D - Table lil).

4.5 Power Operations Fire Frequencies The power operations fire frequency for the majority of plant locations e

showed a decrease during the update period (1986-1994) when compared with the 1965-1985 period (see Appendix E'- Figures 19 21 and Tables Ill and IV. Appendix E - Tables I and il provide plant average Unit Availability Factors, used in converting overall fire frequencies to power operations fire frequencies).- The following depicts the ratio of 19651985 period to 1986-1994 period for these plant locations:

Plant Location R_gtfo Control Room 3:1 Other Buildings 2:1 Auxitiery BalLding (PWR) 2:1 Diesel Generator Building 2:1 Cable Spreading Room 2:1 Reactor Building (BWR) 1:1 Switchgear Room 1:1 Conta f ruent 1:1 Switch Yard 1:1 Turbine Sullding 1:1 Service Water Puuphouse 1:3-Battery Room (no fire events, 1986 1994) t b

19

4.6 Fire Severity and Risk Implications 4.6.1 Severity Grouping of Power Operations Fire Events Appendix F-Tables I and 11 and Figure 22 depict the plant operational data l

severity grouping for power operations fire events. The following provides insights to the risk significance of these fire events:

Of the 341 power operations fire events during the combined 1965-1994 period, one, the Browns Ferry fire in 1975, was not suppressed in time to prevent propagation to other safety-related trains or systems (Category A). Loss of function occurred to multiple systems.

For the 199 power operations fire events in the 1965-1985 period:

Ten fire events caused SCRAM and a loss of safety-related train and were suppressed without propagation (Category B).

Forty-one fire events caused a SCRAM, but with no loss of a safety-related train and were suppressed without propagation (Category C).

Twenty-two fire events resulted in a loss of one train of safe shutdown equipment, regardless of the fire's duration, but without a SCRAM (Category D).

For the 142 power operations fire events in the 1986-1994 period:

One fire event caused a SCRAM and loss of a safety related train, without further propagation (Category B). A second power operations fire event (Oyster Creek), initiated by an offsite fire, resulted in a SCRAM and Loss-of-Offsite Power (LOOP), but caused no loss of function to safety-related systems (Category B due to SCRAM with LOOP).

Forty fire events caused a SCRAM, but with no loss of a safety-related train and were suppressed without propagation (Category C).

Twenty-one fire events resulted in a loss of fire safe shutdown equipment, regardless of the fire's duration, but without a SCRAM (Category D).

The balance of power operations fire events were evaluated as less severe (Category E).

20

~-

,.--.n.=-_

a a.

e 4

i RISK INSIGHTS SEVERITY GROUPING RISK INSIGHTS SEVERITY GROUPING POWER OPERATIONS FIRE EVENTS-1965 1985 POWER OPERATIONS FIRE EVENTS-1986 1994 oIW C20%

C 20%

015 g s\\

(',

j~

ss 81%

s-t 85%

A1%

n

%, " ') <

s.<, P.-

4

%h y

3 '

v s

<',s s

M 1 54 %

i 2

No. of Fire Events et power: 199 No. Fire Events et Power: 142 Category A: 1: Category B: 10 Category At 0: Category 8: 2:

Category C: 41; Category D: 22 Category C: 40: Category D: 21 l

l RISK INSIGHTS - SEVERITY GROUP 4

POWER OPERATION FIRE EVENTS - 1965 1994 4

i 012%

C 24%

>d

~

,a B3%

j.

c's, r,

A1%

j' L^ ll sf'N._,

,J

^^

'< [

k'r ' ' <: i,'Jj, A s

s 5

, isfs ^

s e

,y.

1 i

E 60%

i Total No. of Fire Events at Power; 341 Category A: 1: Category B: 12 FIGURE 22 Category C: 81: Category D: 43 (FROM APPENDIX F) 21

4.6.2 Comparison of Power Operations Fire Frequencies with Selected Plant PRA Data and Other Data by Plant Location The sensitivity analysis for the PRAs and other analyses, based on 1986-1994 operating experience fire frequencies for each of the five plant locations, resulted as follows (see Appendix E-Table V and Appendix F-Table ill and Figures 23-25):

Control Room - The updated power operations mean fire frequency (2.6x10')

was lower than used in the selected PRAs and the industry studies.

Cable Spreading Room - The updated power operations mean fire frequency (4.3x10') varied from slightly higher to slightly lower than used in the selected PRAs and the industry studies.

Switchgear Room - With the exception of the Kewaunee IPEEE (point estimate 1.8x10 ), the updated power operations mean fire frequency (1.3x10') was 2

higher than used in the few PRAs and industry studies that had developed Switchgear Room fire frequencies and fire-induced CDF estimates.

Reactor Building (BWR) - The updated power operations mean fire frequency (5.4x10 ) was approximately the same as the two PRAs (Cuoper and LaSalle) 2 used for this study.

Auxiliary Building (PWR) - With the exception of the Kewaunee IPEEE (point2 estimate 7.3x10 ), the updated power operations rnean fire frequency (4.6x10 )

2 was approximately the same as all other point estimate fire frequencies used for specific PRAs and other studies.

Turbine Building - The updated power operations mean fire frequency (6.9x10 ) was higher than all the point estimate fire frequencies used for specific 2

PRAs and other studies.

There was little significant change in the specific plant location fire induced CDFs (the majority were still in the 10 ' screening range for the FIVE threshold).

Therefore, the following summari.es the comparison and addresses the major

?

purpose of this review:

The updated fire events database provides new information for assessing fire frequencies. The 1986-1994 fire event frequencies at power operations were lower for the Control Room and Cable Spreading Room, approximately the same for the Auxiliary Building (PWR) and the Reactor Building (BWR), and higher for the Switchgear Room and Turbine Building than those assumed by most PRAs reviewed in this study.

22

1 The updated fire events database and estimated frequencies should provide an improved source of fire initiation information for use in estimating fire frequencies for risk assessment or for reviewing such assessments. However, some more recent fire risk studies are using component level ignition source estimates for calculating fire initiation rate,s in specific plant locations as opposed to the approach in this report of calculating frequencies based on operating experience in particular areas. Either approach can be used, but comparisons between frequencies in this report and analyses using these other r.pproacnes requires some care in their application.

The use of these updated fire frequencies has the potential for proportionally lowering generic fire induced CDF estimates for the Control Room and the Cablo Spreading Room than those previously estimated in i

PRAs; while the potential for proportionally raising generic fire-induced CDF estimates for the Switchgear Room and Turbine Building. However, based on these updated fire frecuencies alone, there appears to be no significant impact on the fire-induced ODFs by major plant location or for the total plant fire-induced CDF (see Appendix F - Table ill and Figures 23 through 25 and Appendix F - Table IV).

4.7 Shutdown Fire Events 4.7.1 Duration of Shutdown Events for the 1965-1985 Period - The majority of fire events (77%) in plant locations with safety-related systems were less than 10 minutes duration; while 67% of the fire events were less than 5 minutes duration. The mean duration was longer than 10 minutes in the Containment due to two longer duration fires caused by welding. The following provides a summary of the durations at the plant locations with safety-related systems.

Plant No. Fire Events Mean locaticn

< 5 Min.

<10 Min.

10 Min.or >

Total Duration Control Room 1

1 0

1 2.5 Containment 7

10 12 22 21.5 Reactor Bldg (BWR) 14 16 2

18 4.7 Auxiliary Bldg (PWR) 10 10 3

13 7.3 Cable Spreading Room 1

1 0

1 3.0 Switchgear Room 7

8 0

8 3.1 Battery Room 0

0 0

0 0

Diesel Gen. 8tdg 12 13 1

14 4.2 Serv. Water Pumhse 0

1 Q

__1 8.0 Total No. Events:

52 60 18 78 Percent of Total:

67 77 23 100 23

4.7.2 Duration of Shutdown Events for the 1986-1994 Period - The majority of fire events (67%) in plant locations with safety-related systems were less than 10 minutes duration; while 43% of the fire events were less than 5 minutes duration. The mean duration was longer than 10 minutes in the Containment due to longer duration fires caused by welding. The following provides a summary of the durations at the plant locations with safety-related systems:

Plant No. Fire Events Mean L.ocation

< 5 Min.

<10 Min.

10 Min.or >

Total Duration control Room 0

0 0

0 0

containment 1

2 7

9 31.3 Reactor Bldg (BWR) 9 11 3

14 13.1 Auxiliary 8ldg (PWR) 5 7

1 8

5.1 Cable Spreading Room 0

0 0

0 0

Switchgear Room 3

4 1

5 5.9 Battery Room 0

0 0

0 0

Diesel Gen. Bldg 1

6 3

9 10.9 Serv. Water Pupphse 1

1 0

J 2.5 Total No. Events:

20 31 15 46 Percent of Total:

43 67 33 100 Except for the Containment, the mean duration of shutdown fire events for plant locations was approximately the same to lower than for mean durations occurring during power operations for both the 1965-1985 and 1986-1994 periods. The Containment fire everr were predominantly caused by welding sparks / arcing (see Appendix 3-Tables I-IV and Figures 26-31).

4.7.3 Shutdown Fire Frequencies e

For the 1965-1985 period, the shutdown fire frequencies were approximately the same or lower in comparison to the fire frequencies at power for most risk significant plant locations used in PRAs; while higher fire frequencies were calculated for the Containment and Reactor Building (BWR)(see Appendix H-Tables I).

e For the 19861994 period, the shutdown fire frequencies varied in comparison to the fire frequencies at power for most risk significant plant locations used in PRAs. Since seme plant locations were higher (Containment, Reactor Buildina, Auxiliary j

Building, Switchgear Room, and Diesel Generator Buiicing - see Appendix H-Tables ll), a more detailed review of shutdown fire events, resulted in the following conclusions:

Containment fires were predominantly caused by welding operations and did not affect decay heat removal.

24

O d

There were a limited number of fire events that affected the functional operability of Residual Heat Removal (RHR), Decay Heat Removal (DHR), and Emergency Diesel Generator (EDG) system trains. The number of fire events and fire frequencies and corresponding plant locations are as follows:

Shutdown No. Systess Plant Shutdown Shutdown Mean*

Location Systese Fire Events Reactor-Years Fire Freauency Reactor Bldg RHR 2

90.4 2.7x10' Auxiliary Bldg RMR &

2 139.8 1.8x10' DHR Switchgear Room RHR 1

230.2 6.5x10' Dies. Gen. Bldg EDG 7

230.2 3.2x10'

• indicates Bayes method mean, with noninformative prior.

4.7.4 Summary of Shutdown Fire Events Therefore, the operating experience indicates that the frequency and duration of shutdown fire events appears to be similar or less significant than for fire events occurring at power operation. This finding is somewhat tentative considering the limitation in treatment of fires in currently available shutdown risk assessments.

4.8 Smoke Events The overall smoke events are compiled in Appendix J - Tables I and 11 for the 1965-1985 period (95 events) and 1986-1994 period (296 events), respectively.

The major results are as fo!!aws:

The density of smoke events throughout the 1965-1994 period were predominantly Light (91%), followed by Medium (8%) and Heavy (1%).

Smoke Event Causes for the 'i965-1994 period were predominantly e

Electric Failure (66%), followed by Overheated Material (31%).

Smoke Event Locations for the 1965-1994 period were predominantly in the Auxiliary Building for PWRs (44%), in the Reactor Building for BWRs (17%), and jointly in the Turbine Building (13%), Diesel Generator Building (13%), and Service Water Pumphouse (6%). Smoke events in the Control Room were limited to approximately 3% over the entire period.

No risk significant effects were found from the review of Smoke Events for either of the two periods or for the combined period.

25

mi.__

a 4.-

.aA.____-.

aA-

__a2s,

.A_4-

..E I

as:

r

=.a,

.sa a

a me m..-

m i

d 5.

CONCLUSIONS The major results of this study are as follows:

A comparison of fire events in the pre-Appendix R period (1965-1985) with fire events in the subsequent period shows that event frequencies have declined slightly, while the safety significance of events has also been lower. The most significant fire event occurred at Browns Ferry in March,1975 and was a pivotal incident in the recognition of fire safety concerns. ft resulted in a scram and propagated without suppression to affect multiple redundant trains of safety equipment. Since the implementation of Appendix R modifications and other industry activities (1986-1994), there were no fire events with similar safety significance.

There were only two fire events resulting in a scram and loss of one safety related train or loss of offsite power (LOOP) during this period compared to 10 events previously. Other fires have been severe in terms of the magnitude and duration of combustion (such as some turbine building fires), but their severity in terms of challenges to safety systems operation has been limited. However, such fires could be important if redundant safety trains or decay heat removal systems were dependant on equipment located there.

e The fire durations during power operations were generally short (less than 10 minutes). The information available on these short duration fires was not sufficient to evaluate probability of fire detection and suppression used in recent PRAs.

The fire durations during shutdown were also generally short (less than 10 minutes). Shutdown durations in plant locations that contain systems necessary for decay heat removal during shutdown, were the same or lower than fire durations for the same plant locations during power operations, e

The 19881994 (post-Appendix R implementation) fire event frequencies at power operations were lower for the Control Room and the Cable Spreading Room, approximately the same for the Auxiliary Building (PWR) and the Reactor Building (BWR), and higher for the Switchgear Room and Turbine Building than those values used in most PRAs reviewed for this study. A sensitivity study, based solely on changes to the initiator frequencies, did not reveal substantial changes to the overall CDF due to fires. Other aspects of fire analyses may be more critical to their risk assessments, including: the mechanics of combustion, combustible loading, and means of detection and suppression. The data in this report was not suitable for addressing these issues.

26

4 4

l For the 1986-1994 period, the shutdown fire frequencies varied in comparison to the fire frequencies at power for most risk significant plant locations aed in PRAs. Since some plant locations were higher (Containment, Reactor Building, Auxiliary Building, Switchgear Room, and Diesel Generator Building), a more detailed review of shutdown fire events resulted in the following conclusions:

Containment fires were predominantly caused by welding operations and did not affect decay heat removal.

There were a limited number of fire events that affected the functional operability of Residual Heat Removal (RHR), Decay Heat Removal (DHR), and Emergency Diesel Generator (EDG) system trains. The number of fire events and fire frequencies and corresponding plant locations are as follows:

Shutdom No. System Plant Shutdown Shutdom Meen toegiED IER.tsta Fire Events teactor-Years Flee Frecmannev*

t Reactor Bldg RHR 2

90.4 2.7x10' Auxiliary Bldg RHR &

DHR 2

139.8 1.8x10' Switchgear Room RHR 1

230.2 6.5x10' Diesel Generator Building EDG 7

230.2 3.2x10'

• Indicates Bayes method mean, with noninformative prior.

Therefore, the operating experience indicates that the frequency and duration of shutdown fire events appears to be similar or less significant than for fire events occurring at power operation. This finding is somewhat tentative considering the limitation in treatment of fires in currently available shutdown risk assessments.

i e

Other results include:

]

Of the 341 power operations fire events during 1965-1994, one, the Browns Ferry fire in 1975, was not suppressed in time to 1

prevent propagation to other safety related trains or systems, For the 199 power operations fire events in trie 1965-1985 period, 10 fire events (in addition to the Browns Ferry fire) caused a SCRAM and a loss of one safety-related train. All but the Browns Ferry fire were suppressed without propagation.

l 27

For the 142 power operations fire events in the 1986-1994 period, only one fire event caused a SCRAM and loss of one safety related train, but without further propagation. A second power operations fire event (Oyster Creek), initiated by an offsite fire, resulted in a SCRAM and Loss-of-Offsite Power (LOOP), but caused no loss of function to safety-related systems.

The frequency of fires at power operations for the majority of plant locations showed a decrease during the update period (1986-1994) when compared with the 19651985 period.

Electrical Failure was the predominant cause of fire everits during all operations (i. e., overall) for the combinedi period 1965-1994, with an increase in apportionment during the update period,1986-1994; while the apportionment of the other causes (Overheated Material, Explosion, and Welding) decreased during the update period.

No risk significant effects were found from the review of Smoke Events for either of the two periods or for the combined period.

Although archival data is retrievable from the NPRDS database, no new nuclear plant failure history data is available through the NPRDS database after 12/31/96. It is not clear whether there will be an industry initiative to replace it with another data source that would be useful in compiling fire event and smoke event data.

1 28

~

6.

REFERENCES j

1.

NUREG 1407, " Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities," dated June,1991.

2.

NUREG/CR-5088 (SAND 88-0177), " Fire Risk Scoping Study: Investigation of Nuclear Power Plant Fire Risk, including Previously Unaddressed issues," dated January 1989.

l 3.

NUREG/CR-4586 (SAND 86-0300), " User's Guide for a Personal Computer-Based Nuclear Power Plant Fire Data Base," dated August, 1986.

4.

NUREG/CR-4832 (SAND 92-0537) Vol. 9, " Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP)," dated March 1993.

S.

NUREG/CR-2934 (SAND 82-2929), " Review and Evaluation of the Indian Point Probabilistic Safety Study," dated December 1982.

6.

NUREG/CR-4142 (UCID-20330), "A Review of Millstone 3 Probabilistic Safety Study," dated April 1986.

7.

NUREG/CR-4458 (SAND 86-2496), " Shutdown Decay Heat Removal Analysis of a Westinghouse 2-Loop Pressurized Water Reactor," dated March 1987. (Point Beach) 8.

. NUREG/CR-4448 (SAND 85-2373), "ShcLown Decay Heat Removal Analysis of a General Electric BWR 3/ Mark I," dated March 1987. (Quad Cities) 9.

NUREG/CR-4767 (SAND 86 2419), " Shutdown Decay Heat Removal of a General Electric BWR 4/ Mark I," dated July 1987. (Cooper) 10.

NUREG/CR-4710 (SAND 86-1797), " Shutdown Decay Heat Removal of a Cornbustion Engineering 2 Loop Pressurized Water Reac:or," dated August 1987. (St. Lucie) 11.

NUREG/CR-4762 (SAND 86 2377), " Shutdown Decay Heat Removal of a Westinghouse 3-Loop Pressurized Water Reactor," dated March 1987 (Turkey Pt. 3 & 4) 29

4 o

)

12. -

NUREG/CR-5726 (BNL-NUREG-52288), " Review of the Diablo Canyon Probabilistic Risk Assessment, " dated August 1994.

13.

(Draft) "A Review of Fire PRA Requantification Studies Reported in NSAC/181," (Sandia National Laboratories). (Seabrook and Peach Bottom).

14.

Wisconsin Public Service Corporation "Kewaunee Nuclear Power Plant -

Individual Plant Examination of External Events Summay Report," dated i

June 28,1994.

i 15.

NUREG-0020, " Licensed Operating Reactor Status Summary," 1974-1994, 16.

Idaho NrSonal Engineering Laboratory report, EGG-RAAM 11088,

" Events in Time: Basic Analysis of Poisson Data," dated September 1994.

I i

i i

4 30 se

l l

t 1

l l

i I

APPENDIX B OVERALL FIRE EVENT APPORTIONMENT BY CAUSE AND LOCATION l

t i

l i

l I

l

't b

n OVERALL FIRE EVENT APPORTIONMENT OVERALL FIRE EVENT APPORTIONMENT BY CAUSE - 1965-1985 BY CAUSE - 1986 1994 5

E MPLOSON 6%

V MT M k3 OVERMY MATL 29%

E APLOSCN 10%

/

\\

OTHER 11%

ELEC P AL 32%

\\

ELEC F AL 60%

WELDING 7%

WILDING 15%

% fee Events 173 l

Fue Evente 319 Eselueet espapeWeed date 1989 1994 1

l OVERALL FIRE EVENT APPORTIONMENT BY CAUSE - 1965 1994 1

i i

EXPLOSION 9%

OVERHT MATL 31%

/

kl OTHER 10%

ELEC Fall 38%

t s WELDING 12%

l No. Fire Events: 492 FEM 2 Excludes extrapolated data, 1989 1990.

B2

1 O

+

APPENDIX B - TABLE I OVERALL FIRE EVENT APPORTIDINENT SY CAUSE - TOTAL PLANT PERIOD: 1 % 5 1985 PERIOD: 1986 1994 PERI (2: 1945-1994 CAUSE N0 PERCENT

_NO PERCENT E

RCE9 a

2 Electrical Failures 102 32 86 50 188 38 (Shorts, Faults, Grounds, etc.)

overheated Materiet 101 32 51 29 152 31 (011, Bearings, Insulation, etc.)

Explosion 33 10 10 6

43 9

(Hydrogen gas ignition)

Welding sparks / Arcing 47 15 12 7

59 12 Other 16 11 14 J

J J

(Unknown, Personnel Error, Component Failure, etc.)

Totats:

319 100 1 73 100 492 100 NOTE:

1.

See Figure 2 and A p endia A, Tables I and II.

2.

Entrapolated data for 1989-1994 (10/yr.) is emetuded from this table.

1 i

l 1

i B-3

l i

l l

OVERALL FIRE EVENTS APPORTIONMENT OVERALL FIRE EVENTS APPORTIONMENT BY LOCATION " ELECT. FAILURE

• 1965-1985 BY LOCATION " ELECT. FAILURE' 19861994 ass adg aus Dog 12 %

36 %

Twb Odg

/

A'8CI 809 10 %

React Sad 9 16 %

\\

N

\\

/

c ;.-

' w

/

//.

d g

1. 'g'd8 Conte Rm

~

oth Ddge 7

4%

7 5%

other Bhtes C,"Yd g sw Pmphoe o;;.

it, oo,d, Sach9' Rm Sachge Am Mesc 10 '*

oc sing 7%

10 %

$4 0%

ho 19691909 Pened 102 No fuents tot 19841994 Pened. 36 m.twents tot a cent.n.ni. ec edRm. sen we n sw.*,,

cone Am, c ine so d Pmphae. offste fewf en es4 Sett Room Am. and Gene,y Room.

)

OVERALL FIRE EVENTS APPORTIONMENT BY LOCATION " ELECT. FAILURE" 19651994 i

1 Aux Bldg 25 %

React Bldg Turb Bldg N\\ x, \\.

///

7 j

Oth Bldgs iy; j

'~

5%

Swch Yd

]U'/ Offs e

/ SWNphse 4%

l DG Bldg Swchgr Rm

)

10%

Misc 7%

7%

l i

I 1

l No. Events for 1965-1994 Period: 188 Misc.: Containment, Conti Rm, Cabl.Sprd FIGURE 3 j

Rm, Batt. Rm. and Temporary Bldgs.

1 B-4

e OVERALL FIRE EVENTS APPORTIONMENT OVERAtt FIRE EVENTS AF?ORTIONMENT BY LOCATION

• OVERHEATED MAT'L".19651985 BY LOCATION

• OVERHEATED MAT'L* 1986-1994

~Io?

a,',"'

^";%"'

r...

s 19% -

Turb Sdg

\\

Reect 9de 38 %

30 Conten g

5%

g cani,n u,g Oto Dogs N

4%

OHete 7%

4%

$wch vd 8

DG Dde 4%

n 34 %

ho Events for 196619tS Pened 101 M.ac : CM Spd Ren.8wqch Vd.

Ortste. and Teenpenery esdge

% fvents tee 1986-1994Pened St OVERALL FIRE EVENTS APPORTIONMENT BY LOCATION " OVERHEATED MAT *L"-1965-1994 Aux Bldg 9%

9 Turb Bldg 24%

g \\'

Contain, 5 %

b w i.

\\

Off site 3%

2%

! Swch fd 5%

/ Oth Bldg 4%

DG Bldg 34%

FIGURE 4 No. Events for 1965 1994 Period: 152 Misc.: Cable Spread Rm and Temp Bldgs B-5

o o

l I

OVERALL FIRE EVENTS APPORTIONMENT OVERALL FIRE EVENTS APPORTIONMENT BY LOCATION " EXPLOSION" 1965198 By LOCAT10N " EXPLOSION" 19861994 i

l i

I r., so,

• • • *de o%

e,

o,...

y oo.d, 3%

I*

l Y

1 x

o swchvd

)

0,n Ihdas 30 %

d3%

I

..,i......,-n Meec.; Sen Rm and Tenieeeary hdga 8eo f seMs foe 198 1994,ened 10 i

OVERALL FIRE EVENTS APPORTIONMENT BY LOCATION " EXPLOSION"-19651994 l

Turb Bldg Aux Bldg i

2%

Misc React Bldg DG Bldg 5%

Contain, w Y

]

7%

Oth Bldgs 37%

FIGURE 5

• do. Events for 1965 1994 Period: 43 Misc.: Battery Room and Temporary Bidgs.

B-6

1 OVERALL FIRE EVENTS APPORTIONMENT OVERALL FIRE EVENTS APPORTIONMENT

)

BY LOCATION

• WELDING SPARKS" 1965-1985 Bf LOCATION." WELDING SPARKS" 19861994

' "'E

cone ment

//

f,/,

" r,',~'

,/

Saden Ya 2'

I

(

Oth Sidgs

~;p.

..g..

'1;ra

';r' r..

34 %

~...,,...........,

OVERALL FIRE EVENTS APPORTIONMENT l

BY LOCATION " WELDING SPARKS"-19651994 I

l Containment 40%

React Bldg

/

14 %

M N

y--

Switch Yd I

\\

2%

Aux Bldg h

Swchgr Rm 10%

Oth Bldg Turb Bldg 8%

19%

FIGURE 6 No. Events for 1965 1994 Period: 59 B-7

o a

I L

OVERALL FIRE EVENT APPORTIONMENT OVERALL FIRE EVENT APPORTIONMENT 8Y LOCATION. 1965 1985 BY LOCATION - 1986 1994 i

I Au=No 10%

Aombdg 18%

9g Yurbektg 24%

Conten.10%

\\

h$r'

% ) ""*I*

h 111W

'W othedge 11%

g.cng,nm 5%

Ewchgenen 5%

gs 4%

Misc 7%

Switch 4d 8%

D4, 8:49 12 %

SwWchYd 12%

g g4g, y g Totas No Fr. Ev nts 173 he. f we Event. 319 mee.mcsue.. c mspron. senne.m.

ww c.ae am, cm se.e nm. sw emeb,

c aven

. ano sawm, rumew.

sanmm.on.n..aT.m see.

OVERALL FIRE EVENT APPORTIONMENT BY LOCATION - 1965-1994 l

AuxBldg 15%

ReactBidg x

Tur B dg Contain.

Jk N

.~

TM#..

am Offsite 3%

Swch rRm k

)

OthB dgs Misc 6%

Swch Yd 8%

DG Bldg 15%

ho. Fire Events: 492 i

j Misc: ContlRoom, CblSprdRoom, BattRoom, FIGURE 7 l

ServWtrPmphse, & Temporary Bldgs.

l B-8

APPEIDIX B - TABLE 11 OWERALL FIRE EVENTS LOCATION APPORTICIgEWY BY CAUSES - PERIT: 1965-1985 ITEn ELECTRICAL FAILURE OWERIEATED IETERIAL EMPLOSION ELDING SPARKS / ARCING OTHER TOTAL E

LOCATION B0.

PERCENT Ilo.

PERCENT mo.

PERCEhi No.

PERCENT Wo.

PERCENT MO 1.

Contairvnent 1

1 5

5 1

3 20 43 3

8 30 2.

Reactor stdg(BkJ 12 12 15 15 5

15 5

11 3

8 40 3.

Auxiliary BidcPWR) 37 36 10 10 1

3 4

8 4

11

$6 4.

Turbine 8tdg 7

7 19 19 8

24 7

15 5

14 46 5.

Controt Root 4

4 0

0 0

0 0

0 0

0 4

6.

Cable Spreading 1

1 2

2 0

0 0

0 1

3 4

Room 7.

Switchgear 10 10 0

0 0

0 6

13 1

3 17 Room 4

8.

Dieset Gen.

6 6

41 40 1

3 0

0 5

14 53 stdg 9,

Service Water 2

2 0

0 0

0 0

0 1

3 3

Pumphouse 10.

Switch Yard 12 11 2

2 0

0 1

2 2

6 17 11.

Battery Room 2

2 0

0 1

3 0

0 0

0 3

12.

Other Bldgs 6

6 4

4 14 Id 4

8 7

19 35 13.

Offsite 1

1 2

2 1

3 0

0 0

0 4

14 Temporary 1

1 1

1 1

3 0

0 4

11 7

Bldgs Totals:

102 100 tot 100 33 100 47 100 36 100 319 Percent of Period Total:

32 32 to 15 11 NOTES:

1.

Includes pre-operationet testing fire events.

2.

See Figures 3 - 7; Amendix A, Table I; and Amendix 5. Tabte I.

B-9

._m.

t APPEIBlX B - TABLE III UWERALL FIRE EVENTS LOCATIDII APPORTIDINENT NY CAUSES - PERICD: 1986-1994 ITEft ELECTRICAL FAILIRE OWERIIEATED INtTERIAL EXPLOSION lELDING SPARKS / ARCING OTHER TOTAL LOCATION No.

PERCENT toc PERCENT 10 0. PERCENT No.

PFRCENT IIe.

PE2 CENT 11 0.

1.

Contairinent 3

4 2

4 0

0 4

33 2

14 11 2.

Reacter Bldg (GWR) 14 16 6

12 0

0 3

25 0

0 23 3.

Aux?!tery Bldg (PWR)10 12 4

7 0

0 0

0 3

21 17 4.

Turbine 8tdg 14 16 18 35 2

20 4

34 4

29 42 5.

Control Room 0

0 0

0 0

0 0

0 1

7 1

r 6.

Cable Spreading 0

0 0

0 0

0 0

0 2

14 2

Roorn 7.

Switchgear 9

10 0

0 0

0 0

0 0

0 9

Room 8.

Diesel Gen.

7 8

12 24 1

to 0

0 0

0 20 Bldg 9.

Service Water 6

7 0

0 0

0 0

0 0

0 6

Pupphouse

• 0.

Switch Yard 12 14 5

10 3

30 0

0 0

0 20 11.

Battery Room 0

0 0

0 0

0 0

0 0

0 0

12.

Other stdgs 4

5 2

4 2

20 1

8 1

7 13 L

13.

03fsite 7

8 2

4 2

20 0

0 J

7 12 A

Totats:

86 100 51 100 10 100 12 100 14 100 173 Percent of Period Total:

50 29 6

7 8

NOTES:

1.

See Figures 3, 4, 5, and 6; Appendix A, Table II; and Appendix B, Table I.

5 2.

Excludes extrapolated data, 1989-1994 (10 fire events per year).

B-10 wa.

~ ~ _ - - -

- ~ '

_ -. _ _ _ _ _ - _ _ _ _ _ _. - ~. -__- -. -.______

APPElmiX B - TABLE IV OWERALL FIEiE EVENTS LOCATION APPORT10INENT BY CAUSES - CIBEIIED PERT (B: 1965-1994 ITEM ELECTRICAL FAILtRE OWERIEATED MATERIAL EXPLOSION ELDING SPARKS /ARCIIIG OTNER TOTAL NO 1.0 CATION NO.

PERCEN" No.

PERCENT Mo.

PERCENT 11 0. PERCEIIT

_ Ilo.

PERCENT IID A

A 1.

Containment 4

2 7

5 1

2 24 40 5

10 41 2.

Reactor 8tdg(BWR; 26 14 21 14 5

12 8

14 3

6 63 3.

Auxiliary Bldg (PWR) 47 25 14 9

1 2

7 7

7 14 73 4.

Turbine 8td3 21 11 37 24 10 24 11 19 9

18 88 5.

Control Room 4

2 0

0 0

0 0

0 1

2 5

[

6.

Cable Spreading 1

1 2

1 0

0 0

0 3

6 6

Room l

7.

Switchgear 19 10 0

0 0

0 6

10 1

2 26 Room 8.

Diesel Gen.

13 7

53 34 2

5 0

0 5

10 73 Bldg 9.

Service Water 8

4 0

0 0

0 0

0 1

2 9

Punphouse i

10.

Switch Yard 24 13 7

5 3

7 1

2 2

4 37 11.

Battery Room 2

1 0

0 1

2 0

0 0

0 3

12.

Other Bldgs 10 5

6 4

16 37 5

8 8

16 45 13.

Offsite 8

4 4

3 3

7 0

0 1

2 16 14.

Tenporary J

1 1

1 1

J 0

0 4

8 7

Bldgs Totats:

188 100 152 100 43 100 59 100 50 100 492 Percent of Period Total:

38 31 9

12 10 100 NOTES:

1.

See Figures 3, 4, 5, and 6; Appendix A, Tabte I AND II; and Appendix B, Table 1, II, and 111.

2.

Excludes extrapolated data, 1989-1994 (10 fire events per year).

3.

Includes pre-operational testing fire events (1%5-1985).

1 B-11 3-n

e a

APPENDIX C OVERALL FIRE FREQUENCIES l

l

I OVERALL FIRE FREQUENCIES TOTAL PLANT Overall Fire Frequency x E-1 7

65-85 AVE.

6 (3.8E-1) s COMBINED 65-94 5

j s

AVE.

86-94 l

s l

(3.3E-1)

AVE.

7 4

s (2.8E-1 ) -

a 8

i q

s s

3 5

~

?

t s

s s s 4

a G

j G

s G j j

s s

j 4

6 3

s s

2 8

1 s

m s

s s

4 c

G s

s 1

2 s

s 2

s 1

s s

s s

s' s 4

I l s

l 5 2 i i

5 5 !

l 3 !

s s

s s

s s

s s

s s

e s

s j

1 3

s 3

j s j j

0" 111111111111111111111111111111 999999999999999999999999999999 666667777777777888888888899999 567890123456789012345678901234 Operating Years

/' / Overall Freq:65-85 l

l Overall Freq:86-94 l

l No. fire events: 65-85, 319; 86-94, 233 (inci 60 extrapolated events).

FIGURE 8 Cal.oper.-yrs:65-85, 850.4: 86 94, 816.3 l

C-2 l

e i

OVERALL FIRE FREQUENCIES OVERALL FIRE FREQUENCIES CONTAINMENT REACTOR BUILDING (BWR)

Overall Fire Frequency x E-2 Overall Fire Frequency x E 2 25 50 20 40 65 85 AVE.

15 30 (1.2E 1) 86-94 AE (8 7E 2)

AE (3.5E-2)-

(2.1 E-2) 20 10 1

5 10 q

OnnEn00 h!

O n

.88 ! 8 ! B n..

111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Operating Years Operating Years

@ 1965 1985 C 19861954

@ 1965 1985 1986 1994 OVERALL FIRE FREQUENCIES OVERALL FIRE FREQUENCIES AUXlLIARY BUILDING (PWR)

TURBINE BUILDING Overall Fire Frequency x E-2 Overall Fire Frequency x E-2 60 25 50 20 65 85 86-94 40 gg g5 AVE.

AVE.

15 (5.4E-2) 16.2E-2)

AVE.

30 (1.1E 1) 86-94 AVE.

jo (5.6E 2) 20

~

10 q

l l l n

An O nlin l l ! B !

0 0

j 111111111111111111111111111111 111111111111111111111111111111 I

999999999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 l

567890123456789012345678901234 567890123456789012345678901234 j

Operating Years Operating Year 8

@ 1965 1985 C 19861994 6 1965.J85 C 19861994 FIGURE 9

}

C-3

i a

a l

l I

OVERALL FIRE FREQUENCIES OVERALL FIRE FREQUENCIES CONTROL ROOM CABLE SPREADING ROOM Overall Fire Frequency x E-2 Overall Fire Frequency x E 2 3

4 2.5

~

86 94 AVE 2

6545 86-94 2.5 (2.4E 3 AVE.

AVE.

(4.7E-3) 65-85 1.5 (1.0E 3) 2 AVE.

ii 14.7E-3) 1.5 1

q O.5 111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Operating Years Operating Years 1965 1985 1986-1994 C 19651985 C 19861994 No fire events. 1986-1994.

OVERALL FIRE FREQUENCIES OVERALL FIRE FREQUENCIES DIESEL GEN. BUILDING SWITCHGEAR ROOM Overall Fire Frequency x E 2 Overall Fire Frequency x E 2 20 16 14 15 12 65 85 10 l

AVE.

l (6.2E 2) g 65 86 1,

86-94 AVE.

AVE.,

6 (2.0E.2) 86-94 (3.6E 2)

AVE.

5 4

l (1.8E 2) 2 nd' L

l B 00

.l !

.00.

Ill an I

111111111111111111111111111111 111111111111111111111111111111 l

999999999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Operating Years Operating Years

)

1965 1985 C 19861994 19651985 C 19861994 FIGURE 10 C-4

+

a l

t l

OVERALL FIRE FREQUENCIES OVERALL FIRE FREQUENCIES SERVICE WATER PUMPHOUSE SWITCH YARD Overall Fire Frequency x E-2 Overall Fire Frequency x E-2 2.5 8

l 86 94 AVE.

86-94 17.4E 3) 65 85 AVE.

AVE.

6 (2.0E 2) 13.2E-2) -

l 1.5 5

65-85 AVE.

4 I '(3.5E-31 l

3 al l

2 0.5 1

0^

0 111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 l

666667777777777888888888899999 666667777777777888888888899999 l

567890123456789012345678901234 567890123456789012345678901234 l

Operating Years Operating Years

@ 1955 1985 1986 1994 19654 985 C 19861994 OVERALL FIRE FREQUENCIES OVERALL FIRE FREQUENCIES BATTEPY ROOM OTHER BUILDINGS Overall Fire Frequency x E 2 Overall Fire Freequency x E 2 i

4 25 l

l 3.5 l

20 l

3 2.5 16 l

65-85 65-85 AVE.

AE j

2 - g3,g.3, 1

~

86 9*

16

~

(2 4E-3)q

,E 3

(2.0E-2) 5 0.5 q

BhD n ll n 0 n 0 n d n

,,l 111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567690123456789012345678901234 Operating Years Operating Years

@ 1965 1985 C 19861994 O 1986 1985 C 19861994 d

FIGURE 11 c-5

a l

OVERALL FIRE FREQUENCIES l

OFFSITE Overall Fire Frequency x E 2 4

86 94 i

AVE.

(1.5E3 -

65-85 AVE.

N 4.7E 3 1

O 111111111111111111111111111111 999999999999999999999999999999 666667777777777888888888899999 567890123456789012345678901234 Operating Years

' ' 1965 1985 C 19861994 OVERALL FIRE FREQUENCIES TEMPORARY BLDG Overall Fire Feoquency x E-2 5

4 65 85 AVE.

, 8.2E 3)

(

2 i

1 0

111111111111111111111111111111 999999999999999999999999999999 666667777777777888888888899999 567890123456789012345678901234 l

Operating Years 1

1965 1985 C 1986-1994 FIGURE 12 No 1986-1994 data availatde I

I C-6

e 4

l l

i APPENDIX C - TA8LE I PLANT OPERATING YEARS - 01/01/65 -12/31/94 NO. PLANT OPERATING TEARS IFAR PWR BWR ALL PLANTS total 1965 2.0 3.0 5.0 1966 2.0 3.0 5.0 1967 2.0 3.0 5.0 1968 4.0 3.0

7. 0 1969 4.0 2.1 6.1 1970 4.4 5.7 10.1 1971 6.8 7.4 14.2 1972 8.2 9.1 17.3 1973 13.3 12.6 25.9 1974 18.8 14.4 33.2 1975 27.4 17.9 45.4 1976 31.9 20.0 51.9 1977 38.9 20.8 59.7 1978 38.5 20.8 59.3 1979 40.7 23.3 64.0 1980 41.7 24.0 65.7 1981 44.2 24.0 68.2 1982 47.6 24.0 71.6 1983 48.0 24.2 73.3 1984 52.5 26.5 79.0 1985 55.9 29.5 85.4 Subtotals:

521.9 328.5 850.4 1986 62.1 31.4 93.5 1987 65.2 32.5 97.7 1988 69.8 35.6 105.4 1989 71.8 36.0 107.8 1990 72.8 37.0 109.8 1991 T3.8 37.0 110.8 1992 72.8 37.0 109.8 1993 71.4 37.0 108.4 1994 72.0 37.0 109.0 Subtotals:

495.8 320.5 316,3 Totals:

1017.7 649.0 160'.7 NOTES:

l 1.

The sandia database was used for Fire events,1%5 through 1985 The plant operating years total for the 21 year period = 850.4.

)

j 2.

The tgadatad database period for Fire Events is 1986 through 1994, based on LER, component failure histories, and other fruiJatry database information. The plant operating-years total for the 9 year period = 816.3.

3.

The plant operating years total for the two periods combined (i.e., 1965-1994) = 1666.7.

4.

For overalt fire frecpJency calculations in Tables II and III of this Apppendix, use PWR values for Auxiliary Bldg ard SWR values for Reactor Bldg. All other locations are considered combined PWR and 3

BWR values for No. Plant Operating Years.

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APPEISIX C - IABLE II (CEEIIIIRJED)

OWERALL FIRE FREQtKIICY BY TOTAL PLAIIT Als PLAIIT LOCATIDII - 1 % 5-1985 ITEII PERICD PERCENTAGE g

LOCATIDII 1976 1977 1978 1979 L980 1981 1982 1983 1984 1985 TOTAL TOTAL 1

Cont airunent No. Fire Events 3

2 0

1 1

4 1

9 1

4 30 10 Plt Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overall Fire Freq.

0.058 0.034 0.000 0.016 0.015 0.059 0.014 0.123 0.013 0.047 0.035 2

Reactor Buildina (BWR)

No. Fire Events 2

8 1

1 2

4 2

1 2

5 40 13 Plt Oper.-Yrs 20 20.8 20.8 23.3 24 24 24 24.2 26.5 29.5 328.5 Overatt Fire Freq.

0.100 0.385 0.048 0.043 0.083 0.167 0.083 0.041 0.0 75 0.169 0.122 3

Auxiliary euildina (PWR)

[

No. Fire Events 6

2 3

4 6

6 5

4 6-4 56 18 i

Pit Oper.-Yrs 31.9 38.9 38.5 40.7 41.7 44.2 47.6 48.8 52.5 55.9 521.9 Overal1 Fire Freq.

0.188 0.051 0.078 0.098 0.144 0.136 0.105 0.082 0.114 0.072 0.107 4

Turbine Buildina No. Fire Events 0

5 2

0 5

2 4

1 6

6 46 14 Pit Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overalt Fire Freq.

0.000 0.084 0.034 0.000 0.076 0.029 0.056 0.014 0.0 70 0.071 0.054 5

Control Room No. Fire Events 0

0 1

1 0

0 0

2 0

0 4

1 Pit Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overalt Fire Freq.

0.000 0.000 0.016 0.016 0.000 0.000 0.000 0.027 0.000 0.000 0.005 6

Cable spreadina Room No. Fire Events 0

2 0

0 0

0 1

0 0

0 4

1 Pit Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 t

overall Fire Freq.

0.000 0.034 0.000 0.000 0.000 0.000 0.014 0.000 0.000 0.000 0.005 7

Switchaear Room No. Fire Events 0

0 1

3 3

0 6

0 1

1 17 5

Plt Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 overati Fire Freq.

0.000 0.000 0.016 0.047 0.046 0.000 0.084 0.000 0.013 0.012 0.020 8

Dieset Gen. Blda No. Fire Events 9

3 2

4 5

9 4

2 6

1 53 17

?

i Pit Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overall Fire Freq.

0.1 73 0.050 0.034 0.062 0.076 0.132 0.056 0.027 0.076 0.012 0.062 C-10

APPElmtX C - TABLE II (CDWTINUED)

OWERALL FIRE FREMENCY BY TOTAL PLANT Als PLANT LOCATION - 1965-1985 ITEM PERIm PERCENTAGE No.

LOCATION 1976 1977 1978 1979 1980 1981

+c82 1983

'984 1985 TOTAL TOTAL 9

service Water Ptmphouse No. Fire Events 0

0 0

1 0

0 c

0 c.

2 3

1 Pit Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overall Fire Freq.

0.000 0.000 0.000 0.016 0.000 0.000 0.000 0.000 0.000

0. C 0.004 10 sw3 ch Yard No. Fire Events 0

2 3

1 1

1 1

3 2

1 17 5

Plt Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overalt Fire Freq.

0.000 0.034 0.051 0.016 0.015 0.015 0.014 0.041 0.025 0.0'2 0.d20 11 Battery Room No. Fire Events 0

0 2

1 0

0 0

0 0

0 3

1 Plt Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 overatt Fire Freo.

0.000 0.000 0.034 0.016 0.000 0.000 0.000 0.000 0.000 0.000 0.004 12 Other Buitdina No. Fire Events 5

4 4

4 3

0 2

1 2

1 35 11 Ptt Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 overalt Fire Freq.

0.096 0.067 0.067 0.062 0.046 0.000 0.028 0.014 0.025 0.012 0.041 13 Offsite No. Fire Events 0

0 1

0 0

0 2

0 0

1 4

1 Plt Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overall Fire Freq.

0.000 0.000 0.016 0.000 0.000 0.000 0.028 0.000 0.000 0.012 0.005 14 Temporary Bld3 No. Fire Events 1

0 1

1 3

0 0

0 0

0 7

2 Plt Oper.-Yrs 51.9 59.7 59.3 64 65.7 68.2 71.6 73.3 79 85.4 850.4 Overalt Fire Freq.

0.019 0.000 0.017 0.016 0.046 0.000 0.000 0.000 0.000 0.000 0.008 Yearly Total No. Fire Events:

26 28 21 22 29 26 28 23 26 26 319 100%

Plant Operating-Yeers:

51.9 59.7 59.3 64 -

65.7 68.2 71.6 73.3 79 85.4 E6.4 Yearty Ave. Overalt Fire freq.: 0.501 0.469 0.354 0.344 0.441 0.381 0.391 0.314 0.329 0.304 0.375 NOTE: See Figures 7, 8, 9,10,11, and 12 and Appendix A, Table I.

C-11

APPEISIX C - TABLE 111 OWERA31 FIRE FREGLENCY BY TOTAL PLANT AfD PLANT LOCATION - 1986-1994 (WITN EXTRAPOLATED DATA)

ITEM PERl(B PERCENTAGE 1 % 5-1994 IXpelWED E

LOCATION 1986 1987 L985 M

M 1991 1992 E

M TOTAL TOTAL PERCENT.

1 Containment No. Fire Events 3

3 2

1 1

2 1

2 2

17 7

47 8

Pit Oper.-Yrs 93.5 97.7 105.4 107.8 109.8 110.8 109.8 108.4 109 816.3 1666.4 Overalt Fire Freq.

0.032 0.031 0.019 0.009 0.009 0.018 0.009 0.018 0.018 0.021 0.028 i

2 Reactor Buildina (BWR)

No. Fire Events 4

6 3

3 4

1 3

2 2

28 12 68 12 Plt Oper.-Yrs 31.4 32.5 35.6 36 37 37 37 37 37 320.5 649.0 Overall Fire Freq.

0.127 0.185 0.084 0.083 0.108 0.027 0.081 0.054 0.054 0.087 0.105 3

Auxiliary Buildina (PWR)

No. Fire Events 2

5 3

2 5

3 2

4 2

28 12 84 15 Plt Oper.-Yrs 62.1 65.2 69.8 71.8 72.8 73.8 72.8 71.4 72 495.8 1017.7 Overall Fire Freq.

0.032 0.077 0.043 0.028 0.069 0.041 0.027 0.056 0.028 0.056 0.082 4

Turbine Buildina No. Fire Events 3

9 8

5 4

6 4

4 5

51 22 vt 18 Plt Oper.-Yrs 93.5 97.7 105.4 107.8 109.8 110.8 109.8 108.4 109 816.3 1666.4 Overalt Fire Freq.

0.032 0.092 0.076 0.074 0.036 0.055 0.037 0.037 0.046 0.0(e 0.058 5

Controt Room No. Fire Events 0

0 0

1 0

0 0

0 0

1 1

5 1

Plt Oper.-Yrs 93.5 97.7 105.4 107.8 109.8 110.8 109.8 108.4 109 816.3 1666.4 Overalt Fire Freq.

0.000 0.000 0.000 0.009 0.000 0.000 0.000 0.000 0.000 0.001 0.003 6

Cable Spreadino Room No. Fire Events 0

0 2

0 0

0 0

0 0

2 1

6 1

Plt Oper.-Yrs 93.5 97.7 105.4 107.8 109.8 110.8 109.8 108.4 109 816.3 1666.4 overalt Fire Freq.

0.000 0.000 0.019 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.004 7

Switchaear Room No. Fire Events 0

2 0

4 2

2 1

1 3

15 6

32 6

Pit Oper.-Yrs 93.5 97.7 105.4 107.8 109.8 110.8 109.8 108.4 109 816.3 1666.4 overalt Fire Freq.

0.000 0.020 0.000 0.037 0.018 0.018 0.009 0.009 0.028 0.018 0.019 8

Diesel Gen. 8tda No. Fire Events 4

3 3

3 2

2 3

3 6

29 12 82 15 Plt Oper.-Yrs 93.5 97.7 105.4 107.8 109.8 110.8 109.8 108.4 109 816.3 1666.4 Overalt Fire Freq.

0.043 0.031 0.028 0.028 0.018 0.018 0.028 0.028 0.055 0.036 0.049 C-12

i I

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i 4

APPENDIX D POWER OPERATIONS FIRE EVENTS l

MEAN DURATIONS BY PLANT LOCATION AND 4

COMPARISON OF 1965-1985 DURATIONS WITH 1986-1994 DURATIONS i

i l

J 4

__~,,

. ~. ~

.~

.- _ _. _ _ = _

. ~. -

1 s

4 I

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION CONTAINMENT BUILDING - 1965 1985 REACTOR BUILDING (BWR)- 1965 1985 Number of Fire Events Number of Fire Cvents 30 30 25 25 MEAN MEAN 20 - 5 6 rmn.

20 15.3 rrun.

15 15 10 to i

5 5

0 C

0 0

>5 1 1 223344 55 6 6 7 7 8 89 9

>5 1 1 223344 5566 7 7 8 8 99 0<050 5 0 505050 50 5050 5 0<05050 5050505050505

<1 <<<<<<<<<<<<<<<<<<

<1 <<<<<<<<<<<<<<<<<<

501 22 33445566 7 7 8 899 1 501 223344 5566 7 7 5899 1 50 50 505050 5050505 0 505050505 0 50505050 0

0 Duronon intervel (Minutes)

Duration interval (Minutes)

No. fire events dunng power oper.: 6.

No fire events dunng power oper.: 18.

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION AUXILIARY BUILDING (PWR)- 1905 1985 TURBINE BUILDING - 1965 1985 Number of Fire Evente Number of r,re Events 30 30 3

25 25 h

MEAN 8 6 men.

18.3 rmn.

15 15

)

10 10 5

5 3

'E m'

0 0

>5 1 1223344556 6778899

> 51 12233445566778899 0<0505 05 050505050505 0<050505050505050505

< 1 <<<<<<<<<<<<<<<<<<

<1 50 1 223344 55667788 99 1 501 22334455667788991 505050505050505050 505050505050505050 0

0 Duretion interval (Minutes)

Duretion Interval (Manutes)

No. Sre event.

,in9,o.,e, o,e,.: 40.

No..,e evente unn9, owe, o,e,.: 3i.

FIGURE 13 D-2 l

e a

~... -

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION CONTROL ROOM - 1965 1989 CABLE SPREADING ROOM - 1965 1985 Number of Fere Events Number of Fire Events 30 30 25 25 j

1 0

MEAN 20 WEAN 2.5 nn.

52.7 min.

l 15 15 1

10 10 1

i 5

5

'U' U

O 0

>51 1 223344556677 88 99

>5 1 1 22334 4 556 67788 99 0<0505 05050505050505 0<050505050505050505 1<<<<<<<<<<<<<<<<<<

1<<<<<<<<<<<<<<<<<<

50122334 4 5 5 6 6 7 78 899 1 50 1 2 2334 4 55 667 7 8 8 99 1 5050 50505050505050 1

5050 50505050505 050 0

0 Duretion Interval (Mmutes)

Duretion interval (Manutes)

No. fire events durtng power oper.: 3.

No. Are events dunng power opera 3.

Includes Browns Ferry Fire (100rrun.,maa)

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION SWITCHGEAR ROOM - 1965 1985 DIESEL GENERATOR BUILDING - 1965 1985 Number of Fire Events Number of Fire Eventa 30 30 25 25 h MEAN 6.4 min.

20 utAN 20 17.4 min.

15 15 10 10 5

V 5

'U' 0

0

>51 1 22334 4 5566778 8 99

>5 1 1 223344 5566778899 0<05050505 0505050505 0<050505050505050505

< 1<<<<<<<<<<<<<<<<<<

< 1<<<<<<<<<<<<<<<<<<

501 223344 55667788991 501 223344556677 8 899 1 505050505050505050 5050505050 5050 5050 0

0 Dureteon intervel (Mmutes)

Duration Interval (Mmutes)

No. fire events duttng power oper.: 9.

No. fire events during power oper.: 37.

%Qy% j4 D-3

~..

- - ~. -. -. ~...

~ --

a 6

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION I

BATTERY ROOM - 1965 1985 OTHER BUILDINOS - 1965 1985 Number of Fire Events Number of Fire Events 30 30 25 25 - MEAN 12.6 min.

20 MEAN 20 2.5 anin.

15 15 E'/

10 10 1

h i

5 -

5 l

I O

0*'#

'PI

,m,

,m

>$ 1 1 223344 5 56677 %899

>5 1 1 223344 5566778899 0<05050 5050505050505 0<0505050505050F0505

< 1 <<<<<<<<<<<<<<<<<<

<1 <<<<<<<<<<<<<<<<<<

2 5 0 1 2 2 334 4 5 56 6 7 7 8 5 9 9 1 50 1 22334 4 556 6 7 78 8 99 1 50 5050 5050 50505050 50505060505050 5050 0

0 Duration interval (Manutes)

Duration Interval (Minutes)

No. fire events during power oper.: 3.

No. fire events dunng power oper.: 26.

POWER OPEtiMIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION SERVICE WATER PUMPdOUSE - 1965 1985 SWITCH YARD - 1965 1985 Number of Fire Events Number of Fire Events 30 30 i

25 25 U

20 - MEAN 20 19 3 rmn.

2.5 min.

4 15 15 10 10 5

5 0

0

>51 1 223344 5 566 7 7 8899

> 5 1 1 2233445566778899 0<050505t50505050505 0<050505050505050505

< 1 <<<<<<<<<<<<<<<<<<

<1 < < < <. s < < <<<<<<< <<<<

50122334 4 55667 78899 1 501 22134 4 55667 7889 91 50 5050505050505050 505050J05050505050 0

0 Duration interval (Minutes)

Duration Interval (Minutes)

No. Are events during power oper.: 2.

No. fite events dunng power oper.: 15.

FIGURE 15 2

D-4

t-1 APPEROIX D - TABLE I POKR OPERATIONS FIRE EVENTS tRatATION BY PLANT LOCATION - 1965-1985 t

DLRATION (MINUTES)

LOCATIDW

>0<5 5<10 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 55<60 60<65 95<100 TOTALS Contairument:

No. Fire Events:

3 2

1 6

Percent of Fire Events: 50 33 17 100 No. Fire Event-Min.:

6 12.5 15 33.5 Mean Duration (Min.):

5.6 REACTOR SUILDING: (But)

No. Fire Events:

12 1

1 1

1 1

1 18 Percent of Fire Events: 66 6

6 6

6 6

6 100 No. Fire Event-Min.:

29.5 7.5 23 30 40 45 100 275 Mean Duration (Min.):

15.3 AUM!LIARY SUILDING: (PWt}

No. Fire Events:

26 5

2 1

4 1

1 40 Percent of Fire Events: 65 12 5

2 10 2

2 100 No. Fire Event-Min.:

65 35 22 15 80 25 Mean Duration (Min.):

100 342 i

8.6 TtRSIE BUILDING:

No. Fire Events:

10 4

4 2

3 3

1 2

1 1

31 Percent of Fire Events: 32 13 13 6

10 10 3

6 3

3 100 i

No. Fire Event-Min.:

23.5 30 49 30 60 90 35 90 60 100 567.5 i

Mean Duration (Min.):

18.3 Control Room:

No. Fire Events:

3 3

Percent of 'ere Events: 100 100 No. Fire Event-Min.:

7.5 7.5 Mean Duration (Hin.):

2.5 l

y D-5 1

u

APPEIE!X D - TABLE I (CONTINUED)

P0lER OPERATIONS FIRE EVEllTS DURATION SY PLANY LOCATION - 1 % 5-1985 DURATION (MINUTLS)

LOCATION

>0<5

}<jo 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 55<60 75<80 95<100 TOTALS CABLE SPREADING E01BI:

No. Fire Events:

1 1

1 3

Percent of Fire Events:

33 33 33 100 No. Fire Event-Min.:

13 45 100 158 Mean Duration (Min.):

52.7 5WITCMGEAR ROOM:

No. Fire Events:

7 1

t 9

Percent of Fire Events: 75 12 12 100 No. Fire Event Min.:

17.5 39 100 156.5 Mean Duration (Min.):

17,4 OIESEL GENERATOR BUILDING:

No. Fire Events:

26 4

4 1

1 1

37 rercent of Fire Events: 70 11 11 3

3 3

100 No. Fire Event-Min.:

65 23 60 20 25 45 238 Mean Duration (Min.):

6.4 Battery Room:

No. Fire Events:

3 3

Percent of Fire Events: 100 100 No. Fire Event-Min.:

7.5 7.5 Mean Duration (Min.):

2,5 OTHER MIILDINGS:

(

No. Fire Events:

19 3

1 1

1 1

26 Percent of Fire Events: 73 12 4

4 4

4 100 No. Fire Event-Min.:

47.5 35 30 40 75 100 327.5 Mean Duration (Min.):

12.6 SERVICE WTER PLSPNIRISE:

No. Fire Events:

2 2

Percent of Fire Events: 100 100 No. Fire Event-Min.:

5 5

Mean Duration (Min.):

2.5 L

D-6 i

a>

e

t APPENDIX D - TABLE I (CONilNLED) i P0lER OPERATIONS FIRE EVENTS DURATION SY PLAali LOCATION - 1965-1965 DURATION (MINUTES)

LOCATION

>0<5 5<10 10<15 15<20 70<25 25<30 30<35 35<43 40<45 45<50 50<55 55<60 60<65 95<100 TOTtLS SWITCM YARD:

No. Fire Events:

5 2

5 1

1 1

5 Percent of Fire Events: 33 13 33 6

6 6

103 i

No. Fire Event-Min.:

12.5 15 62.5 40 60 100 29C Mean Duration (Min.):

19.3 NOTES:

1.

The maximaam duration of att fires used in this study was 100 minutes.

2.

The switchgear Room rumber of fire events incitales the Brouns Ferry fire, but the duration is also limited to 100 minutes, anximum.

3.

Duratiors for temporary buildings and of fsite tocations are not included in this table.

4.

See Figures 13, 14, and 15.

i I

L s

D-7

[

t I

b

's r

m m

.n

_.~,.--

_.. ~ -.

4 1

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION CONTAINMENT BUILDING - 1986-1994 REACTOR BUILDING (BWR) - 1980 1994 a

Number of Fire Events Number of Fire Events 20 20 a

15 15 MEAN MEAN 18.2 min.

14.8 min.

10 10 5

5 3

8 0

0

>5 1 1 223344 55 66 77 8 899

>5 1 1 223344 5566 7 78 899 0<050505050505050605 0<050505050505050505

< 1 <<<<<<<<<<<<<<<<<<

<1 <<<<<<<<<<<<<<<<<<

501 223344 5 5667 78899 1 50 1223344 556 6 7 78839 1 505050505050505050 505050505050505050 0

0 Duration interval (Minutest Deration Interval (Minutes)

No. fire events during power oper.: 2 No. fire events during power oper.: 9 (endudas entropolated events)

Excludes entropolated fire events.

6 "NER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION

'UXILIARY BUILDING (PWR) - 1986 1994 TURBINE BUILDING - 1996 1994 Number of Fire Events Number of Fire Events 20 20 15 16 MLAN MEAN 9.2 min.

22.1 min.

10 10 3

b

'4 5

5 l

2 M

a 1

a a

a a

a a

a a

a a

/

a a

a a

a a

a a

a n

s a

a a

>5 1 1J23344556677 8899

>5 1 1 223344 5566 77 8 890 0<050505050305040505 0<0505050505050505 05

<1<<<<<<<<<<<<<<<<<<

<1 <<<<<<<<<<<<<<<<<<

501 22334 4 5566778899 1 50 1 22 334455667 7889 9 1 50f050505050505050 50505068 50 5050 5060 0

0 Duration interval (Minutes)

Duration interval (Minutes)

No. fire events during power oper.: 9.

No. fire events during power oper.: 37 Eactodee extrapolated fire events.

Eactudes entropolated fire events.

flQQQ{ j6 D-8

~ - - _.

.c.~--

. ~

. - -... -. ~ -... ~ ~

~. - _ _. - ~. -

6 l

i

)

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS OURATION CONTROL ROOM - 1986-1994 CA8LE SPREADING ROOM - 1986-1994

)

Number of Fire Events Number of Fire Events l

20 20 t

l 15

~ MEAN MEAN II'0 *i" I

2.0 min.

10 10 5

5 0

0

>5 1 1 223344 556677 8 8 99

>51 1 223344556 677 9899 0<050505050505050506 0<050505050505050505

< 1 <<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<<<<<<<<

50 1 223 344 556 6 7 78 899 1 50 1 22 3344 55 66 778899 1 5050505050 50505050 505050505050G05050 j

0 0

Duration Interval (Minutes)

Duration intervel (Minutes)

No. Are events during power oper.: 1.

No. fire events during power oper.: 2 l

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION SWITCHGEAR ROOM - 1986-1994 DIESEL GENERATOR 8UILDING - 1986 1994 i

Number of Fire Events Number of Fire Events 20 20 15 15 MEAN MEAN 28.2 min.

6.6 min.

10 10 5

5 77 i00.,ia

.... a 0

>Bt 1 223344 5566778899

>5 1 1 223344 556 6778899 0<050505050505050505 0<05050 5050505050505

<1 <<<<<<<<<<< <<<<<<<

< 1<<<<<<<<<<<<<<<<<<

501 223344 5566 77 8899 1 501 2233445566 77 8 8 99 1 5050 50505050505050 50505050505050 5050 0

0 Duroon interval (Mirunes)

Duration interval (Minutes) l No. fire events during power oper.: 4 No. fire events during power oper.: 11.

Excludes outropolated Ere events.

Excludes entropolated fire events.

FIGURE 17 D-9

_m_ _. _ _

O 4

4 e

POWER OPERATIONS FIRE EVENTS DURATION POWER OPERATIONS FIRE EVENTS DURATION BATTERY ROOM - 1986 1994 OTHER BUILDINOS - 1986 1994 Number of Fire Events Numbee of Fire Events 20 20 1

l l

l 15 15 MEAN 50.9 min.

3 l

~

i 10 NO FIRE EVENTS 1

i 5

4 5

6 0

0-

> 5 1 1223344 5566 7 7 8 899 a

> 5 1 1 22 334 4 5 5 66 7 7 8 89 9 0<05050 5050505050505 0<050 5 0 50 50 5 0 5 0 50 5 05 4 1 <<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<<<<<<51 1223344 5566778899

>5 1 1223344 55 667 78899 0<05050505050505050 5 0<050505050 505050505

<1<<<<<<<<<<<<<<<<<<

< 1<<<<<<<<<<<<<<<<<<

501 223344 5 5667 78 899 1 50 1 22334455667 7 8899 1 505050505050505050 5050505050b0505050 0

0 4

Duration intervel (Mmutes)

Duration Intervel (Minutes)

No. Are events during power oper.: 15.

No. Are events during power oper.:5.

Encludes entropolated Hre events.

FIGURE 18 I

D-10 2

APPEIBIX D - TABLE 11 poler OPERATIONS Flite EVENTS DURATICII BY PLANT LOCATirr - 1986-1994 DURATitRt (NiemaTES)

LOCATICM

>0<5 5<10 10<15 15<20 20<25 25<30 30<35 35<40 9 35 45<50 50<55 55<60 75<h0 95<100 TOTALS Contairument:

No. Fire Events:

1 1

2 Percent of Fire Events: 50 50 100 No. Fire Event-Min.:

2.5 34 36.5 Mean Duration (Min.):

18.2 ItEACTOR SUILDIIIG: (BWR)

No. Fire Events:

3 1

1 2

1 1

9 Percent of Fire Events: 33 11 11 22 11 11 100 No. Fire Event-Min.:

7.5 12.5 18 40 25 30 133 Mean Duration (Min.):

14.8 ABAtlllARY BUILDTIIG: (RJR) 1 No. Fire Events:

3 1

3 1

1 9

Percent of Fire Events: 33 11 33 11 11 100 No. Fire Event-Min.:

7.5 7.5 37.5 17 30 82.5 3

Mean Duration (Min.):

9.2 TURSIIIE BUILDIIIG:

No. Fire Events:

9 6

11 2

1 2

1 5

37 Percent of Fire Events: 24 16 30 5

3 5

3 14 100 No. Fire Event-Min.:

32.5 45.5 111.5 40 31 63.5 45 495 820.5 Mean Duration (Min.):

22.1 Controt Room:

l No. Fire Events:

1 1

Percent of Fire Events: 100 100 No. Fire Event-Min.:

2 Mean Duration (Min.):

2 2.0 D-11 e

[

a

- vs -

APPEIBIK D - IABLE II (CONTINUED)

PGER OPERATI(BDS FIRE EVENTS DutATICII BY PLANT LOCAf t0It - 1N-1994 DURATION (MINUTES)

LOCATICIf M

}<10 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50

%<55 55<60 75<80 95<100 TOTALS l

CABLE SPREADlIIG A0(31:

c t

No. Fire Events:

1 1

2 Percent of Fire Events: -

50 50 100 No. Fire Event-Min.:

12.5 15 27.5 Mean Duration (Min.):

13.8 SWITCIIGEAR Rot 31:

No. Fire Events:

2 1

1 4

Percent of Fire Events: 50 25 25 100 No. Fire Event-Min.:

5 50 53 113 Mean Duration (Min.):

28.2 DIESEL GEIIERATCR SUILDIIIG:

No. Fire Events:

5 5

1 11 Percent of Fire Events: 45 45 10 100 No. Fire Event-Min.:

12.5 37.5 23 73 Mean Duration (Min.):

6.6 Battery Room: (Iso Fire Events)

No. Fire Events:

O Percent of Fire Events: -

No. Fire Event-Min.:

Mean Duration (Min.):

0 OTHER BUILDIIIGS:

[

No. Fire Events:

1 2

1 3

7 Percent of Fire Events: 14 20 14 43 100 No. Fire Event-Min.:

1 23 32.5 300 356.5 Mean Duration (Min.):

50.9 SERVICE WATER PtDFIIERJSE:

No Fire Events:

4 1

5 Percent of Fire Events: 80 20 100 No. Fire Event-Min.:

10 14 24 Mean Duration (Min.):

4.8 D-12

...._m b

e APPElmlK 0 - TABLE II (CONI!NUED)

PGER OPERATitMIS FIRE EVENTS DtatATION Bf PLAllT LOCATION - 1986-1994 DLEtATICII (MIIRITES)

LOCATICII

>0<5 5<10 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 55<e0 75<80 95<100 TOTALS SWITCII YARD-t No. Fire Events:

7 1

1 1

2 1

1 1

15 Percent of Fire Events: 46 7

7 7

12 7

7 7

100 No. Fire Event-Min.:

17.5 10 16 10 60 40 77 100 349.5 Mean Duration (Min.):

23.3 IIOTES:

i 1.

The maximum charation of all fires ined in this study uns 100 airutes.

2.

No fire events occurred in the Control Room and Battery Room during the 1986-1994 period.

b 3.

Duretions for offsite fire events were not included in this table.

I 4.

Extrapolated fire everats (1989-1994) are not included.

t 5.

See Figures 16,17, and 18.

b 4

l.

i

?

i F

D-13

s o

i 9

i

+

APPENDIX E Pl. ANT AVERAGE UNIT AVAILABILITY FACTORS AND POWER OPERATIONS FIRE FREQUENCIES

+

POWER OPERATIONS FIRE FREQUENCIES POWER OPERATIONS FIRE FREQUENCIES CONTAINMENT - 1965-1994 and 1986-1994 REACTOR BLDG (BWR) - 1965 1994 l

I Power Operations Fire Frequency a E 2 Power Operations Fire Frequency a E-2 6

50 l

40 65 85 86 94 AVE AVE.

4 65-85 AVE.

30 g g,94

, (1.0E-2)

AVE.

3 (2.9E-2) q 20 2

10 q

j n

11.

ll ll ll

,,i>>>>>

111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999909999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Operating Years Operating Years 1965 1985 1986 1994

' 1965 1985 C 19861934 POWER OPERATIONS FIRE FREQUENCIES POWER OPERATIONS FIRE FREQUENCIES AUXILIARY BLDG (PWR) - 1965 1994 TURBINE BLDG - 1965-1985 AND 1986-1994 Power Operations Fire Frequency a E-2 Power Operations Fire Frequency x E 2 80 30 25 65-85 AVE.

20 65 85 (1.1 E < 1)

AVE.

40 86-94 15

~

86-94 AVE.

AVE.

14.5E 2)

, (6.8E 2)q 20 f

1 l

l 5

t 0 A' '

0 is1111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Operating Years Operating Years 1965 1985 1986-1994 1965 1985 C 19861994 FIGURE 19 E-2

e e

POWER OPERATIONS FIRE FREQUENCIES POWER OPERATIONS FIRE FREQUENCIFS CONTROL ROOM - 19651985 AND 19861994 CABLE SPPEAD RM. 19651985 AND 1986-1994 Power Operations Fire Frequency a E-2 Power Operations Fire Frequency x E 2 5

3 4

25 86-94 AVE.

(2E 3) 2

~

65 85 AVE.

1.5 85 (5.1E 3)

AVE 2

(5.1Eb)

AfE (3.4 E-3 H

~

0.5 q

1 0'

0 111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 66666777777777788884E888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Operating Years Opereung Years 1965 1985 1986-1*ht 1965-1985 1986-1994 POWER OPERATIONS FIRE FREQUENCIES POWER OPERATIONS FIRE FREQUEMCtES DIESEL GEN. BLDG-19651985 AND 19861994 SWITCHGEAR ROOM-1965-1985 AND 19861994 Power Operations Fire Frequency a E 2 Power Operations TNe Frequency a E 2 25 25 20 20 6585 AVE.

15 15 -(6.3E 2) 86 94 65 85 AVE.

10 AVE' 10 g'

86-94 (2.7E-3) q (1.5E 2)

AVE.

(1.2E 2) 5 5

}

0 0

A' 111111111111111111111111111111 111111111111111111111111111111 999959999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Opersang Years Operating Years E 19651985 1986 199-1 1965 1985 1986-1994 FIGURE 20 l

E-3

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1 j

i 1

POWER OPERATIONS FIRE FREQUENCIES POWER OPERATIONS FIRE FREQUENCIES SERV WTR PUMPHSE-19651985 AND 19861994 SW~lTCH YARD - 19651985 AND 1986-1994 J

Power Operations Fire Frequency a E-2 Power Operations Fire Frequency a 3

10 2.5 86-94 8

AVE' 65-85 (1.0E 2 AVE.

86-94 2

65-85 AVE.

AVE 6

(2.5E-2)

(2.9E-3) 1.5 (3.4Ed) 4 I

~

1 0.5 0

0 111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 6666677777777778888888i*199999 666667777777777888888888899999 5678901234567890123450sS901234 567890123456789012345678901234 Operating Years Operating Years 1965 1985 C 19861994 C 19651985 C 19861994 POWER OPERATIONS FIRE FREQUENCIES POWER OPERATIONS FIRE FREQUENCIES BATTERY ROOM - 1965-1985 AND 19861994 OTHER BLDGS - 19651985 AND 1986-1994 Power Operations F6re Frequency a E 2 Power Operations F6te Freequency a E-2 5

16 4

65-85 AVE.

10 (4.3E-2) 3 65 85 AVE.

8 (5.1 E-3 )

86-94 2

6 (1.7E ' )

2 4

1 2

b i1

>>>,i2 2

2 i.

.2 i, i iiii 0

0 111111111111111111111111111111 111111111111111111111111111111 999999999999999999999999999999 999999999999999999999999999999 666667777777777888888888899999 666667777777777888888888899999 567890123456789012345678901234 567890123456789012345678901234 Operatirn9 Years Operating Years 1965-1985 1986 1994 1965 1985 1986 1994 No Pro events. 1986 1994.

Mostly Recombiner and Offges Bldgs FIGURE 21 E-4

e t

APPENDIX E - IAStE I PLANT AVERAGE talIT AVAILABILITY FACTOR - 1 % 5-1985 1965 1966 1%7 1968 M'

19 3 197J 19p 1973 1974 1975 68.8*

68.8*

68.8*

68.8*

68.8*

68.8*

68.8*

68.8*

68.8*

69.2 76.5 PEtttB 1976 1977 19_78 1979 M

IM1, 1982 1983 1984 1985 AVERAGE i

69.3 73.4 74.8 67.9 65.4 67.8 65.7 63.9 63.0 68.5 68.8%

NOTES:

1.

source %r Plant Average tAnit Availability Factor uns NUREG-0020. "Licenced Operating Reactor Status Sumumery," (" Grey sooks) starting 1974.

2.

Plants' Average thit Availability for 1974-1985 =

825.4 = 68.8 %.

i 12 t

3.

• denotes use of 1974-1985 average for 1 % 5-1973, resulting in Plants' Average Unit Availability for 1%5-1985 = 1444.6 68.8%.

=

21 i

i APPENDIX E - IABLE I1 PLANT AVERAGE tNIIT AVAILABILITY FACTOR - 1986-1994 l

PERItB 1986 1987 19g M

1990 1991 1992 1993 1994 AVERAGE 65.5 67.2 69.8 68 5 71.1 73.6 74.8 76.6 79.1 71.8%

i NOTES:

1.

Source for Plant Average Unit Availability Factor was NUREG-0020, "Licenced operating Reactor status summary," (" Grey Books).

2.

Plants' Average Unit Availability for 1986-1994 = 646.2 = 71.81.

9 t

3.

Plants' Average thit Availability for 1965-1994 = 2090.8 = 69.7%.

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APPEISIX E - TABLE Ill (CONTINUED)

PERER OPERATI(NIS FIRE FREMEIICY SY TOTAt. PLANT Ade PLANT LOCAf t0N - 1%5-1985 I

PERIOD PERCENTAGE II.0_,

LOCATICII 1976 1977 1,93 1979 M

198_1 1982 j_983 1984 M

TOTAL TOTAL 1

Containment No. Fire Events 2

1 0

0 0

0 0

1 0

1 6

3 Ptt React-Yrs 35.97 43.82 44.36 43.46 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.056 0.023 0.000 0.000 0.000 0.000 0.000 0.021 0.000 0.017 0.010 2

Reactor Building (BWR)

No. Fire Events 1

4 1

1 1

2 0

0 0

0 17 9

Plt React-Yrs 13.86 15.27 15.56 15.82 15.70 16.27 15.77 15.46 16.70 20.21 226.01 Pur Oper. Fire Freq.

0.072 0.262 0.064 0.063 0.064 0.123 0.000 0.000 0.000 0.000 0.075 3

Auxiliary Building (PWR)

No. Fire Events 2

2 1

4 4

5 4

3 5

3 40 20 Plt React-Yrs 22.11 28.55 28.80 27.64 27.27 29.97 31.27 31.38 33.07 38.29 359.07 Pur Oper. Fire Freq.

0.090 0.070 0.035 0.145 0.147 0.167 0.128 0.096 0.151 0.078 0.111 4

Turbine Building No. Fire Events 0

2 1

0 2

1 2

1 5

6 31 16 Plt React-Yrs 35.97 43.82 44.36 43.%

42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.000 0.046 0.022 0.000 0.047 0.022 0.042 0.021 0.100 0.102 0.053 5

Controt Room No. Fire Events 0

0 0

1 0

0 0

2 0

0 3

2 Ptt React-Yrs 35.97 43.82 44.36 43.%

42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pur Oper. Fire Freq.

0.000 0.000 0.000 0.023 0.000 0.000 0.000 0.043 0.000 0.000 0.005 6

Cable Spreading Room No. Fire Events 0

1 0

0 0

0 1

0 0

0 3

2 Plt React-Yrs 35.97 43.82 44.36 43.%

42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pur Oper. Fire Freq..

0.000 0.023 0.000 0.000 0.000 0.000 0.021 0.000 0.000 0.000 0.005 7

switchgear Room No. Fire Events 0

0 1

3 2

0 0

0 1

0 9

4 Plt React-Yrs 35.97 43.82 44.36 43. %

42.97 45.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.000 0.000 0.022 0.068 -0.047 0.000 0.000 0.0000 0.020 0.000 0.015 8

Dieset Gen. 8tda No. Fire Events 7

3 0

2 2

8 3

1 4

1 37 18 Plt React-Yrs 35.97 43.82 44.36 43.%

42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.195 0.070 0.000 0.047 0.047 0.1 73 0.064 0.021 0.040 0.017 0.063 E-8

f APPElmlX E - TABLE til (CDETINUED)

PERER OPERATI(MIS FIRE FREEREIICY BY TOTAL PLAlli AaID PtAIIT LOCATION -

1 % 5-1985 ITEM IID LOCATION 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 TOTAL TOTAL PERIG) PERCEIITAGE 9

Service Water Ptschouse No. Fire Everits 0

0 0

1 0

0 0

0 0

1 2

1 Ptt React-Yrs 35.97 43.82 44.36 43.46 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.000 0.000 0.000 0.023 0.000 0.000 0.000 0.000 0.000 0.017 0.003 10 Switch Yard No. Fire Events 0

2 2

1 0

1 1

3 2

1 15 7

Plt React-Yrs 35.97 43.82 44.36 43.46 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.000 0.046 0.045 0.023 0.000 0.022 0.021 0.064 0.040 0.017 0.025 11 Battery Room No. Fire Events 0

0 2

1 0

0 0

0 0

0 3

2 Plt React-Yrs 35.97 43.82 44.36 43.46 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.000 0.000 0.045 0.023 0.000 0.000 0.000 0.000 0.000 0.000 0.005 12 Other Buitdina No. Fire Events 4

4 3

4 2

2 0

0 2

1 25 12 Ptt React-Yrs 35.97 43.82 44.36 43.46 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire freq.

0.111 0.091 0.068 0.092 0.046 0.043 0.000 0.000 0.040 0.017 0.043 13 offsite No. Fire Events 0

0 1

0 0

0 2

0 0

1 4

2 Ptt React-Yrs 35.97 43.82 44.36 43.46 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pur Oper. Fire Freq.

0.000 0.000 0.022 0.000 0.000 0.000 0.042 0.000 0.000 0.017 0.007 14 Temporary 8tda No. Fire Events 1

0 1

1 0

0 0

0 0

0 4

2 Plt React-Yrs 35.97 43.82 44.36 43.46 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Pwr Oper. Fire Freq.

0.0: 7 0.000 0.022 0.023 0.000 0.000 0.000 0.000 0.000 0.000 0.007 Yearly Total No. Fire Events:

17 19 14 18 13 17 13 11 17 16 199 10M Plant Reactor-Years:

35.97 43.82 44.36 43.M 42.97 46.24 47.04 46.84 49.77 58.50 585.08 Yearly Ave. Pur Oper. Fire Freq.: 0.473 0.434 0.316 0.414 0.302 0.368 0.276 0.235 0.342 0.2 74 0.345 IIOTES:

1.

See Figures 19, 20, and 21.

E-9

o e

j l

1 APPENDlX E - IA8LE IV POWER OPERATIONS EXTRAPOLATED FIRE EVENTS SY TOTAL PLANT AND PLANT LOCATION - 1989-1994 NLAEBER OF EXTRAPOLATED FIRE EVENTS LOCAfl0N L89 1990 1991 1992 1993 1994 TOTAL 1.

Containment 1

0 1

0 1

0 3

2.

Reactor Bldg (BWR) 0 1

0 1

0 1

3 3.

Auxiliary Bldg (PWR) 1 1

1 1

1 1

6 4.

Turbine Bldg 0

1 0

1 1

1 4

5.

Control Room 0

0 0

0 0

0 0

6.

Cable Spreading Room 0

0 0

0 0

0 0

7 Switchgear Room 0

0 1

1 1

0 3

8.

Diesel Gen. Bldg 1

1 1

0 1

1 5

9.

Battery Room 0

0 0

0 0

0 0

10.

Other Bldgs 1

0 1

1 0

0 3

11.

Service Water Pumphse 0

0 0

0 0

0 0

12.

Switch Yard 1

1 0

0 0

1 3

Totals:

5 5

5 5

5 5

30 Note:

Extrapolated data was developed from mreported fire events from EPRI reconciled data over 19/9-1988 period, with average of five fire events per year during power operationo and five fire events per year during shutdom. The location apportioment was determined at approximately the same apportionment of fire events from Appendix A - Tables I and Il for the 1979-1988 period.

l E-10

_ ~..

. ~ _. - - -

n-.

APPEIWlX E - TABLE V POKR EPERATIONS FIRE FRESENCY BY TOTAL PLAIIT Als PLAIIT LOCATION - 1986-1994 I

ITEM PERl(B PERCENTAGE LOCATICIl 1986 1987 1988 1989 1990 1991 1992 1993 1994 TOTAL TOTAL 1

Containment No. Fire Events 1

1 0

1 0

1 0

1 0

5 4

Plt React-Yrs 61.24 65.65 73.5 7 73.84 78.07 81.55 82.13 83.03 86.22 586.10 1

Pwr Oper. Fire Freq.

0.016 0.015 0.000 0.014 0.000 0.012 0.000 0.012 0.000 0.008 2

Reactor Buildina (BWR)

No. Fire Events 2

2 1

0 2

1 1

1 2

12 8

Plt React-Yrs 20.56 21.84 24.85 24.66 26.31 27.23 27.60 28.34 29.27 230.12 Pur Oper. Fire Freq.

0.097 0.092 0.040 0.000 0.076 0.037 0.036 0.035 0.068 0.052 s

3 Auxiliary BuildinQ (PWR)

No. Fire Events 2

3 1

1 2

1 3

2 1

16 11 Plt React-Yrs 40.68 43.81 48.72 49.18 51.76 54.32 54.45 54.69 56.95 355.98 Pur Oper. Fire Freq.

0.049 0.068 0.020 0.020 0.039 0.018 0.055 0.036 0.018 0.045 1

4 Turbine Buildina No. Fire Events 1

7 7

6 3

5 3

4 4

40 28 Plt React-Yrs 61.24 65.65 73.5 7 73.84 78.07 81.55 82.13 83.03 86.22 586.10 Pwr Oper. Fire Freq.

0.016 0.107 0.095 0.081 0.038 0.061 0.036 0.048 0.046 0.068 5

Controt Room No. Fire Events 0

0 0

1 0

0 0

0 0

1 1

Plt React-Yrs 61.24 65.65 73.5 7 73.84 78.07 81.55 82.13 83.03 86.22 586.10 Pur Oper. Fire Freq.

0.000 0.000 0.000 0.014 0.000 0.000 0.000 0.000 0.000 0.002 6

6 Cable Spreadino Room No. Fire Events 0

0 2

0 0

0 0

0 0

2 1

Plt React-Yrs 61.24 65.65 73.5 7 73.84 78.07 81.55 82.13 83.03 86.22 586.10 Pwr Oper. Fire Freq.

0.000 0.000 0.027 0.000 0.000 0.000- 0.000 0.000 0.000 0.003 7

Switchaear Room No. Fire Events 0

1 0

2 1

1 1

1 0

7 12 Plt React-Yrs 61.24 65.65 73.5 7 73.84 78.07 81.55 82.13 83.03 86.22 586.10 Pwr Oper. Fire Freq.

0.000 0.015 0.000 0.027 0.013 0.012 0.012 0.012 0.000 0.012 i

8 Diesel Gen. Blda No. Fire Events 2

1 1

2 1

1 2

2 4

16 11 Plt React-Yrs 61.24 65.65 73.5 7 73.84 78.0 7 81.55 82.13 83.03 86.22 586.10 l

Pwr Oper. Fire Freq.

0.033 0.015 0.014 0.027 0.013 0.012 0.024 0.024 0.046 0.027 t

E-11

APPENDIX E - TABLE V (CONTINULD) paler OPERATIONS FIRE FREGtENCY BY TOTAL PLANT AND PLANT LOCATION - 1986-1994 ITEM PERIG) PERCENTAGE g

LOCATION 1986 1987 1988 1989 1990 1991 1992 1993 1994 TOTAL TOTAL 9

Service Water Ptmohse ko. Fire Events 1

0 2

2 0

0 1

0 0

6 4

Pit React-Yrs 61.24 65.65 73.57 73.84 78.07 81.55 82.13 83.03 86.22 586.10 Pur Oper. Fire Freq.

0.016 0.000 0.027 0.027 0.000 0.000 0.012 0.000 0.000 0.010 10 Switch Yard No. Fire Events 1

2 3

1 3

3 3

0 1

17 12 Plt React-Yrs 61.24 65.65 73.5 7 73.84 78.07 81.55 82.13 83.03 86.22 586.10 Pwr Oper. Fire freq.

0.016 0.030 0.041 0.014 0.038 0.037 0.036 0.000 0.012 0.029 11 Battery Room No. Fire Events 0

0 0

0 0

0 0

0 0

0 0

Plt React-Yrs 61.24 65.65 73.5 7 73.04 78.07 81.55 82.13 83.03 86.22 586.10 Pwr Oper. Fire Freq.

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 12 Other Buildina No. Fire Events 1

2 2

1 1

1 2

0 0

10 7

Plt React-Yrs 61.24 65.65 73.5 7 73.04 78.07 81.55 82.13 83.03 86.22 586.10 Pwr Oper. Fire Freq.

0.016 0.030 0.027 0.014 0.013 0.012 0.024 0.000 0.000 0.017 13 Offsite No. Fire Events 1

0 1

1 4

0 1

0 2

10 Plt React-Yrs 61.24 65.65 73.5 7 73.04 78.07 81.55 82.13 83.03 86.22 586.10

-7 Pwr Oper. Fire Freq.

0.016 0.000 0.014 0.014 0.051 0.000 0.012 0.000 0.023 0.017 Yearly Total No. Fire Events:

12 19 20 18 17 14 17 11 14 142 100%

Plant Reactor-Years:

61.24 65.65 73.57 73.04 78.07 81.55 82.13 83.03 86.22 586.10 Yearly Ave. Pur Oper. Fire Freq.:0.1%

0.289 0.272 a.246 0.218 0.172 0.207 0.132 0.162 0.242 NOTES:

1.

See Figures 19, 20, and 21.

2.

Plant Reactor-Years for a specific year = plant operating-years for a specfic year tismes the (Jnit Availability factor for that year (see Appendix E - Table II).

3.

~ Totals incturJe 30 (5/ year, 1989-1994) extrapotered fire events. Apportionment of extrapotated data was by plant location, based on the 1979-1988 data (See Appendix E - Table IV).

E 1'?

e e

.--__=c-a.-.

- = -

- - - - - - - - - = - - - - - - -

APPEWIX E - TABLE VI PGER OPERATIGIS FIRE FREERENCY BY PLANT LOCATION - BAYES 90% INTERVALS 1 % 5-1985 PERIOD 1986-1994 PERIOD 1965-1994 IXBWINED PERIOD ITEst LDER LPPER LOER UPPER LGER tPPER g

LOCATION mam g

g(333 game g game maan g

mm 1

Containment 5.0E-3 1.1E-2 1.9E-2 3.9E-3 9.4E-3 1.7E-2 5.6E-3 9.8E-3 3.0E-2 2

Reactor 6.8E-2 7.7E-2 1.1E-1 3.2E-2 5.4E-2 8.2E-2 4.6E-2 6.5E-2 8.5E-2 Building (BWR) 3 Auxiliary 8.5E-2 1.1E-1 1.4E-1 3.0E-2 4.6E-2 6.7E-2 6.2E-2 7.9E-2 9.7E-2 Building (PWR) 4 Turbine 3.9E-2 5.4E-2 7.1E-2 5.2E-2 6.9E-2 8.8E-2 4.5E-2 6.1E-2 7.8E-2 Building 5

Control 1.8E-3 6.0E-3 1.2E*2 3.0E-4 2.6E-3 6.7E-3 1.4E-3 3.8E-3 7.2E-3 Room 6

Cable 1.8E-3 6.0E-3 1.2E-2 9.8E-4 4.3E-3 9.5E-3 2.0E-3

4. 7E-3 8.4E-3 Spreading Rm 7

Switchgear 8.6E-3 1.6E-2 2.6E-2 6.2E-3 1.3E-2 2.1E-2 8.9E-3 1.4E-2 2.0E-2 Room 8

Diesel Gen.

4.8E-2 6.4E-2 8.2E-2 1.8E-2 2.8E-2 4.0E-2 3.2E-2 4.6E-2 6.1E-2 Building 9

Service 9.8E-4 4.2E-3 9.5E-3 5.CE-3 1.1E-2 1.9E-2 3.7E-3 7.2E-3 1.2E-2 Water Puriphse 10 Switch Yard 1.6E-2 2.6E-2 3.8E-2 1.9E-2 3.0E-2 4.2E-2 2.0E-2 2.8E-2 3.6E-2 11 Battery Room 1.8E-3 6.0E-3 1.2E-2 3.4E-6 8.5E-4 3.3E-3 9.3E-4 3.0E-3 6.0E-3 12 Other Bldgs 3.0E-2 4.4E-2 5.9E-2 1.0E-2 1.8E-2 2.8E-2 2.2E-2 3.CE-2 3.9E-2 13 Offsite 2.8E-3 7.7E-3 1.4E-2 1.0E-2 1.8E-2 2.8E-2 7.6E-3 1.2E-2 1.8E-2 Note:

Jef freys noninforumtive prior (i.e., 0.5 fire events) was used in the develogment of Bayesian 901 intervals.

E-13

a 4'

4 i

\\

I l

j l

I 4

APPENDIX F 4

RISK INSIGHTS - SEVERITY GROUPING OF POWER OPERATIONS FIRE EVENTS l

AND COMPARISON OF POWER OPERATIONS FIRE FREQUENCIES WITH SELECTED PLANT PRA DATA BY PLANT LOCATION 4

4 i

i i

m.

.-.__m.._

m m.i.. __

4 l

t i

RISK INSIGHTS. SEVERITY GROUPING RISK INSIGHTS SEVERITY GROUPING POWER OPERATIONS FIRE EVENTS-1965 1985 POWER OPERATIONS FIRE EVENTS-1986 1994 L

D 11%

C 20%

D IS%

C 28%

s

(

Al%

gjg gi9i

• W" g' ~"'

>P i' d.:.m i

s-i:Q:9 F 53%

$ 56%

No fue Events et power 199 he. Fue Iwents et poww 142 Category A.1; Category S 14.

Category A 0. Category 8 2:

Catevery C:41. Category 0 22 Category C. 40. Category 0 21 RISK INSIGHTS - SEVERITY GROUPING POWER OPERATIONS FIRE EVENTS-1965 1994 1

D 12%

C 24%

l 5

B3%

,i Att %

tlY v

$$fE

/, s % ~,'

4

?

v y

!!!$d '.

E 60%

No, Fire Events at power: 341 Category A: 1: Category B: 12:

FIGURE 22 Category C: 81: Category D: 43 F-2

2 APPEN0lX F TABLE I RISK INSIGHTS - SEVERITY GRCUPING OF POWER OPERAfl0NS FIRE EVENTS - 1 % 5-1965 ITEM PLANT SAFETY SYS POWER SEVERITY LOCATION No.

DKT NAME DUR TRAIN EFF EFFECT CATEGORY 2

Switchgear Re:

4 1

++

1Hr-1 train SCRAM 8

45 min.

(Evaluated)

Auxiliary 8tds:

5 206 San 1He-1 train SCRAM B

onofre 1 45 min.

(Evaluated) 19 409 Lacrosse 20 min.

1 train SCRAM B

(Evaluated)

Reactor Stdg:

20 265 Quad 2 Hrs 1 train SCRAM S

cities 2 (Evaluated) 45 249 Dresden 3

<5 min.

I train SCRAM B

(Expl) (Evaluated)

D. G. Blde:

49 333 FitzPatrick 45 min.

1 EDG train SCRAM B

Cable Sprd am: 51 259 Browns Ferry 1 7 Hrs-Multiple SCRAM A

30 min.

Systems 99 278 Peach 45 min.

1 train SCRAM 8

Bottom 3 (Evaluated)

Other sides:

66 325 Brunswick 2

<5 min.

1 train SCRAM B

(Expt) (Evaluated) 74 249 Dresden 3

<5 min.

I train SCRAM 8

(Expt) (Evaluated)

Switch Yard:

265 3

++

3 Hrs-Plt AC Pwr SCRAM /

8 45 min.

(att)

LOOP NOTES:

1.

Power Operations fire events data (i.e., at power operations) is from Appendix A, Table I (1 % 5-1965).

2.

Severity Crow Category A: Fire events at power operations that caused loss of more thant one train of a safety-related system or loss of multiple single train safety-related systans.

3.

Severity Gro w category B: Fire events at power operations that resulted in a SCRAM g)d LOOP of resulted n a SCRAM and a loss of one train and had a & ration of 5 minutes or longer, o_r resulted in a SCRAM and a loss of one train and had an emplosion, regardless of the fire's dJration.

4.

Severity Cro @ Category C: Fire events at power operations that reutted in a SCRAM, regardless of

& ration, but no loss of a safety-related train occurred (41 fire events - not shown in this table.

See Appendix A - Tables I ard II).

5.

Sever ity Grom Category D: Fire events at power operations that resulted in a loss of one train of fire safe shutdown ewipment, regardless of the fire's daration, but without a SCRAM or Reactor Trip (22 fire events - not shown in this table. See Appendix A - Tables I and II)..

6.

Were "I train (Evaluated)" is listed, the specific safety related train was not identified in the initial SANDIA database or other industry database.

7.

See Figure 22.

l 1

l F-3 1

1 l

e a

APPENDIX F - TARLE 11 RISK INSIGHTS SEVERITY GROUPING OF POE R OPERATIONS FIRE EVENTS - 1986-1994 ITEM PLANT SAFETY STS POWER SEVERITY i

LOCATION A

D

_NA_ME DUR TRAIN EFF EFFECT CATEGORY A

a Reactor Blde:

17 341 Fermi 2

>10 min. HPCI Sys SCRAM B

(Manual)

Offsite:

139 219 Oyster Creek 17 Hrs Plt AC Pwr SCRAM /

B (all)

LOOP NOTES:

1.

Power Operations fire events data frtzm Appendix A, Table II (19861994).

2.

Severity Grote Category B: Fire events at power cperations that resulted in a SCRAM _and LOOP g resulted in a SCRAM and a loss of one train and had a duration of 5 minutes or longer, E resulted in a SCRAM and a loss of one train and had an explosion, regardless of the fire's daration.

3.

Severity Grote Category C Fire events at power operations that resulted in a SCRAM, regardless of duration, but no loss of a safety-related train occurred (40 fire events - not shows in this table, see A mendix A - Tables I and II).

4 Severity Grote Category 0: Fire events at power operations that resulted in a loss of one train of fire safe shutdonal egalpuent, regardless of tne fire's duration, but without a SCRAM or Reactor Trip (21 fire events - not shown in this table. See Appendix A - Tables I and II).

5.

See Figure 22.

4 4

4 F-4

a O

l I

l i

AUXILIARY BLDG (PWR) POWER OPERATIONS FIRE FREQUENCY COMPARISON l

DATA SOURCE 1965 1985 1986-1994 l

l 1965 1994

[

l St.Lucie 1&2 l

Turkey Pt. 3&4 l

Pt. Reach 1&2 l

Inden Pt. 2&3 l

Millstone 3 No Data Diablo Canyon No Data Kewaunee l

Seabrook(PRA) l Seabrook(FR$$)

l Seabrook(EPRI) l 0 20 40 60 80 100 120 140 160 FREQUENCY a E.3 TURBINE BLDG POWER OPERATIONS FIRE FREQUENCY COMPARISON DATA SOURCE 1965 1985 1986 1994 1965 1994 St.Lucie 1&2 l

Turkey Pt. 3&4 l

Quad Cities 1&2 No Data Cooper

~

l Pt. Beach 1&2 l

Indian Pt. 2&3 No Data Millstone 3 No Data Diablo Canyon l

Kewmunee l

LaSalle l

Seabrook(PRA) l Seabrook(FRSS)

Not Applicable Seabrook(EPRI)

Not Applicable

(

Pch Bottom (Fray Not Applicable h

,Not Applicable,

Pch Bottom (EPRI) 0 20 40 60 80 100 FREQUENCY a E-3 i

FIGURE 25 F-5

.. ~.. _ _.. _.... _.......

.m 1

4 4

1 CONTROL ROOM POWER OPERATIONS FIRE FREQUENCY COMPARISON 4

DATA SOURCE 1965 1985 19f 6-1994 1965 1994 4

1 St. Lucia 1&2 l

Turkey Pt. 3&4 l

Quad Cities 1&2 I

j Cocoor l

Pt. Beach 1&2 I

j Indien Pt. 2&3 I-

?

Millstone 3 No Data Diablo Canyon l

Kewaunee No Data LaSalle l

Seibrook(PPA) l Seabrook(FRSS) l Seabrook(EPR')

l l

Pch Bottom (PRA) l

,l Pch Bottom (EPRI) i 0

2 4

6 8

10 17 14 FREQUENCY a E-3 i

CABLE SPRD ROOM POWER OPERATIONS FIRE FREQUENCY COMPARISON DATA SOURCE I

1965 1985 1986 199l 1965 1994 St.Lucie 1&2 l

Turkey Pt. 364 l

Quad Cities 1&2 l

s Cooper l

Pt. Beach 1&2 1

Indian Pt. 2&3 l

Millstone 3 1

No Data Diablo Canyon K.

.un#e

- l LaSalle l

Seebrook(PRA) l Seabrcok(FRSS)

NO DATA Seebrook(EPRI) f Pch Bottom (PRA)

- l l

Pch Bottom (EPRI) 0 5

to 15 20 25 30 FREQUENCY a E 3 FIGURE 23 F-6

.- =.

A SWITCHGEAR ROOM POWER OPERATIONS FIRE FREQUENCY COMPARISON DATA SOURCE.

)

1965 1985 U

1986 1994 1965 1994 St.Lucie 142 No Data Turkey Pt. p s No Dats 1

Quad Cities t h2

- O*

Cooper No Data Pt. Beach 1&2 l

Indiert Pt. 2&3 No Data MiMstone 3 No Data Diablo Canyon No Date Kewaunee l

LaSalle l

Seabrook(PRA)

Not Applicable

(

SeabrookiFRSS)

Not Applicable 3-Seabrook (EPRI)

Not Applicable j

Pch Bottom (PRA) l

}

Pch Bottom (EPRI) ~l 0

5 10 15 20 25 30 FREQUENCY a E 3 4

REACTOR BLDG (BWR) POWER OPERATIONS FIRE FREQUENCY COMPARISON i

DATA SOURCE f

j 1965 1985 ij i

1 f

1986 1994 i

i f

1965 1994

=

Oued Cniaa 1&2 No Data Cooper f

LaSalle Pch Bottom (PRA)

Not Applicable PCH Bottom (EPRI) -

Not Applicable i

0 20 40 60 80 100 120 FREQUENCY a E-3 F-7

APPEIBl1 F - IABLE III RISIC INSIGIITS - NISON OF P(AER OPERATICIIS FIRE FREMEIICIES WITN SELEC1ED Pt.AIITS PRA DATA - BYePLANT LOCATION '

IIeen Present LOCATIEMI Fire Diff. hit.

Diff. hit.

Diff. hit.

Pt. Est.

ramparison Sigiificance CJON RnIJ3; Free.

W1965-19115 W1986-19%

w/1%5-1994 Fire (DF with 1986-1994 Data

1. This Stury;

a. 1965-1985 6.0E-3

b. 1986-1994 8.5E-4

c. 1%5-1994(contained) 3.0E-3 2.

St. Lucie 1&2:

4.9E-3 1.22 0.17 0.61 Lower, but CDF not quantified in PRA.

3.

Turkey Pt. 3&4:

4.9E-3 1.22 0.17 0.61 Lower, but CDF not quantified in PRA.

4.

Quad Cities 182:

4.9E-3 1.22 0.17 0.61 6.7E-6 Lower, but CDF still in E-6 range.

5.

Cooper 4.9E-3 1.22 0.17 0.61 Lower, but CDF not quantified in PRA.

6.

Point Beach 182:

4.9E-3 1.22 0.17 0.61 Lower, but CDF not quantified in PRA.

7.

Irdian Pt. 2&3:

4.9E-3 1.22 0.17 0.61 Lower, but Cor not quantified in PRA.

5.

Mil! stone 3:

NA NA NA Fire freq. and CDF not quantified in PRA.

9.

Diablo Canyon 5.0E-3 1.20 0.17 0.60 3.0E-6 Significantly lower CDF (E-7 range).

10. Kewaunee (IPEEE):

NA NA NA Fire freq. & CDF not quantified in IPEEE.

11. LaSalle 1.8E-3 3.33 0.47 1.67 1.4E-5 Lower, but CDF still in E-6 range.

12. Seabrook:

a. PRA(PLG):

4.7E-3 1.22 0.17 0.61 1.3E-5 Lower, but CDF still in E-6 range.

b. FRSS (SNL):

4.4E-3 1.36 0.19 0.68 9.7E-6 Lower, but CDF still in E-6 range.

c. EPRI Requantif.:

7.5E-3 0.80 0.11 0.40 1.0E-5 Lower, but CDF still in E-6 range.

13. Peach Bottom:

a. FRA(1150):

2.3E-3 2.61 0.37 1.30 6.2E-6 Lower, but CDF still in E-6 range.

b. EPRI Requantif.:

1.3E-2 0.46 0.07 0.23 1.9E-7 Lower, not significant (still <E-6 range).

IIOTE: See Figure 23.

F-8

?

m.

Y APPEISIX F - 1ABLE III (CIMITIIRJED)

RISK Ills:GIITS - Ct3FARISIM OF PGER (PERATI(NIS FIRE FREEREIICIES WITN SELECTED PLANTS PRA DATA - BY PLANT LOCATitEl Iteen Present LOCATION Fire Diff. 8tutt.

Diff. Itutt.

Diff. htt.

Pt. Est.

Casparisort Siptificance CABLE SPREADilIG R0(se:

Frea.

u/1965-1985 u/1986-1994 W1%5-1994 Fire CDF with 1986-1994 Data t

1. This Study:

a. 1965-1985 6.0E-3

b. 1986-1994 4.3E-3 c.1965-1994(conbined) 4.7E-3 2.

St. Lucie 112:

6.7E-3 0.90 0.64 0.70 1.5E-5 Lower, but CDF still in E-6 range.

3.

Turkey Pt. 384:

6.7E-3 0.90 0.64 0.70 3.0E-6 Lower, but CDF still in E-6 range.

4.

Quad Cities 182:

6.7E-3 0.90 0.64 0.70 5.8E-6 Lower, but CDF still in E-6 range.

5.

Cooper 6.7E-3 0.90 0.64 0.70 5.8E-7 Lower, not significant (stilt <E-6 range).

6.

Point Beach 112:

6.7E-3 0.90 0.64 0.70 Lower, but CDF not quantified in PRA.

7.

Indian Pt. 2&3:

7.2E-3 0.93 0.64 0.65 1.9E-6 Lower, but CDF still in E-6 range.

'i 8.

Mittstone 3:

2.6E-2 0.23 0.16 0.18 Lower, but CDF not quantified in PRA.

9.

Diablo Canyon NA hA NA Fire freq. ard CD: not quantified in PRA.

11,. Kewaunee (IPEEE):

3.2E-3 1.88 1.34 1.47 Higher, but CDF not quantified in IPEEE.

11. LaSatte 6.5E-3 0.92 0.66 0.72 1.6E-7 Lower, not significant (still <E-6 range).

12. Seabrook:

a. PRA(PLG):

6.7E-3 0.90 0.64 0.70 4.1E-6 Lower, but CDF still in E-6 range.

b. FRSS (SNL):

2.7E-3 2.22 1.59 1.74 2.3E-6 Higher, but CDF still in E-6 range.

c. EPRI Requmntif.:

2.8E-4 21.4 15.4 16.8 5.3E-9 Higher, not significant (still <E-6 range).

13. Peach Bottom:

a. PRA(1150):

3.5E-3 1.71 1.23 1.34 6.7E-7 Higher, not significant (still <E-6 i

range).

b. EPRI Requantif.:

7.5E-3 0.80 0.57 0.62 2.2E-8 Lower, not significant (still <E-6 range).

NOTE-See Figure 23.

i F-9 4

-.. - =

APPE EIR 5 - TAst.E III (CGITimKD) i RISK INSIGNTS - CEBPARISON OF PGER (PERATIONS FIk2 FREQUENCIES WITN SELECTED PUWils PRA DATA - BY PtANT LOCATION IIeen Present LOCATION Fire Diff. Itutt.

Diff. Itutt.

Diff. Stult.

Pt. Est.

Comparison Significance SWITCNGEAR ROOM:

Frea.

W1965-1985 m/1986-1994 W1965-1994 Fire CDF with 1986-1994 Da_ta

1. This Study:

1

e. 1965-1985 1.6E-2

b. 1986-1994 1.3E-2 c.1%5-1994(conbined) 1.4E-2 2.

St. Lucie 1&2:

NA NA NA Fire freq. and CDF rd quentified in "RE' 3.

Turkey Pt. 3&4:

NA NA NA Fire freq. and CDF not quantified in PRA' 4.

Quad Cities 1&2:

NA NA NA Fire freq. and CbF not quantified ir URA 5.

Cooper NA NA NA Fire freq. and CDF not "pantified in PRA.

6.

Point Beach 1&2:

5.0E-3 3.20 2.63 2.80 2.0E-5 Higher, but CDF still in E-% ranoe.

7.

Indian Pt. 2&3:

NA NA NA 5.6E-5 Fire freq. not quantified ir* CR5.

8.

Millstone 3:

NA NA NA Fire f req. and CDF not auantinen in prs.

9.

Diablo Canyon NA NA NA Fire freq, and CDF not quantified in 8'95.

10. Kewaunee (IPEEE):

1.8E-2 0.89

0. 72 0.78 Lower, but CDF not ouantified in IPEEE.

11. LaSalle 8.0E-3 2.00 1.62 1.75 1.4E-5 Higher, hit CDF still in t:-5 ranoe.

P

12. Seabrook:

a. PRA(PLG):

NA NA NA

b. FRSS (SNL):

NA NA NA

c. EPRI Requantif.:

NA NA NA

13. Peach Bottom:

a. PRA(1150):

2.7E-3 5.92 4.81 5.18 1.3E-5 Higher, CDF still in E-5 range.

b. EPRI Requantif.:

2.3E-3 6.96 5.65 6.09 1.3E-5 Higher, CDF still in E-5 range.

NOTE: See Figure 24.

F-10 i

I

vr APPElmlX F - IAM.E Ill (CXNITIFED)

PRA IllSIC41TS - CXBW%RISIMI OF PERER (FERATIONS FIRE FRESENCIES WITN SELECTED PLANTS PRA DATA - BY PLAIIT LOCATION Iteen Present LOCATION Fire Diff. Itutt.

Diff. Itutt.

Diff. leult.

Pt. Est.

rv ison Significance EEACTot EUILDING (BIR):

Frea.

W1965 86 is/1986-1996 W1%5-1996 Fira (BF with 1986-1996 Data I

t

1. This Study:

a. 1965-1985 7.7E-2

b. 1986-1994 5.4E-2 c.1965-1994(contined) 6.5E-2 2.

ound Cities 182:

NA NA NA Fire freq. and CDF not quantified in PRA.

3.

Cooper 4.8E-2 1.60 1.12 1.35 A mrox. same, but CDF not quantified in PRA.

t

4. LaSatte 4.9E-2 1.57 1.10 1.33

-3.8E-6 Approx. same.

5. Peach Bottom:

a. PRA(1150):

NA NA NA

b. EPRI Requantif.:

NA NA NA NOTES:

1.

The Reactor Ersilding is identified for BlRs plants enty in this study.

2.

See Figure 24.

1 L

}

F-11 t

.m.

APPElmiX F - 1ABLE III (CoullIRED)

PRA INSIGIITS - CDPARISGI OF PGER (FERATItEIS FIRE FREGERICIES WITH SELECTED PLAI:TS PRA DATA - SY PLAlli LOCATI0tt Mean Present LOCATICIt fire Diff. IIult.

Diff. IIutt.

Diff. Mult.

Pt. Est.

Casparison Significance AURILIARY SUILDIIIG (Plat):

Frea.

w/1965-1985 W1986-1994 W1%5-1794 Fire (DF with 1986-1994 Date

1. This Study:

a. 1965-1985 1.1E-1

b. 1986-1994 4.9E-2 c.1%5-1994(combined) 8.0E-2 2.

St. Lucie 1&2:

4.8E-2 2.29 1.02 1.67 Same, but CDF not quantified in PRA.

3.

Turkey Pt. 3*.4:

4.8E-2 2.29 1.02 1.67 Same, but CDF not quantified in PRA.

4.

Point Beach 1&2:

4.8E-2 2.29 1.02 1.67 Same, but CDF not quantified in PRA.

5.

Indian Pt. 2&3:

3.4E-2 3.24 1.44 2.35 Higher, but CDF not quantified in PRA.

6.

Millstor:e 3:

NA NA NA Fire freq. and CDF not quantified in PRA.

7.

Diablo Canyon NA NA NA Fire freq. and CDF not quantified in PRA.

8. Kewaunee (IPEEE):

7.3E-2 1.51 0.67 1.10 Lower, but CDF not quantified in IPEEE.

9. Seabrook:

a. PRA(PLG):

4.8E-2 2.29 1.02 1.67 Same, but CDF not quantified in PRA.

b. FRSS (SNL):

6.4E-2 1.72 0.76 1.25 2.9E-5 Lower, but CDF still in E-5 range.

c. EPRI Requantif.:

6.4E-2 1.72 0.76 1.25 4.3E-9 Lower, but not significant (still <E-6 range.

ilOTES:

1.

The Auxiliary Building is used for PWRs only in this study.

2.

See Figure 25.

F-12 w

- = - - - - - + -. - - - - - -

e m.

APPEIBIM F - TABLE III (CONTINUED)

PRA INSIGIITS - COIFARISGI Os Pouer Operations FtRE FREQUENCIES WITN SELECTED PLAllTS PRA DATA - SY PUET LOCATICII 91een Present LOCATIGI Fire Diff. Itutt.

Diff. Itutt.

Diff. feutt.

Pt. Est.

Comparison Sipitficance

_ TURBINE SUILDIilG:

Freo.

W1965-1985 W1986-1994 w/1%5-1994 Fire Q)F vith 1986-1994 Data

1. This Study:

a. 1965-1985 5.4E-2

b. 1986-1994 6.9E-2 c.1%5-1994(cordained) 6.1E-2 2.

St. Lucie 1&2:

1.6E-2 3.38 4.31 3.81 Higher, but CDF rot quantified in PRA.

3.

Turkey Pt. 3&4:

1.6E-2 3.38 4.31 3.81 Higher, but CDF not QJantified in PRA.

)

4.

Quad Cities 1&2:

NA NA NA Fire freq. and CDF not quantified in PRA.

i 5.

Cooper

'.62-2 3.38 4.31 3.81 Higher, but CDF not quantified in PRA.

i 6.

Point Beach 1&2:

1.6E-2 3.38 4.31 3.81 Higher, but CDF not qtrantified in PRA.

7.

Indian Pt. 2&3:

NA NA NA Fire freq. and CDF not quantified in PRA.

8.

Millstone 3:

NA NA NA Fire freq. and CDF not quantified in PRA.

9.

Diablo Canyon 1.3E-2 4.15 5.31 4.69 Hig%r, but CDF not quantified in PPA.

10. Kewaunee (IPEEE):

6.6E-2 0.82 1.04 0.92 Same, but CDF not quantified in IPEEE.

11. LaSalle 3.6E-2 1.50 1.92 1.69 6.2E-7 Higher, CDF now in E-6 range.

12. Seabrook:

a. PRA(PLG):

1.6E-2 3.38 4.31 3.81 Higher, but CDF not quantified in PRA.

b. FRSS (SNL):

6.4E-2 0.84 1.08 0.95 4.1E-5 Approximately the same.

c. EPRI Requantif.:

N*

4A NA

13. Peach Bottom:

a. PRA(1150):

NA NA NA

b. EPRI Requantif.:

NA NA NA r

NOTE: See Figure 25.

k F-13

m._

In APPENDIX F - TABLE IV C.SK INSIGHTS - EtBFARISON OF SELECTED PLANT FIRE PRA DATA WITH 1986-1994 PLANT OIPERATING EXPERIENCE PRA FIRE EDF tJSING STtBY FIRE PRA FIRE AREA RATIO A::EA RATIO SEVERITY PROB.

PROB.

FIRE STLBY FREGLENCY PLANT NMg_

FREQUENCY FR60.(A)

TO BLDG TO ROOM RATIO NONSUP. OTHER EDF SENSITIVITY ANAL.

LaSatte 2 control Room 2.6E-3 2.17E-3.

M NA NA 1.0E-1 Note 3 1.39E-5 1.66E-5 Cable Spreading Room 4.3E-3 6.48E-3 NA 1.5E-1 3Jt-1 9.9E-1 Note 3 1.63E-7 1.08E-7 Switchgear Room:

Fire Area W (Scenario 1) 1.3E-2 7.97E-7 NA NA NA 9.8E-1 Note 3 1.80E-6 Fire Area W (Scenario 2) 1.3E-2 7.97E-3 NA 1.8E-1 3.0E-1 9.8E-1 Note 3 6.71F-6 Fire Area Y (Scenario 1) 1.3E-2 7.97E-3 NA NA NA 9.5E-1 hote 3

1. ?6E - E i

Fire Area Y (Scenario 2) 1.3E-2 7.97E-3 NA 1.3E-1 3.0E-1 9.5E-1 Note 3

3. W -6 S4 total:

1.37E -5 2.23E 5 Reactor Bldg:

Fire Area P 5.4E-2 4.9E-2 6.0E-2 8.4E-1 3.0E-1 8.2E-1 Note 3 5.75E-7 Fire Area 2 5.4E-2 4.9E-2 8.2E-2 5.0E-3 3.0E-1 9.1E-1 Note 3 3.5RE-8 Fire Area AA 5.4E-2 4.9E-2 6.4E-2 8.0E-2 3.0E-1 9.3E-1 Note 3 7.3tE-9 i

Fire Area AC 5.4E-2 4.9E-2 1.6E-3 NA NA 9.9E-1 Note 3 5.RF 7 Firs Area S (Scenario 1) 5.4E-2 4.9E-2 2.8E-2 1.1E-1 3.0E-1 9.7E-1 Note 3 5.94E-9 Fire Area S (Scenario 2) 5.4E-2 4.9E-2 2.8E-2 1.1E-1 3.0E-1 9.7E-1 Note 3 3.52E-7 Fire Area T 5.4E-2 4.9E-2 6.6E-2 8.4E-1 3.0E-1 8.2E-1 kote 3 2.27E-6 S4 total:

3.79E-6 4.18E-6 Turbine 5tde:

fire Area E-52 6.9E-2 3.6E-2 3.8E-3 3.0E-1 1.7E-1 8.3E-1 Note 3 1.14E-7 Fire Area E-53 6.9E-2 3.6E-2 3.5E-3 3.0E-1 1.7E-1 8.3E-1 Note 3 5.06E-7 S4 total:

6.20E-7 1.19E-6 Totals:

3.2E-5 4.4E-6 W;ES:

1. Mtaber of Severity Groep A and B fire events, 1986-1994: 1 Category a fire event a 586.1 reactor years.

2. Data for ratios and nonstypressim probability are based on targe fires.

3. Data for random failures and other attributes are not included in this table.

F-14

.~ ~

W f

APPEIE)!X F - IABLE IV (CONIIIRED)

RISK INSIGHTS - CINFARISON OF SELECTED PLANT FIRE PRA DATA WITN 1986-1994 PLANT OPERATING EXPERIENCE PRA FIRE CDF USING STIEY FIRE PRA FIRE AREA RATIO AREA RAIIO SEVERITY PROB.

PROS.

FIRE STIEY FREQUENCY PLAllT IL4fE TREMENCY FREO.(A)

TO ELDG TO ROCM RATIO IIONSUP. OTNER Q)F SENSITIVITY ANfl.

Peachbottom PRA (NUREG 1150)

Control Room:

(Scenario 1) 2.6E-3 2.3E-3 NA 2.0E-2 hA NA Note 3 1.8E-6 (Scenario 2) 2.6E-3 2.3E-3 NA 0.8E-1 NA NA Note 3 4.4E-6 S 4 total:

6.2E-6 7.0E-6 Cable Spreading Roce 4.3E-3 3.5E-3 NA 6.2E-2 3.0E-1 8.7E-1 Note 3 6.7E-7 8.2E-7 Switdgear Room:

Sutchgr Rm 2A 1.3E-2 2.7E-3 NA 9.0E-1 NA 7.7E-1 Note 3 7.4E-7 Sutchgr Rm 23 1.3E-2 2.7E-3 NA 9.0E-1 NA 7.7E-1 Note 3 3.6E-6 Sutchgr Rm 2C 1.3E-2 2.7E-3

. NA 9.0E-1 NA 7.7E-1 Ncte 3 4.7E-7 Swtchgr Rm 2D 1.3E-2 2.7E-3 NA 9.0E-1 NA 7.7E-1 Note 3 7.4E-7 Sutchgr Rm 3A 1.3E-2 2.7E-3 NA 9.0E-1 NA 7.7E-1 Note 3 7.4E-7 Sutchgr Rm 38 1.3E 2 2.7E-3 NA 9.0E-1 NA 7.7E-1 Note 3 7.4E-7 Swtchgr Rm 3C 1.3E-2 2.7E-3 NA 9.0E-1 NA

7. ?7.' 1 Note 3 7.4E-7 Sutchgr Rm 3D 1.3E-2

2. 7E-3 NA 9.0E-1 NA 7,.h ' Note 3 8.1E-7 Sabtotal:

1.3E-5 6.2E-5 Reactor 8tdg:

NA (Not Siyiificant to the Fire PRA)

Turbine stdg:

IIA (Not Significant to the Fire PRA)

Totals:

(Q9 7.0E-5 N01ES:

1. Ntaber of Severity Groep A and 8 fire events, 1986-1994: 1 Category a fire ev M a 586.1 reacts.= gl %

2. Data for ratios ard nonstepression probability are based on targe fires.

3. Data for raruke failures and other attributes are not incitsfed in this table.

I i

F-15 e

t

. = - -

APPEWIX F - 1ABLE IV (CONTINUED)

RISK INSIGHT 3 - CINFARISON OF SELECTED PLANT FIPE PRA DATA WITH 1986-1994 PLANT OPERATING CXPERIENCE EPRI FIRE CDF USING STtBY FIRE PRA FIRE AREA RATIO AREA RATIO SEVERITY PROB.

PROB.

FIRE STimY FRE0llENCY PLANT MAfE FREMENCY FREQdd)

TO BtDG TO ROGE RATIO IKNISIP. OTNER E

SENSITIVITY ANAL.

Peachbottcm EPitI Rewantification Control Room:

(Scenario 1) 2.6E-3 1.32E-2 NA 1.45E-2 NA NA Note 4 4.4E-8 (Scenario 2) 2.6E-3 1.32E-2 NA 9.86E-1 NA NA Note 4 1.5E-7 Stbtotal:

1.9E-T 3.7E-b Cable Spreading Room 4.3E-3 7.5E-3 NA 1.3E-2 1.54-1 1

Note 4 2.2E-8 1.3E-8 Switchgear Room:

Sutchgr Rm 2A 1.3E-2 2.5E-3 NA

- No Recpanntification Performed -

Swtchgr Rm 2B 1.3E-2 2.3E-3 NA (See Note 3)

Swtchgr Rm 2C 1.3E-2 2.2E-3 NA Sutchgr Rm 2D 1.3E-2 2.2E-3 NA Sutchgr Rm 3A 1.3E-2 2.4E-3 NA Sutchgr Rm 3B 1.3E-2 2.3E-3 NA Sutchgr P-: 3C 1.3E-2 2.2E-3 NA Swtchg* Rm 3D-1.3E-2 2.0E-3 NA Sahtotal:

1.3E-2 2.3E-3(Ave.)

Note 4 1.3F-5 7.3E-5 Reactor 5tds:

- MA (Not Siytificant to the Fire PRA) -

Turbine 8tdg:

- NA (Not Significant to the Fire PRA) -

l Totals:

1.3E-5 7.3E-5 o

TOTES:

1. akader of Severity Grotp A and 5 fire events, 1986-1994: 1 Category B fire event a 586.1 reactor years.

2. Stbtotals for Switchgear Room are estimefed same as NUREG 1150 PRA. The use is intended for estimating total Fire (DF only.

3. Data for ratios and nornagpression probability are based on large fires.

4. Data for random failures and other attributes sre not incitated in this table.

i F-16

~

e APPElWlX F - TABLE IV (CONillRJED)

RISK IRSIGNTS - COW ARISON OF SELECTED PLAllT FIRE PRA DATA WITN 1986-1996 PLANT OPERATING EXPERIENCE PRA FIRE CDF USIIIG SttmY FIRE PRA FIRE AREA RATIO AREA RATIO SEVERITY PROB.

PROB.

FIRE SilmY FREQtEIICY PLANT MAIE FREMElICY FREG.(A )

TO BLDG TO RotBE RATIO IIONSLP. OTHER CDF SENSITIVITY AIBAL.

Seabrook PRA Control Room:

Zone C 2.6E-3 4.9E-3 NA 8.1E-3 WA NA Note 3 9.0E-6 Zone G 2.6E-3 4.9E-3 NA 8.1E-3 NA NA Note 3 2.1E-6 Zone H 2.6E-3 4.9E-3 NA 8.1E-3 NA NA Note 3 2.1E-6 Stbtotal:

1.3E-5 6.9E-6 Cable Spreading Room Seq. 2 4.3E-3 6.7E-3 NA 9.7E-2 2.7E-2 1.3E-1 Note 3 3.6E-6 Seq. 4 4.3E-3 6.7E-3 NA 4.85E-2 2.7E-2 1.3E-1 Note 3 3.9E-7 Seq. 6 4.3E-3 6.7E-3 NA 4.85E-2 2.7E-2 1.3E-1 Note 3 8.4E-8 Seq. 8 4.3E-3 6.7E-3 NA 4.85E-2 2.7E-2 1.3E 1 Note 3 4.5E-8 S4 total:

4.1E-6 2.6E-6 Switchgeer t

Room:

IIA (flot Significant to the Fire PRA)

Auxiliary stdg:

NA (Not Siytificant to the Fire PRA)

Turbine stde:

NA (Not Significant to the Fire PRA)

Totats:

1.7E-5 9.5E-6 IIOTES:

1. Ikaber of Severity Grotp A and B fire events, 1986-19M: 1 Category B fire event a 586.1 reactor years.

2. Data for ratios and nonstepression probability are based on tarse fires.

3. Data for random faittses ard other attributes are not included in this table.

1 F-17

APPEM)IX F - TABLE IV (CDNTilNAD)

RISK lilSIGHTS - C0fFARISDN OF SELECTED PLANT FIRE PRA DATA WITH 1986-1994 PLANT OPERATING EXPERIEstCE FRSS FIRE O F USING STLE)Y FIRE PRA FIRE AREA RATto AREA RATIO SEVERITY PROB.

PROB.

FIRE STimY FREQUENCY PLANT IIAfE FREMENCY FREO. (A )

TO BLDG TO R0[M RATIO NONSLP. OTER GF SENSITIVITY ANAL.

Seabrook Sul ReeaantificationtFRSS)

Control Room:

Zone C 2.6E-3 4.4E-3 NA 8.1E-3 NA NA Note 3 6.9E-6 Zone G 2.6E-3 4.t.E-3 NA 8.1E-3 NA NA Note 3 1.4E-6 Zone H 2.6E-3 4.4E*3 NA 8.1E-3 NA NA Nute 3 1.4E-6 Sibtotal:

9.7E-6 5.7E-6 Cable spreading Room:

Seq. 2 4.3E-3 2.7E-3 NA 9.7E-2

2. 7E-2 8.3E-1 Note 3 2.2E-6 Seq. 4 4.3E-3 2.7E-3 NA 4.8E-2 2.7E-2 8.3E-1 Note 3 1.0E-7 Seq. 6 4.3E-3 2.7E-3 NA 4.8E-2 2.7E-2 8.3E-1 Note 3 4.2E-8 Seq. 8 4.3E-3 2.7E-3 NA 4.8E-2 2.7E-2 C.3E-1 Note 3 3.1E-8

+

Sihtotal:

2.4E-6 3.8E-6 Switchgear Room:

KA (Not Significant to the Fire PRA Requentification - FRSS)

Auxiliary Bldg:

PCC Ptap Area 4.6E-2 6.4E-2 1.6E-1 1.3E-1 2.6E-2 8.3E-1 NA 2.9E-5 2.1E-5 Turbine 8tdg:

IIA (Not significant to the Fire PRA Requentification - FRSS)

Totats:

4.1E-5 3.1E-5 IIOTES:

1. Mtaber of Severity Group A and B fire events, 1986-1994: 1 Category B fire ever.ts a 586.1 reactor years.

2. Data for ratios and nonsigpression pr

• ability are based on targe fires.

3. Data for randam failures and other attributes are not inclialed in this table.

~

F-18 m

e w

APPEIBIX f - TABLE IV ((XNIIINLED)

RISK INSIGHTS - CE W ARISON OF SELECTED PLAllT FIRE PRA DATA WITH 1986-1994 PLANT OPERATIBIG EXPERIEIICE EPRI FIRE EDF USIIIG STtDY FIRE PRA FIRE AREA RATIO AREA RATIO SEVERITY PROB.

Ptos.

FIRE STimY FRE M 'eCY PLANT MApE FRE M IICT FREQ.(A)

TO SLDG TO ROENI RATIO IIENISEF. OTER CDF SENSITIVITY AIIAL.

Seabrook EPRI Recmaantification Control Room:

Zone C 2.6E-3 7.5E-3 NA 1.2E-2 NA NA Note 4 1.2E-6 Zone G 2.6E-3 7.5E-3 NA 1.2E-2 1

NA Note 4 4.6E-6 Zone H 2.6E-3 7.5E-3 NA 1.2E-2 NA NA Note 4 4.6E-6 Stbtotal:

1.0E-5 3.5E-6 Cable spreading Room:

Seq. 2 4.3E-3 2.8E-4 NA NA NA 3.0E-1 Note 4 4.3E-9 L

Seq. 4 4.3E-3 2.BE -i.

NA NA NA 2.9E-2 Note 4 7.6E-10 Seq. 6 4.3E-3 2.8E-4 NA NA NA 2.9E-2 Note 4 1.7E-10 Seq. 8 4.3E-3 2.8E-4 NA NA NA 2.9E-2 Note 4 8.8E-11 Stbtotat:

5.3E-9 8.1E-8 Sd tchgear Roosa:

1.3E-2 MA (Not Significant to the Fire PRA EPRI RecyJantification)

Auxiliary 5tdg:

PCC P g Area 4.9E-2 2.8E-4 1.45E-2 NA 1.54E-1 3.0E-2 Note 4 4.3E-9 7.1E-9 Turbine Bldg:

IIA (Not Significant to the Fire PRA EPRI RecyJantification)

Totats:

1.0E-5 3.6E-6 NOTES:

1. Isunber of severity Group A and B fire events, 1986-1994: 1 Category a fire event a 586.1 reactor years.

2. Data front EPRI Fire Recpantification Studies. The use is intended for estimating total Fire CDF only.

3. Data for ratios and nonstypression probability are based on targe fires.

4. Data for random failures and other attributes are not included in this table.

l h

f F-19

e l

l I

l i

APPENDIX G SHUTDOWN FIRE EVENTS - MEAN DURATION BY PLANT LOCATION

)

l l

l AND COMPARISON WITH POWER OPERATIONS FIRE EVENTS DURATION l

i l

[

l I

l l

l i

I l

l l

-. ~. - -

-. ~. - -.... ~..

. ~. ~. -. _. -...- -... -.

- - - -. -.- - ~. - _ - ~. -.

I I

a s

l l

I SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATION CONTAINMENT BUILDING - 1965 1985 REACTOR BLDG (BWR)- 1965 1985 Number of Fire Fvents Number of Fire Events 20 20 MEAN 4.7 men.

15 MEAN

~

l 21.5 min.

3 10 10 e

5 5

M k h 0

0

>5 1 1 22 3344 5566 778899

>5 1 1 2233445566 77 88 99 0<0505 050505050 50505 0<0505050505050505 05

< 1 <<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<< <<<<< <

50 1 223 34 4 55 6 6 7 7 a8 99 1 50 1 22334 4 5 56 6 7 78 89 9 1 50 5050 5050 50505050 5 050 50505050505050 0

0 Duretson Interv al (Mmutes)

Duration interval (Mmutes)

No, fire events dunng shutdown:22.

No. fire events during shutdown: 18.

SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATlON l

AUXILIARY BLDG (PWR)- 1965 1985 TURBINE BUILDING - 1965 1985 Number of F6te Events Number of Fire Events 20 20 l

15 15 I

gg 7.3 min.

MEAN 11.0 min.

10 10 t

i e

s i

0 0

>5 1 1 22334 4 5 5 6 6 778 8 99

>$ 1 1 22334 4 556677889 9 0<050505050505050505 0<050505050505050505

<1<<<<<<<<<<<<<<<<<<

<1 < <<<<<<<<<<<<<<<<<

50 122334 4 55 66 7 78 8 99 1 501 223344 5 566778 899 1 505050505050505050 505050505050505050 0

0 l

Duration interval (Minutes)

Duration interval (Minutes)

No..,e events un9 shutoown: n No. o,e events du,in, sh ida-a: "-

FIGURE 26 G-2 l

~.

l t

a M

i k

1 l

SHUTDOWN FIRE EVENTS OURATION SHUTDOWN FIRE EVENTS DURATION j

CONTROL ROOM - 1965 1989 CABLE SPREADING ROOM - 1965 1985 i

i Number of Fire Events Number of Fire Events 20 20 4

1

'MEAN MEAN 2.5 rrun-3.0 mm.

3 10 10 a

5 5

1 i

f2 ' ' ' ' '

g 0

l 0

>$ 1 1 223 344 5566 778899

>5 1 1 223344 5566778899 0<0505 05050505 050505 0<05 05 050505 05050505

< 1 < < << <<<<<<<<<<<<<<

j

< 1 <<<<<<<<<<<<<<<<<<

50 1 22 3344 5 56 6 7 78 8 99 1 1

50 1 22334 4556 6 7 7 8 8 99 1 505050505050505050 3

505050505 050505050 0

0 Duration Interval IMenutest 1

Duration le.terval (Minutes)

No. f; s events dunng shutdown: 1.

No. fire events dunng shutdown: 1 includes Browns Ferry Fire.

SHUTDOWN FIRE EVENTS DURATlON SHUTDOWN FIRE EVENTS DURATION SWITCHGEAR ROOM - 1965-1985 DIESEL GENERATOR BUILDING - 1965 1985 a

Number of Fire Events Number of Fire Events 20 20 MEAN 1

4.2 min.

15 15 MEAN

},

3.1 rrun.

f 10 10 i

5 5

i a

a a

a a

a a

a a

a a

a e

a a

e a

e a

a a

a e

a a

a e a 1

s a

e a

>5 1 1 223344556 6778899

>5 1 1 223344 5566778899 0<050505050505050505 0<050505050505050505 1<<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<<<<<<<<

50 1 22334 4 5566 77 8 899 1 501 2233445566 778899 1 505050505050505050 50505 0505050505050 0

0 Duration interval (Minutes!

Duretion intervel (Minutes)

No. fire events during shutdown. 8.

No, fire events during shi,tdown: 14.

FIGURE 27 G-3

m

..m.

.. ~ _.

~ _,

--.m

. _. ~... _

4 e

SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATIOff BATTERY ROOM - 1965 1985 OTHER BUILDINGS. 1965 1985 Number of Fire Events Number of Fire Events 20 20 15 15 MEAN 9.4 min.

l 1

10 10 NO SHUTDOWN FIRE EVENTS 5

5 0

0

>5 1 1 22 3 34 4 5 5 6 6 7 7 8 8 9 9

>51 1223344556677 8 8 9'9 0 < 0 5 0 5 0 50 5 0 50 5 0 5 0 5 0 5 0<050 5050 5 0505 050 50 5

< 1 < <<<<<<<<<<<.<<<<<<

< 1 <<<<<<<<<<<<<<<<<<

50 1 22 3 34 4 5 5 66 7 7 8 8 9 9 1 50 1 22 334 4 5 566 7 78 899 1 l

50 50 505 0 50 5 05 05050 505 0505 05 050505050 0

0 Duration interval (Minutes)

Duration intervsi (Minutes) l No. fire events during shutdown; 0.

No, nre events during shutdown: 4.

SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATION SERVICE WATER PUMPHOUSE - 1965 1985 SWITCH YARD - 1965 1985 Number of Fire Events Number of Fire Events 20 20 15 15 l

gg MEAN l

9.4 rrun.

2.5 rnen.

10 10 i

l I

5 5

,0,,..

,0....

l

>5 1 1 22334 4 55667788 99

>51 1 223344 5566778 899 l

0<0505050505 0505050 5 0<050 5 05050505050505

<1

< 1 <<< <<<<<<<<<<<<<<<

l 50 1 22334 4 5 566 7 78 8 99 1 501 22334 4 5 5 667 788 99 1 505050505050505050 5050505050e0505050 0

0 I

Duretson interval (Minutes)

Duretion Interval (Menutes)

No. Are events durtng shutdown: 1.

No. Are events dunng shutdown: 1.

FIGURE 28 G-4

s APPE W IM G - TABLE I SIRJTD0hAl FIRE EVENTS DURATION SY PLANT LOCATION - 1 % 5-1985 DLEATION (MINUTES)-

LOCATION

>0<5

_5 10 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 55<60 75<a0 95<100 TOTALS 1

Conteirament:

No. Fire Events:

7 3

1 1

5 1

2 2

22 Percent of Fire Events: 32 14 5

5 23 5

9 9

100 No. Fire Event-Min.:

17.5 15 10 15 106 30 80 200 4 73.5 Mean Duration (Min.):

21.5 REACTOR BUILDING:

No. Fire Events:

14 2

1 1

13 Percent of Fire Events: 78 11 6

6 100 No. Fire Event-Min.:

35 14 12 23 84 Mean Duration (Min.):

4.7 AUXILIARY BUILDING:

No. Fire Events:

10 1

2 13 Percent of Fire Events: 77 8

15

=

100 No. F ire Event-Min..

23.5 22 50 95.5 Mean Duration (Min.):

7.3 TURE!NE BUILDING:

No. Fire Events:

7 1

1 1

1 11 Percent of Fire Events: 64 9

9 9

9 100 No. F ire Event-Min..

17.5 10 15 33 45 120.5 t

Mean Duration (Min.):

11.0 Control Room:

No. Fire Events:

1 1

Percent of Fire Events: 100 100 No. Fire Event-Min.:

2.5 Mean Duration (Min.):

2.5 4

2.5 i

i 1

k G-5 m.

m

- a--

L.

-m r

APPEISIM G - TABLE I (tXNIIIIRJED)

SMUTD0bal FIRE EVENTS DURATION SY PLANT LOCATION - 1 % 5-1985 DURATION (NINUIES)

L_OCAflou

>0<5 3 5 10<t5 15<20 20<25 25(30 30<35 35<40, 40<45 45<50 50<55 55<60 75<80 95<109 TOTALS CABLE SPREADRIIG ROON:

No. Fire Events:

1 1

Percent of Fire Events: 100 300 No. Fire Event-Min. :

3 Mean Duration (Min.):

3 3.0 SWITCMGEAR R0(38:

No. Fire Events:

7 1

8 Percent of Fire Events: 88 12 100 No. Fire Event-Min.:

17 5 7.5 Mean Duration (Min.):

25 3,1 DIESEL GENERATOR SUltDilIG:

No. Fire Events:

12 1

1 14 i

Percent of Fire Events: 86 7

7 100 No. Fire Event-Min.:

30 7.5 22 59.5 Mean Duration (Min.):

4,2 Sattery Room:

No. Fire Events:

0 Percent of Fire Events: -

No. Fire Event-Min.-

Mean Duration (Min.):

0 OTIER RittDilIGS:

i No. Fire Events:

3 1

4 Percent of Fire Events: 75 25 100 No. Fire Event-Min.:

7.5 30 37,5 Mean Duration (Min.):

93 SERVI & lanTER PLSFMERISE:

No. Fire Events:

1 1

Percent of Fire Events:

100 100 No. Fire Event-Min.:

8 8

[

t Mean Duration (Min.):

8.0 I

G-6 f

I APPEWIX G - TABLE I (CONIIIRED)

SIRITDobal FIRE EVENTS DURATION SY PLANT LOCATION - 1965-1985 DIAtATION (MIIILITES) toCATicIt

>0<5

_5.11,0 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 55<60 75<80 95<100 TOTALS StilTCN YARD:

No. Fire Events:

1 1

Percent of Fire Events: 100 100 i

No. Fire Event Min.:

2.5 Mean Duration (Min.):

2.5 2.5 TEWORARY BLDGS:

No. Fire Events:

3 3

Percent of Fire Events: 100 100 No. Fire Event-Min.:

7.5 Mean Duration (Min.):

7.5

2.5 IIOTES

1.

The maximam duration of all fires used in this study uns 100 minutes.

2.

See Figures 26, 27, and 28 (imary 31 des not shoun on ptets).

?

f i

k G-7

4 e

SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATlON CONTAINMENT BUILDING - 1986 1994 REACTOR BUILDING - 1986-1994 Number of Fire Events Number of Fire Evs.its MEAN 31.3 rmn.

7 8

8 t

g MEAN 13.1 min.

6 6 h

'/)

4 4

3

'/

2 2

~

g h

000 E

.. f..l.

0 3.

... Id 0

0

> 5 1 1 223 34 4 556 67 7 8899

>5 1 1 223344 5566 77 8 899 0<050505 0505050505 05 0<0 505 0 50505 05050505

< 1 <<<<<<<<<<<<<<<<<<

<1 <<<<<<<<<<<<<<<<<<

50 1 22 334 4 556 6 7 78 8 9 9 1 50 1 2 2 3 34 4 5 566 7 7 8 899 1 5050505050 505050 50 50 50 505050 5050 50 50 0

0 Duration intervel (Mmutes)

Duration interval (Mmutes)

No. fire events during shutdown: 9.

No. fire events during shutdown: 14 l

SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATION AUYlLIARY BUILDING - 1986 1994 TURBINE BUILDING - 1980 1994 Number of Fire Eu.ts Number of Fire Events 10 10 8

8 MEAN MEAN 5.1 mm.

8,1 min.

6 6

7 3

4 k 4

I's s

n 2

h 2

r'

~

l 1 0

i i i i..... i.

i i i

0 0

>6 1 1 223344 556 6778 899

>5 1 1 22334 4 55067788 99 0<050605050505050 5 05 0<05 0505 050505050505

< 1<<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<<<<<<<<

50 1 223344 5 566 7 78 8 99 1 50 1 22334 4 5 566 7 78 8 9 9 1 5050 605050 50505 050 5050 5050505 0505050 0

0 Duration Interval (Mmutes)

Duretaan interval (Minutes)

No. hre events during shutdown: 8 No fire events dunng e%tdown: 5 FIGURE 29 G-8

i e

SHUTDOWN FIRE EVENTS DURATION SHU1DOWN FIRE EVENTS DURATION CONTROL ROOM. 1986 1994 CABLE SPREADING ROOM - 1986 1994 Number of Fire Events Number of Fire Events I

NO FIRE EVENTS NO FIRE EVENTS 0

0 j

>5 1 1 22334455667 7 8 899

> 5 1 1 22334 4 5 566 7 78 8 9 9 0<05050 5050505050505 0<050 5 05050 5 050 50 5 05

< 1 <<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<<< <<<<<

5C 1223344 5566 7 788 99 1 5 0 1 2233 4 4 5 5 6 6 7 7 8 89 9 1 505050505050505050 50 5 050505050 505050 0

0 Duration interval (Minutes)

Duration interval (Minutes)

No. fire events during shutdown: O.

No. fire events dunng shutdown. O SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATION SWITCHGEAR ROOM - 1986-1994 DIESEL GENERATOR BUILDING. 1986 1994 Number of Fire Events Number of Fere Events 10 10

. MEAN g

5.9 min.

MEAN 10.9 min.

6 6

4 4

s 2

2 h

0 0

>5 1 1 223344 5566 778899

>51 1 223344 5 566778899 0<050505050505050505 0<05 0505050505050505

<1 <<<<<<<<<<<<<<<<<<

< 1<<<<<<<<<<<<<<<<<<

501 223344 5566 778 8 99 1 50 1 2233445566 7 78 899 1 50505050505 0505050 50505050505050 5050 0

0 Duration interval (Minutes)

Duration intervel (Minutes)

No. fire events during shutdown: 5 No. Are events during shutdown: 9 FIGURE 30 G-9

...._..___-m_m

.m.....

.m b

t I

f L

SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATION BATTERY ROOM - 1986 1994 OTHER BUILDINGS - 1986 1994 I

Number of Fire Events Number of Fire Events 10 l

8 1

MEAN 6.2 min.

l 6

~

NO FIRE EVENTS l

2 7

0 0

>5 1 1 223 34 4 55 6 67 7 8 8 9 9

>51 122334 4 55657788 99 l

0<050 505050505050 5 05 0<050505050505050505

< 1 <<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<<<<<<<<

50 1 22 33 4 4 556 6 7 7 8 8 9 9 1 50 1 223344 5 5567 78 8 99 1 50 50505050505 050 5 0 505050505050505050 0

0 Duration interval (Mmutes)

Duration Interval (Minutes)

No, fire events during shutdown: O.

No. fire events during shutdown: 3 SHUTDOWN FIRE EVENTS DURATION SHUTDOWN FIRE EVENTS DURATION SERVICE WATER PUMPHOUSE. 1986 1994 SWITCH YARD - 198u 1994 Number of Fire Events Number of Fire Events 10 10 8

8 MEAN 18.6 min.

6 6

MEAN 2.5 min.

4 4

2 2

~

0 0

t. 5 1 1 223344 5566 7788 99

>5 1 1 2233445566778899 J<050505050505050505 0<050505050505050505

<1<<<<<<<<<<<<<<<<<<

< 1 <<<<<<<<<<<<<<<<<<

50 1 2233445566 77889 9 1 501 223344 55667788991 5050505050505050 50 505050505050505050 0

0 i

l l

Duration interval (Mmutes)

Duration Interval (Mmutes)

No fire events during shutdown: 1.

No. fire events during shutdown: 5.

FIGURE 31 a

\\

t G-10

APPEISIX G - TABLE il SNUTDonal FIRE EVENTS DURATION ET PLANT LOCATION - 1986-1994 DURATION (MIIIUTES)

LCCATICII

>0<5 5<10 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 55<60 75<80 95<100 TOTALS Contairment:

No. Fire Events:

2 1

1 1

2 1

1 9

i Percent of Fire Events:

22 11 11 11 22 11 11 100 No. Fire Event-Min.:

15.5 13 17 Mean Duration (Min.):

71 50 100 286.5 31.8 NEACTM BUILDING:

No. Fire Events:

8 2

1 1

1 14 Percent of Fire Events: 62 31 8

8 8

100 No. Fire Event-Min.:

20 15.5 25 30 97

~ 187.5 Mean Duration (Min.):

14.4 AUKILIARY EUILDIIIG:

No. Fire Events:

5 2

1 8

Percent of Fire Events: 62 25 13 100 No. Fire Event-Min.:

11 14.5 15 Mean Duration (Min.):

40.5 5.1 TIESIE ElILDIIIG:

No. Fire Events:

1 3

1 5

Percent of Fire Events:

20 60 20 100 No. Fire Event-Min.:

7.5 37 20 64.5 Mean Duration (Min.):

8.1 Control Room:

No. Fire Events:

O Percent of Fire Events: -

No. Fire Event-Min.:

Mean Duration (Min.):

0 1

G-11 i

^^

APPEWIX G - TABLE II (CONT!isuED)

SNUTDOWN FIRE EVENTS DURATION SY PLANT LOCATION - 1986-1994 DURATION (MINUIES)

LOCATION g

M 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 55<60 75<30 95<100 TOTALS CABLE SPREADING R0(Bt:

No. Fire Events:

0 Percent of Fire Events: -

No. Fire Event-Min.:

0 Mean Duration (Min.):

O SWITCMGEAR ROOM:

No. Fire Events:

3 1

1 5

Percent of Fire Events: 60 20 20 100 No. Fire Event-Min.:

7.5 7

15 29.5 Mean Duration (Min.):

5.9 DIESEL GENERAT(R BUILDING:

No. Fire Events:

1 5

1 1

1 9

Percent of Fire Events: 11 56 11 11 11 100 No. Fire Event-Min.:

2.5 37.5 10 21 27 98 Mean Duration (Min.):

10.9 Battery Room:

No. Fire Events:

0 Percent of Fire Events: -

No. Fire Event-Min.:

0 Mean Duration (Min.):

0 OTIER EllLDINGS:

No. Fire Events:

2 1

3 Percent of Fire Events: 67 33 100 No. Fire Event-Min.:

3.5 15 18.5 Mean Duration (Min.):

6.2 SERVICE WTER PtBFNOUSE:

No. Fire Events:

1 1

Percent of Fire Events: 100 100 No. Fire Event-Min.:

2.5 2.5 Mean Duration (Min.):

2.5 G-12

= --

APPEleIX G - TABLE II (CONTINUED)

SMUTDonal FINE EVENTS DURATION SY PLANT LOCATION - 1996-1994 DLRATION (MIINJTES)

LOCATION

>0<5 5510 10<15 15<20 20<25 25<30 30<35 35<40 40<45 45<50 50<55 15_<60 75<80 95<100 TOTALS SUITCN YARD:

5 No. Fire Events:

1 3

1 5

Percent of Fire Events: 20 60 20 100 No. Fire Event-Min.:

2.5 22.5 68 93 Ave. Duration (Min.):

18.6 OFFSITE:

i No. Fire Events:

1 1

2 i

Percent of Five Events:

50 50 100 No. Fire Event-Miri.:

64 100 164

[

Ave. Duration (Min.):

82.0 1

NOTES:

1.

The maximan duration of att fires used in this study suas 100 airutes.

k 2.

See Figures 29, 30, and 31.

e p

h t

i i

r G-13

,~

+.-

-.... ~

-~

e a

i APPEN0lX G - TABLE Ill MEAN DURATION C00 PARIS 0N BETWEEN SHUTDOWN AND POWER OPERATIONS FIRE EVENTS 8v PLANT LOCATION - 1 % 5-1985 I

PLANT ShuiDOW MEAN POWER OPER. MEAN COFARISON/W LOCATION DURATION (NIN.)

DURATION (NIN.)

POWER OPER.

Contairunent 21.5 5.6 Higher

• Reactor Bldg (BWR) 4.7 15.3 Lower 1

Auxiliary Bldg (PWR) 7.3 8,6 Approx. same Turbine Bldg 11.0 18.3 Lower Control Room 2.5 2.5 Same

)

Cbt Spreading Rm 3.0 52.7**

Lower Switchgear Room 3.1 17.4 Lower

{

Diesel Gen. Bldg 4.2 6.4 Approx. same i

Battery Room 0

2.5 Approx. same i

Other Bldgs 9.4 12.6 Approx. same Serv Wtr Pumphse 9.4 2.5 Approx. same i

Switch yard 2.5 19.3 Lower NOTES:

1.

• Denotes the pre &minant cause was welding sparks / arcing during shutdown operations.

2.

• • Includes Broms Ferry fire, but & ration limited to 100 minutes for this & ration evaluation.

{

3.

See Figures 13,14, and 15 for Power Operations dJrations and Figures 26, 27, aruf 28 for Shutdown

& rations.

a G-14

~.

e o

i APPENDIX G - TABLE IV NEAN DURATION COMPARISON BETWEN SMUTDOW AND POWER OPERATIONS 87 PLANT LOCATION - 1966-1994 PLANT SMUTDOW EAN POER OPER. E AN CEDFMt! SON /W LOCATION DURATION (NIN.)

DURATION (NIN.)

POE R OPft.

Contairrnent 31.3 18.2 Higher

• Reactor P Mg (BWR) 13.1 14.8 Approx. same Auxiliary Bldg (PWR) 5.1 9.2 Approx. same i

Tueat.e aldg 8.1 22.1 Lower d

control Room 0

2.0 Approx. same (no shutdown events)

Cbt 5-reading Rm 0

13.8 Lower (no shutdown events)

Switchgear Room 5.9 28.2 Lower 1

Diesel Gen. Bldg 10.9 6.6 Approx. same Battery Room 0

0 Same tw events)

Other Bldgs 6.2 50.9 Lower Serv V. Pt,mphse 2.5 4.8 Approx. same Switch Yard 18.6 23.3 Lower NOTES:

1.

• Denotes the predominant cause was welding sparks / arcing & ring shutdown operations.

2.

See Figures 16, !T,1nd 18 for Power Operations & rations arid Figures 29, 30, and 31 for Shutdown durations.

4 I

I G-15 i

1 i

t

_. ~ - -.

4 0

)

4

\\

h i

APPENDIX H l

SHUTDOWN FIRE EVENTS j

SHUTDOWN AVERAGE FIRE FREQUENCY BY LOCATION AND COMPARISON WITH POWER OPERATIONS AVERAGE FIRE FREQUENCIES-

\\

l l

=

0 0

l APWlO!X H TABLE I SHUTD0bal FIRE EVENTS - AVERAGE FIRE FREQUENCIES BY PLANT LOCAT10N - 1%5-1985 AIO C0MPARISON WITH POLER OPERAi!ONS AVERAGE FIRE FREQUENCIES PLANT SHUiDN F!r! EVENTS POWER OPERATIONS COW ARISON/W N0 AVE. FRfQ.

poler OPER.

0

{pCATION NO AVE. FREQ.

3 2

Containment 22 8.5E 2 6

1.1E 2 Higher

• Reactor Bldg (BWR) 18 1.8E-1 17

7. /E -2 Higher **

Auxiliary Eldg (PWR) 13 8.3E-2 40 1.1E-1 Lower Turbine Bids 11 2.0E-2 31 5.4E-2 Lower i

control doom 1

2.6E-3 3

6.0E 3 Lomar Cbl Spre.eding Rm 1

2.6E-3 3

6.0E-3 Lower Switchgear Room 8

1.4E-2 9

1.6E-2 Approx. same Diesel Gen. Bldg 14 2.5E 2 37 6.4E 2 Lower Battery Room 0

8.5E 4 3

6.0E-3 Lower i

Other Bldgs 4

7.7E 3 25 4.4E-2 Lower Serv Wtr Pumphse 1

2.6E 3 2

4.2E 3 Lower Switch Yard 1

2.6E-3 15 2.6E-2 Lower Offsite 0

8.5E 4 4

7.7E-3 Lower Temporary Bldgs 3

4 Not conpared NOTES:

1.

Preoperational Testing fire events were excitajed.

2.

Ave. Overall Plt Oper.-Yrs (850.4) - Ave. Pit Power Oper. React.-Yrs (585.1) = Ave. Plt Sht&-Yrs (265.3),

s.

Reactor Blde (enst) Ave. Plt shutWi-Yrs =

328.5-226.0 = 102.5.

b.

Auxiliary Bldg (PWR) Ave. Plt Shut &-Yrs = 521.9-359.1 = 162.8.

3.

Shuth Fire Freq. = No. Shth Fire Events / Ave. Plt Sht&-Yrs. Bayes mean is shows, with Jef ferys noninfonastive prior used.

4.

%enotes predaninant cause was welding sparks / arcing during shutdown.

5.

• • senotes variety of cases, including welding sparks, electrical failure, and overheated material.

6.

Number of Power operations fire events, 1 %5-1985: 199.

7.

Number of Shutdow) fire events, 1986-1994: 97.

H-2

9 s

I APPEIE)!X X - TABLE !!

SHlfTD0bal FIRE EVENTS - AVERAGE FIRE FREQUENCIES BY PLANT LOCATION - 1966-1994 Alm CCSFARISON WIYH POLER OPERATIONS AVERAGE FIRE FREQUENCIES s

PUUli SHUTDN FIRE EVENTS POWER OPERATIONS COMPARISON /W LOCATION

_NO AVE. FREQ.

NO.

AVE. FREQ.

POLER OPER.

i 2

Containment 12 5.4E 2 5

9.4F. 3 Higher

• 1 Reactor Bldg (BWR) 16 1.8E 1 12 5.4F-2 Higher" Auxiliary Bldg (PWR) 14 1.0E-1 16 4.6E-2 Higher **

Turbine Bldg 9

4.1E 2 40 6.9E-2 Lower Control Room 0

2.2E 3 1

2.6E-3 Approx. same (no shutdown events)

Cbt Spreading Rm 0

2.2E 3 2

4.3E-3 Lower Switchgear Room 8

3.7E 2 7

1.3E 2 Higher **

Diesel Gen. Bldg 14 6.3E-2 16 2.8E-2 Higher ***

Battery Room 0

2.2E 3 0

8.5E 4 Approx, same (no events)

Other Bldgs 6

2.8E-2 10 1.8E-2 Approx. came Serv Wtr Punphse 1

6.5E 3 6

1.1E-2 Lower Switch Yard 8

3.7E 2 17 3.0E-2 Approx. same Offsite T

1.1E 2 10 1.8E 2 Approx. same J

NOTES:

1.

Ave. Overall Plt oper.-Yrs (816.3) - Ave. Plt Power Oper. React.-Yrs (586.1) = Ave. Plt Sht&-Yrs (230.2).

a.

Reactor Blde (BWR) Ave. Plt Shut h-Yrs

= 300.5 230.1 = 90.4.

b.

Auxiliary Blds (PWR) Ave. Plt Shutdn-Yrs = 495.8-356.0 = 139.8.

2.

Shuth Fire Freq. = No. Shth Fire Events / Ave. Plt Sht&-Yrs. Bayes mean shown, with jefferys 4

noninformative prior taed.

3.

• Deretsa predcminant cause was welding sparks / arcing & ring shutdown.

4.

• • Denotes predominant cause was electrical failure & ring shutdoest.

5.

• • • Denotes predomin e t cause was overheating material & ring shutdown testing of the Emergency Diesel-Generator.

6.

Number of Power Operations fire events, 1966-1994: 142 (includes 30 extrapolated fire events).

i 7.

Number of Shutdono fire events, 1966-1994: 90 (incitales 30 extrapolated fire events).

Y l

i H-3 i

1 l

i

_ _ ~

I 1

e o

I l

APPENDIX H - TABLE 111 i

SHUTDOWN FIRE EVENTS - AVERAGE FIRE FREQUENCIES SY PLANT LOCATION - 1%51994 (COMBIMED)

AND COMPARISON WITH POWER OPERATIONS AVERAGE FIRE FREQUENCIES PLANT SHUTDN FIRE EVENTS POWR OPER.

COMPARISON /W LOCATION

!!O,,

AVE. FR R AVE. FREQ.

POWER OPER.

Containment 34 7.0E 2 11 9.8E 3 Higher

• Reactor B!dg (BWR) 34 1.8E 1 29 6.5E-2 Higher **

Auxiliary Bldg (PWR) 27 9.1E-2 56 7.9E 2 Approx. same Turbine Blds 20 4.1E 2 71 6.1E-2 Lower Control Room 1

3.0E-3 4

3.8E-3 Approx. same Cbl Spreading Rm 1

3.0E-3 5

4. 7E -3 Approx. same Switchgear Room 16 3.3E 2 16 1.4E-2 Higher **

Diesel Gen. Blds 28 5.8E-2 53 4.6E 2 Approx. same Battery Room 0

1.0E-3 3

3.0E-3 Lower other Bldas 10 2.1E 2 35 3.0E-2 Approx. same Serv Wtr Pumphse 2

5.0E-3 8

7.2E-3 Approx. same Switch Yard 9

1.9E 2 32 2.8E-2 Approx. same Offsite 2

5.0E 3 14 1.2E 2 Lower Temporary Bldgs 3

4 Not compared NOTES:

1.

Preoperational Testing fire events were excluded.

2.

Ave. Overall Plt Oper.-Yrs (1666.7) - Ave. Plt Power Oper. React.-Yrs (1171.2) = Ave. Plt Sht&-Yrs (495.5).

a.

Reactor Bldg (BWR) Ave. Plt Sht & -yrs = 649-456.1 9 192.7.

b.

Auxiliary Bldg (PWR) Ave. Fit Sht&-yrs = 1017.7-715.1 = 302.6.

3.

Shuth Fire Freq. = No. Shth Fire Events / Ave. f lt Shtr& Yrs. Bayes mean showi, with Jefferys runinformative prior used.

4.

• Denotes predominant cause was welding sparks / arcing & ring shutdone.

5.

" Denotes predominant cause was electrical failure &rire shutdown.

d.

Muuber of Power Operations fire events, 1 % 5-1994: 341 (including 30 extrapoplated fire events for 1987-1994 period at 5 per year).

7.

Number of Stutdowi fire events, 1 %5-1994: 187 (including 30 extrapoplated fire events for 1989-1994 period at 5 per p ar) i H-4

i e

i i

i i

t

)

i i

i 4

d s

4 i.

i t

1 i

APPENDIX J t

4

)

REPORTED SMOKE EVENTS DATA i

}

FROM LERs AND COMPONENT FAILURE HISTORIES

}

1

?.

.. =. _ _ _

_m

.. _ _ ~ _ _ _.

._.._._._m 6

e SMOKE EVENTS DENSITY SMOKE EVENTS DENSITY 1965 1985 Period 1986-1994 Period s//Y' ~

A. lll l'9"t g g' 89%

e tv la dunne the pened A Sawke Events 294 SMOKE EVENTS DENSITY 1965-1994 Period p/

Medium 8%

_a HEAVY 1%

Ught 91 %

FIGURE 32 No. Total smoke Events: 389 huePF J-2

6 I

4 l

l SMOKE EVENTS CAUSES SMOVE EVENTS CAUSES 1965 1985 Period 1986 1994 Period l

l

\\

ElICT 8 41 ELict sat OTHE R 31 %

ovgest Matt

% Smeto f venes 95 feo Smete lvents 294 l

SMOKE EVENTS CAUSES 1965-1994 Period ELECT. Fall.

66%

/

///

'%N OTHER

N

/, '

OVERHT MATL 31 %

No. Total Senoke Events: 389 J-2

~ _. - ~ _.. - _. - _. _

e e

d 4

1 l

SMOKE EVENTS LOCATION SMOKE EVENTS LOCATION i

j 1965 1985 Period 1986-1994 Period i.

'U ' 8

1. U " k OO'"* *'

5 O THE R b

1)

/

I

/

y Tuns St.DG I

4%

RE ACBtDG<6 WR)

O THE n

$W PA pH5E fungstog RE AC79tDGiaWR

ONfL Ru SW PHSE i

CONTL RM 13 oc stoG 2%

13%

4 No Smoke Events 95 No Smoke Events 294

% " 1~." A'.', 2,".*2,,'e"""""

%*1".'fP '="*t.*"47""

SMOKE EVENTS LOCATION 1965-1994 Period 1

i 4

i 1

1 AUX BLDG (PWR) 44 %

/[

/

OTHER 4%

/)

\\s N

E

/ TURB BLDG REACTBLOG(BWR) 17%

13%

CONTL RPs SW PMPHSE 3%

i DG BLDG 13%

No. Smoke Events: 389 J-4

.. _. _ -. ~ _ -. - -

e i

i APPEISIX J - TABLE I SNOKE EVENTS DATA - 01/01/65 - 12/31/85 ITEM DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

C(BF.

TRAIN P0hER g

PtT ID OTNER DATE TIME PLY AREA SNEE DUR NODE SYS SMOKE 9EANS CCBIP.

C(BS.

EFFECT EFFECT EffECT l

1 22 Conp.

12/08/74 --

Reactor Light

<20 Power LPCS Elect. Motor Cont.

Motor Cont.

LPCS None f

Fait.

Building min.

Oper.

Fail.

Overld Isol Ooer.

Isol.

Hist.

Alarm Valve Intern. Valve 2

10 Comp.

05/17/75 --

Auxiliary Light

<20 Power DC Pwr Elect. Visuet Batt.

Xiormr Batt.

None None Fait.

Building min.

Oper.

Distr.

Fail.

Chgr Windngs Chgr i

Hist.

Xformr 3

53 Conp.

11/09/74 --

Reactor Light

<5 0%

HPCI Elect. Visual Turb.

Motor Turb.

None None-Fait.

Building min.

Power Fail.

Steam Oper.

Steam 0% Pwr l

Hist.

Supply Intern. Supply Valve Valve 4

46 Comp.

04/06/78 0930 Auxiliary Light

<20 0%

AFW Elect. Visual Flow Motor Flow None None-Fait.

Building min.

Power Fail.

Conti Limit Contt 0% Pwr Hist.

Valve Switch Valve

[

5 7

Conp.

10/24/78 1040 Reactor Light

<5 Power SLC Over6:t Visual SBLC Pump SBLC

$CLC(1) None Fail.

Building min.

Oper.

Matt Pmp Packing Pump Hist.

E 6

60 Conp.

01/05/79 2315 Auxiliary Light (20 0%

Instr Elect. Visual Power Capac. Power None None-Fail.

Building min.

Power AC Pur Fail.

Supply Supply 0% Pwr l

Hist.

Distr Invertr Invertr 5

7 60 Comp.

03/27/79 0815 Auxitiary Light

<20 Power Instr Elect. Visual Power Capac. Power Instr None Fail.

Building min.

Oper.

AC Pwr Fait.

Supply Supply AC Pwr Hist.

Disti Invertr Invertr Distr (1) 8 19 ccm.

08/04/79 --

Auxiliary Light

<23 Power Instr Elect. Visual Power Diode Power Instr None Fait.

Building min.

Oper.

AC Pwr Fail.

Surply Supply AC Pwr Hist.

i Distr Invertr Invertr Distr (1)

[

9 65 Comp.

12/07/79 1618 Service Wtr Medium <30 0%

Plt Elect. Visual Strainr Circuit Strainr None None-f i

Fait.

Pumphouse min.

Power AC Pwr fait.

Circuit Breaker Circuit 0% Pwr Hist.

(

Distr Breaker Intern. Breaker 10 31 Comp.

12/20/79 1800 puxiliary Light

<20 Power Cont.

Elect. Visual Cont.

Circuit cont.

Cont.

None Fail.

Building min.

Oper.

Fan Fail.

Fan Breaker Fan Fan Hist.

l Cooling Cooling Contac. Cooling Cool (1) i Circ Brkr Circ Brkr i

L J-6 l

r L

h

- -. - -- + - - - - -

i

?

APPEMDIM J - TABLE !

SHOKE EVENTS DATA - 01/01/65 - 12/31/85 ITEfe DET/

8ER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

FLT CAUSE DETECT INIT.

INIT.

CINF.

TRAIN PUdLR Ng PET ID OtKR DJA Tl8E PLT AREA SBEECE OUR INBE SYS SNOKE E_ANS CINF.

CGW.

EFFECT EFFECT EFFECT L

11 42 Comp.

07/07/80 --

Auxiliary Light

<10 100%

RPS Elect. Visual Power R?tay Peswer None None Fait.

Building min.

Power Fail.

Range Coit Range Hist.

Block Block Relay Relay l

12 49 Comp.

08/20/80 1530 hamiliary Light

<20 Power CVCS Elect. Visual Charg Circuit Charg CVCS(1) None Fail.

suilding min.

Oper.

Fail.

P.ig Breaker Purp Hist.

Circuit Close Circuit dreaker Coit Breaker 13 65 Comp.

10/02/80 0625 Auxiliary Light

<5 0%

cont Elect. Visual cont.

Motor Cant.

None None-Fait.

Building min.

Power Isol.

Fait.

Isol.

Oper.

I r.o t.

0% Pwr Hist.

Valve Intern. Valve 14 41 CLw.

10/29/80 0800 Auxiliary

' Light

<20 0%

CVCS Overht Visual Charg Vari-Charg None None-Fait.

Building min.

Power Matt.

Punp Drive Pump ~

0% Pwr Hist.

Vari-Intern.

Orive 15 60 Com.

12/04/80 1400 Service Wtr Light

<10 0%

NSW Elect. Visual Tenp.

Motor Temp.

None None-Fain.

Pumphouse min.

Power Fail.

Contt Oper.

Contt 0% Pwr I

Hist.

Valve LS Valve 16 60 Comp.

01/18/81 0100 Auxiliary Light

<10 Power Cont!

Elect. Visual MG Set Circuit MG Set CRD(1) None Fait.

Building min.

Oper.

Rod Fait.

Circuit Breaker Circuit Hist.

Drive Breaker Resistr Breaker 17 16 Comp.

02/02/81 2207 Auxitiary Light

<20 0%

AFW Elect. Visual Closing Circuit Closing None None-Fain.

Butiding min.

Power Fai(.

Xformr Breaker Xformr 0% Pwr Hist.

CB Contac. Circ Brkr 18 65 Comp.

07/13/81 --

Auxiliary Light

<10 0%

Contt Elect. Visual Motor Coit Motor None None-Fait.

Building min.

Power Rod Fail.

Contt Contt 0% Pwr Hist.

Drive Panet Panet i

19 8

Copp.

11/19/81 0200 Auxiliary Light

<5 0%

HPS!

Elect. Visual MPSI Motor HPS!

None None-Fait.

Building min Power Fait.

Punp Intern. Pump Cold Hist.

Motor Motor Shurdn

[

20 16 Comp.

04/10/82 0630 Service Wtr Light

<5 0%

NSW Elect. Visual ServWtr Punp ServWtr None None-Fait.

Ptmphouse min.

Power Fait.

Booster Packing Booster 0% Pwr Hist.

Punp Ptsp

[

J-6 i

L

w.

u.-.-

. +. ~.. -.. -.. ~.. ~ -. _. ~. -...

..a

+

I f

APPEIO!X J - TABLE I 910KE EVENTS DATA - 01/01/65 - 12/31/85 t

ITEBI DET/

LER/

EVENT REPORT LOCATI(31 EXTEIIT EST.

(PER.

PLT CAUSE DETECT INIT.

INIT.

CIN.

TRAIN PIRER g

Pti ID OTIIER DATE TIIE PLT ARE_A SIEEE DA B_EBE 3$

SIME MARIS Ct M.

_CTJIG FFFECT EFFECT EFFECT 2

21 12 Corp.

05/19/82 1905 Dieset Gen.

Medium <30 Power EDG Overht visual DG Coot Motor DG Coot EDG(1) N:me Fait.

Butiding min.

Oper.

Matt Wtr Pmp Bearng Wtr Pmp Hist.

Motor Oil Motor 1

22 75 Corrp.

06/21/82 1552 Auxiliary Light

<20 Power CCW overht visual CCW Motor CCW CCW(1) None f

Fait.

Buildir,

min.

Oper.

Matt Pump Bearng Punp Hist.

Motor Oil Motor i

23 313 82-15 07/13/82 --

Diesel Gen.

nediun <30 Power EDG Overht

',moke Day ink fuel Day EDG(1) None Building min.

Oper.

Matt Detect. Limit Oil Tank Switch I

24 52 Comp.

07/26/82 0830 Dieset Gen.

Light

<5 Power EDG Elect. Visual DG Relay DG EDG(1) None Fait.

Building min.

Oper.

Fait.

Contt Switch Cont!

Hist.

Panet Panet i

25 416 82-70 09/07/82 --

Offsite Mediun <30 Power NSW Of fsite Smoke Offsite --

None i

(Burn Pit) min.

Oper.

Burn Detect.

Combst Pit Matt I

26 8

Comp.

11/02/82 1020 Auxiliary Light

<20 0%

RHR Overht fire RMR Pump RHR RHR(1)

None-Fai1.

Buitding min.

Potrer Matt A(arm Punp Bearng Pung 0% Pwr Hist.

27 31 Comp.

12/15/82 1500 Auxitiary Light

<5 0%

RCS overht visual RCP Circuit RCP None None-Fait.

Buildig (Smoke min.

Power Matt Circuit Breaker Circuit 0% Pwr Hist.

Residue)

Breaker Intern. Breaker 28 8

Comp.

03/08/83 1130 Auxiliary Light

<5 Power AFW Overht Visual Turbine Pump Turbine AFW(1) None l

Fait.

Building min.

Oper.

Matt Driven Packing Driven Hist.

Purip Matt Pump 29 29 Comp.

04/06/83 1941 Auxiliary Light

<20 Power Instr Elect. Fire Power Invertr Power None None

[

Fail.

Building min.

Oper.

AC Pwr Fait.

Alarm Supply Diodes Supply Hist.

Distr Invertr Invertr t

33 64 Comp.

04/13/83 2000 Auxiliary Light

<20 0%

RCS Elect. Vi=uat 600v Circuit 600V None None-Fail.

Building (Smoke min.

Power Fall.

Load Breaker Load 0% Pwr Hist.

Smell) t Center Close Center y

CB Coit CB l

J-7 h

f l

__,___.m.

"" ^' " -" ~

APPEIWlX J - IABLE I SMOKE EVENTS DATA - 01/01/65 - 12/31/85 t

31 0

~ DKT/

LER/

EVENT REPORT LOCATION EXTEN!

EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

CIDF.

TRAIN PohER ITEM PLT 10 OTNER DJA TieEE PLT AREA SIIOKE DUR E

SYS ME BEANS CIBF.

CGS.

EFFECT.EFFECT EFFECT I

31 16 Comp.

04/24/83 0710 Service Wtr Light

<5 Power NSW Overht Visual ServWtr Pung SerWtr None None-Fail.

Punphouse min.

Oper.

Matt Booster Bearing Booster 0% Pwr Hist.

Pwp Oil Pump 32 52 Comp.

05/26/83 1120

!!cactor Light

<5 0%

RHR Elect. Visual RHR wmitr RHR RHR(1)

None-

[

Fail.

Building min.

Power Fail.

Flow Intern. Flow 0% Pwr Hist.

Xmitr Xmitr 33 53 Comp.

06/01/83 --

Reacter Light

<5 0%

RCIC Overht Visual RCIC Pung CCW None None-Fait.

Building min.

Power Matt Punp Seats-Pump 0% Pwr

{

Hist.

I 34 25 Conp.

08/24/83 --

Reactor Light

<20 0%

RPS Elect. Visual Reactor Relay Reactor None None-Fait.

Building min.

Power Fail.

Lolo Intern. Loto 0% Pwr

(

Hist.

Scram Scram 5

Relay Relay f

35 8

Comp.

09/14/83 1008 Auxiliary Light

<20 100%

Contt Elect. Visual CRD MG Set CRD CRD(1) kone l

Fait.

Building min.

Power Rod Fail.

MG Bearing MG Hist.

Drive Set Set l

36 3

Conp.

09/20/83 --

Reactor Light

<20 0%

RPS Elect. Visual High Relay High None None-Fail.

Building min.

Power Fait.

Drywell Intern. Drywell 0% Pwr l

Hist.

- Press.

Press.

Relay Relay f

37 1

Comp.

09/25/83 1740 Auxiliary Light

<5 Power ESFAS Elect. Visual Segncr Cape. Seqncr ESTAS None Fail.

Building (Smoke min.

Oper.

Fait.

Power Power (1) i Hist.

Residue)

Supply Supply I

38 30 Comp.

10/13/83 0745 Auxiliary Light

<20 100%

DC Elect.

Fire Battery Xformr Battery DC Pwr None j

Fail.

Building ein.

Power Power Fait.

Alarm Charger Intern. Charger (1)

Hist.

Distr Xforer Xformr 39 80 Comp.

09/14/83 0545 Dieset Gen.

Medium <20 0%

EDG Overht Visual DG Eng DG EDG(1)

None-Fait.

Building (Room min.

Power Matt Engine Fuel Engine 0% Pwr Hist.

Filled)

Cylndr Oil Cylnd.

40 53 Conp.

01/16/84 0245 Service Wtr Light

<20 0%

ESW Overht Visual RHR SW Punp RHR SW None None-f Fail.

Pumphouse min.

Power Matt Booster Bearing Booster 0% Pwr Hist.

Pump Oil Punp i

I t

J-8 l

i i

i 1 -

r

--4 o

i i

e APPENDIX J - TABLE I SNOKE EVENTS DATA - 01/01/65 - 12/31/85

[

ITEM DKT/-

LER/

EVENT REPGti LOCATION EXTENT EST.

OPER.

PLT CAllSE DETECT INIT.

INIT.

COMP.

TRAIN P0hEk E

PLT ID OTNER D_AJE M

PLT AREA SINEE DUR M_(B_E_

S15 SMOKE SEANS CEMP.

CGS.

EFFECT EFFECT EFFECT A

41 8

Comp.

01/17/84 0300 Service Wir Light

<20 Power NSW Tlect. Visual ServWtr Motor ServWtr NSW(1) None Fait.

Pimphouse (Smoke min.

Oper.

Fail.

Pupp Intern. Punp Hist.

Smett)

Motor Motor 4

42 13 Conp.

01/31/84 0536 Auxiliary Light

<20 0%

RPS Elect. Cont Hi Cont Hi pelay Cont Hi None None-1 Fait.

Building min.-

Power Fait.

Press. Press. Coit Press.

0% Pwr Hist.

Alarm Relay Relay 43 73 Comp.

01/31/84 --

Reactor Light

<5 0%

ESW Elect. Visual DG SW Motor DG SW None None-Fait.

Building min.

Power Fait.

Isol Oper.

Isol 0% Pwr Hist.

Valve Intern. Valve 44 10 Conp.

02/21/84 0930 Auxiliary Light

<5 0%

AFW Elect. Visual Trip Sol.

Trip None None-Fait.

Building min.

Power Fail.

Thrott Coit Thrott Cold Hist.

Valve Valve Shutdn 45 34 Comp.

03/18/84 1530 Reactor Light

<20 0%

RPS Elect. Visual Neutron Relay Neutron None None-Fait.

Building min.

Power fait.

Monit. Coil Monit.

Refuel.

Hist.

Relay Relay 46 8

Conp.

04/11/84 1000 Diesel Gen.

Medium

<30 Power EDG Overht Visual DG Fuel DG EDG(1) None Fail.

Building min.

Oper.

Matt Engine Oil.

Engine j

Hist.

5 P

(7 75 Conp.

04/15/84 --

Auxiliary Light

<5 0%

Ice Elect. Visual Glycol Motor Glycot None None-Fail.

Building min.

Power Cond.

Fait.

Chiller Intern. Chitter 0% Pwr i

Hist.

Motor Motor I

(

48 10 Corp.

04/27/84 0455 Auxiliary Light

<5 0%

RHR Elect. Visual Recirc Motor Recirc None None-Fall.

Building min.

Power Fa't.

Pump Oper.

Ptarp Cold

[

i Hist.

Isol.

Windng ! sol.

Shu %

i Valve Valve i

49 30 Comp.

04/30/84 0900 Auxiliary Light

<10 0%

ESFAS Elect. Fire Vent Relay Vent hone None-Fail.

Building min.

Power Fail.

Atatm Isol.

Coil I sol..

Cold l

Hist.

Lockout Lockout Shutdn

[

Relay Relay

(

50 52 Comp.

05/04/84 1320 Service Wtr Light

<20 100%

MSW Elect. Visual ServWtr Motor ServWtr NSW(1) None Fait.

Ptaphouse rain.

Power Fait.

Pump Winding Pump Hist.

Motor Motor J-9 t

~-

m.. -..__

_.._m s.- _ _ _.. _. _. _ _ _ _ _ _ _. _

..m m..

APPEIWIX J - taste I seeDKE EVENTS DA1A - 01/01/65 - 12/31/85 ITEDI DET/

LER/

EVENT REPORT LOCATI(W EXTENT EST.

OPER.

PLT CAUSE DE1ECT INIT.

INIT.

C0155 TRAIN POWER g

PLT ID OTHER DATE Tiet!

PLT AREA SBIDKE OLE E

SYS SBIOKE DIEAllS CEBES.

EIBB.

EFFECT FFFECT EFFECT 51 57 Conp.

06/08/84 --

Reactor Light

<20 0%

Cont.

Elect. Visual Drywelt Voltage Drywelt None None-Fait.

Building min.

Power Atmos Fait.

Cooling Regut. Cooling 0% Pwr Hist.

Cooting TenpRec TenpRec 52 80 Comp.

06/08/84 --

Reactor Light

<5 100%

Contt Overht Visual CRD Purrp CRD CRD(1) None Fait.

Buildirig min.

Power Rod Matt Punp Bearing Putp s

Hist.

Drive i

53 54 Comp.

07/05/84 0700 Auxiliary Light

<20 Power Plant Elect. Visual 480V CB 480VW None None l

Fait.

Building min.

Oper.

AC Pwr Fall.

Reactoi Trip Reactor

[

Hist.

Distr Vent CB Coit vent CB j

54 40 Comp.

07/11/84 1130 Turbine tight

<5 0%

MS Elect. Visual MStV Circuit MSIV None None-Fait.

Building min.

Power Fait.

Circuit Breaker Circuit 0% Pur Hist.

Breaker intern. Breaker L

L 55 16 Comp.

07/17/84 1830 Diesel Gen.

Light

<5 0%

EDG Elect. Visual JaktWtr Motor JaktWtr hone None-

~

Fail.

Building min.

Power Fait.

Cooling Intern. Cooling 0% Pwr.

i, Hist.

PumpMtr PumFMtr l

56 45 Conp.

07/18/84 1800 Dieset Gen.

Medim

<30 90%

EDG Overht Trouble DG Lube DG EDG(1) None Fait.

Building (Filled min.

Power Matt Alarm Air Oil Air-Hist.

Room)

Cocpr.

Compr.

j t

i 57 53 Conp.

07/27/84 1729 Reactor Light

<10 Power React.

Elect. Visual RRPm p Circuit RRPunp RR(1)

Reduced Fait.

Building min.

Oper.

Recire. Iail.

MG Set Breaker Chiller Power Hist.

C8 Intern. Motor h

58 245 84-18 08/03/84 0156 Auxiliary Light

<5 0%

RHR Overht Visual Valve Circuit Valve RHR(1)

None-f Building min.

Power Matt Circuit Breaker Circuit 0% Pwr I

Breaker Intern. 3reaker 59 53 Comp.

08/10/84 1500 Reactor Light

<ZO 0%

RCIC Elect. Motor CST Circuit CST None None-I Fait.

Building min.

Power Fait.

Overtd Isol.

Breaker Isol.

0% Pwr

[

Hist.

Annunc. ValveCB Intern. ValveCB

[

60 397 84-96 09/01/84 --

Other Medium <30 65%

Fire Overht Fire Diesel Lack of Dieset Manual

[

Bdg (Watet min.

Power Protec Matt Alarm Fire Cooting Fire.

Turbine i

Filtration)

Pump Water Pump Trip f

r I

i J-10 l

I

.m-~

e I

o APPEIBIE J - IABLE I SMOKE EVENTS DATA - 01/01/65 - 12/31/85 1

ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

lWIT.

COMP.

TRAIN P0bER 30 PLT ID OTHER DATE T19E PLT AREA SM_OK_E DUR M _ ODE SJS SMOKE MEANS Ct3P.

CtBS.

EFFECT EFFECT EFFECT a

61 18 Conp.

09/04/84 0305 Reactor Light

<10 78%

RPS Elect. Visual Neutron Relay Neutron None None Fait.

Building min.

Power Fail.

Monit. Coil Monit.

Hist.

Relay Relay i

62 2

Comp.

09/13/84 1000 Control Light

<10 0%

DC Elect. Visual 480V Relay 480V None None-Fail.

Room min.

Power Power Fail.

UndrVlt Coit Undrvlt Refuel.

Hist.

Distr.

Lockout Lockout Relay Relay i

63 16 Conp.

10/15/84 1450 Diesel Gen.

Light

<10 0%

EDG Overht Visual DG Fuel DG EDG(1) None Fait.

Building min.

Power Matt Turbo-Oil Turbo-Hist.

Charger Charger

)

64 33 Conp.

11/19/84 1500 Diesel Gen.

Light

<20 0%

EDC Elect. Visual Auxil. Motor Auxit.

Norw None-

{

Fai1.

Buitding min.

Power Fait.

F0 Pump Intern. F0 Punp 0% Pwr i

Hist.

Motor Motor 65 47 Comp.

11/19/84 0925 Auxiliary Light

<10 0%

Contt Elect.

Visual Reactor Trip Reactor None None-Fait.

Building min.

Power Rod Fai; Trip Breaker Trip 0% Pwr Hist.

Drive Breaker Intern. Breaker 66 46 Comp.

12/24/64 1207 Auxiliary Lig5t

<20 Power CVC0 Overht Visual ChrgPnp Speed ChrgPnp None None f

Fait.

Building min.

Oper.

Matt Speed inersr Speed l

Hist.

Incrsr LubeOil Increaser I

67 55 Comp.

12/26/84 1300 Auxiliary Mediun <30 100%

AFW Overht Visual Motor Bearing Motor AFW(1) None f

Fait.

Building (Filled min.

Power Matt Driven Lube Driven Hist.

Room)

Pump Oil Pump 68 47 Comp.

01/07/85 0835 Auxiliary Light

<20 0%

CVCS overht Visual Chargng Motor Chargng None None-Fait.

Building min.

Power Matt Pump Bearing Pump 0% Pwr

[

6 Hist.

Motor Motor 69 45 Comp.

01/11/85 1030 Auxiliary Medium <30 0%

Instr Elect.

Trouble Instr Invertr Instr hone None-Fait.

Building (in min.

Power AC Pwr fait.

Alarm AC Pwr Xformr AC Purt 0% Pwr Hist.

Area)

Distr.

Invertr Invertr

[

70 33 Comp.

01/14/85 1230 Auxiliary Light

<10 0%

AFW overht Visual Motor Pump Motor AFW(1)

None-Fait.

Building min.

Power Matt Driven Bearing Driven 0% Pur Hist.

{

Punp Ptsnp J-11 l

y APPENDIN J - IASLE I SBIOKE EVENTS DATA - 01/01/65 - 12/31/85 ITEM DKT/

LER/

EVENT REPORT LOCATI(Ni EXTENT EST.

OPER.

PLT CAUSE. DETECT tulT.

tuli.

CIBIP.

TRAlu POE R g

PLT 10 OTHER DATE TIE PLY AREA SBEXE Otm BEDE M

SBEEE MANS CIEW'.

Ctse.

EFFFCT EFFECT EFFECT 71 71 Comp.

03/06/85 0747 Auxiliary Light

<10 0%

RHR Elect. Visual LPS!

Motor LPSI None None-Fall.

Building min.

Power Fail.

Minflow oper.

Minflow 0% Pwr Hist.

Valve Intern. Valve 72 1

Comp.

03/07/85 2247 Auxiliary Light

<20 93%

CCW Elect. Visual CCW CB Cntt CCW None None Fail.

Building min.

Power Fait.

Punp Relay Pump Hist.

CB Coit CB Relay Relay 73 41 Comp.

03/16/85 2200 Auxiliary Light

<10 Power CCW Overht Visual CCW Pump CCW CCW(1) None Fait.

Building min.

Oper.

Matt Pump Wear Pump Hist.

Ring 74 36 Comp.

03/20/85 2215 Reactor Light

<10 0%

RHR Elect. Fire RHR Motor RHR RHR(1)

None-Fait.

Building min.

Power Fail.

Alarm Pump Intern. Pump 0% Pwr Hist.

Motor Motor 75 58 Conp.

04/30/85 --

Auxiliary Light

<20 0%

Instr Elect. Visual Instr Invertr Instr None None-Fait.

Building min.

Power AC Pwr fail.

AC Pwr Oil AC Pwr 0% Pwr Hist.

Distr.

Invertr Capac.

Inverer 76 8

Comp.

05/15/85 1422 Auxiliary Light

<10 Power Corrbust Elect. Visual Recom' c Sol.

Recombr None None u

Fait.

Building min.

Oper.

Gas Fait.

Block Coit Block Hist.

Control Valve Valve 77 39 Conp.

05/31/85 --

Auxiliary Light

<5 0%

Instr Elect. Visual Instr invertr Instr None None-Fail.

Building min.

Power AC Pwr fait.

AC Pwr leads AC Pwr Refuel.

Hist.

Distr.

Invertr Invertr 78 60 Conp.

06/12/85 1630 Auxiliary Light

<20 Power instr Elect. Visual Instr Invertr Instr Instr None Fait.

Building min.

Oper.

AC Pwr fail.

AC Pwr Capac. AC Pwr-AC Pur Hist.

Distr.

Invertr Invertr Distr (1) 79 22 Comp.

06/28/85 --

Dieset Gen.

Light

<20 100%

EDG Overht Visual DG Coapr DG None None Fait.

Building min.

Power Matt Air Intern. Air Hist.

Compr Compr 80 483 85-32 07/15/85 2123 Control Light

<10 100%

Food Smoke Food None Room min.

Power Cooking Detect.

(Pantry)

J-12 m

• I APPEIBiX J - TABLE I SMOKE EVENTS DATA - 01/01/65 - 12/31/85 lien DICT /

LER/

EVENT REPORT LOCATI(MI EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

COMP.

TRAIN P0hER NO Pti ID OTIIER D_ ATE YIDE PLT AREA SMOKE DUR M _ ODE SYS SMOKE MEAles COMP.

COME.

EFFECT EFFECT EFFECT A

t j

81 30 Comp.

07/25/85 1600 Auxiliary Light

<20 100%

ESFAS Elect. Visual Vent Relay Ver;t None None Fait.

Building (Smoke min.

Power Fait.

Isol.

Coil Isol.

Hist.

Smelt)

Lockogt Lockout 1

Relay Relay 82 10 Conp.

07/31/85 0722 Auxiliary Light

<20 0%

RPS Elect. Visual Undrvit Relay Undrvtt None None-

[

Fai!.

Buitding min.

Power Fail.

Bus Coity Busp 0% Pwr

[

Hist.

Relay Relay I

83 17 Conn.

07/31/85 --

Reactor Light

<20 100%

RCIC Elect. Visual Supp-Circuit Suppe None None i

Fail.

Building min.

Power Fail.

Alarm Pool Breaker Pool Hist.

Isot.

Coil isol.

Viv CB Vlv CB 84 331 85-31 08/02/85 1108 Auxiliary Light

<5 95%

RCIC Overht Smoke RCIC Invertr RCIC RCIC None Building min.

Power Matt DetFt. Static Capac. Static Invertr Oii Invertr t

85 39 Conp.

08/08/85 --

Auxiliary Light

<5 0%

Contt Elect. Visual Reactor Trip Reactor None None-Fait.

Building min.

Power Rod fail.

Trip Breaker Trip 0% Pwr Hist.

l Drive Breaker Contact Breaker 86 47 Conp.

08/20/85 1529 Auxiliary Light

<5 0%

Contt Elect. Visual Reactor Closing Reactor None None-Fail.

Building min.

Power Rod Fait.

Trip Coit Trip 0% Pwr h

Hist.

{

Drive Breaker Breaker i

87 58 Conp.

09/04/85 0800 Service Wtr Light

<5 Power NSW Overht Visual SW Ptznp Motor SW Ptsnp None None

[

Fait.

Ptrphouse min.

Oper.

Matt Dischg Oper.

Dische i

Hist.

Valve Seat Valve 88 53 Comp.

09/11/85 1500 Reactor Light

<5 0%

HPCI Elect. Visual Booster Motor Booster None None-

[

t Fail.

Building min.

Power Fait.

Ptnp Oper.

Pung 0% Pwr Hist.

Suction Inter... Suction valve Valve

(

89 49 Conp.

10/22/85 --

Turbine Light

<10 0%

Cond.

Elect. Visual Cond.

CB Trip Cond.

None None-Fait.

Building min.

Power Fait.

Booster Colt Booster Refuel.

Hist.

Pmp CB Pmp CB 90 61 Conp.

10/24/85 0330 Auxiliary Light

<10 87%

Plant Elect. Visual P' ant Bus Plant Plant Manual i

Fail.

Building min.

Power AC Pwr Fait.

AC Pwr Bar AC Pwr AC Pwr Shutdown Hist.

i Distr.

Distr.

Insul Dist'.

Disisi) i L

J-13 V

f i

APPENDIX J - IABLE I SMOKE EVENTS DATA - 01/01/65 - 12/31/85 ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

COMP.

TRAIN P0bE R up PLT ID OTHER DJA M

PLY AREA SNOKE DUR M

STS SMIKE MANS CEEW5 CGG.

EF FECT EFFECT EFFECT a

91 34 Comp.

10/30/85 --

Turbine Light

<20 100%

Cond.

Overht Bearing Cond.

Motor cond.

Cond(1) Reduced Fait.

Building min.

Power Matt Tenp.

Punp Bearing Pum Power Hist.

Alarm Motor Motor (to 60%)

92 63 Conp.

11/23/85 0627 Reactor Light

<20 0%

RHR Elect. Fire RHR Motor RHR None None-Fait.

Building min.

Power Fait.

Alarm Punp Winding Punp 0% Pwr l

Hist.

Motor Motor 93 41 Conp.

12/12/85 0230 Auxiliary Light

<20 100%

Instr Elect. Visual Instr Invertr Instr hone None Fait.

Building min.

Power AC Pwr Fait.

AC Pwr Xformr AC Pwr l

Hist.

Distr.

Invertr Invertr 94 1

Cornp.

12/13/85 1408 Turbine Light

<5 0%

FW Overht Visual First Motor First None None-Fait.

Building min.

Power Matt Heater Oper.

Heater Refuel.

Hist.

Block Frict. Block Valve Valve 95 39 Cong.

12/14/85 --

Auxiliary Light

<20 931 CCW Overht Visual CCW Gearbx CCW CCW(1) None Fait.

Building min.

Power Matt.

Pung Breaker Purp Hist.

Contact NOTES:

1.

The Auxiliary Building is For PWR only.

For t' is table, PWR Reactor Building, Control Building, Cable Spreading Room, and Switchgear Room are included with Auxiiary Building.

2.

The Reactor Building is for BWR use only. For this table, BWR Control Building, Waste Treatment Building, Cable Spreading Room, and Switchgear Room are included with the Reactor Building.

3.

Smoke events listed do not include Fire Events for this period (see Appendix A - Table I).

J-14

+

+

e TABLE II SNOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

CW.

TRAIN POhER NO PLY 10 OTNER DATE TIE PLT AREA SMOKE D._tL, g

SJS SMOKE MANS COMP.

CIEW.

EFFECT EFFECT EFFICT 1

259 86-03 01/14/86 1430 Turbine Light

<1 Hr.

0%

Plant Elect. Visual Elect. Cable Elect.

None-Building Power AC Pwr Fait.

Feeder Matt Feeder 0% Pwr Distr.

Cable Cable 2

325 86-07 02/24/C6 1615 Control Light

<10 100%

Food Fire Food None Room min.

Power Cocking Detect.

Cooking 3

47 Comp.

05/11/86 1025 Cabte Spreading Light

<10 2%

Aux Unknown Visual Fan Cable Fan Aun None Fait.

Room min.

Power Bldg Motor Insul Motor Bldg Hist.

HVAC Cable Cable HVAC(1) 4 47 Comp.

05/20/86 0920 Other Bldgs Light ' <10 0%

Hydrgn Overht Smoke Recombr Xformr Recombr None None-Fail.

(Hydrogen min.

Power Ree vibr Mat t Detect. Control Intern. Control 0% Pwr Hist.

Recombiner)

Xformr Aformr 5

61 Conp.

06/24/86 0503 Diesel Gen.

Light

<10 Power EDG Overht Visual Engine Lube EDG EDG(1) None fait.

Building ein Oper.

Matt Lubecil Oil Hist.

Strainr 6

8 Cmip.

01/30/87 --

Auxiliary Light

<5 Power Cont.

Elect. Visual FanCool Relay Fan None None fait.

Building min.

Oper.

Cool.

Fait.

CB Cntt riosing Cooter Hist.

HVAC Retay Coil Unit 7

11 Comp.

02/05/87 2016 Service Water Light

<5 100%

NSW Elect.

Visual NSW Motor NSW NSW(1) Power fait.

PLmphouse min.

Power Fait.

Pump Intern. Punp Reduced Hist.

Motor Motor 8

11 Conp.

02/06/87 1837 Service Water Light

<5 100%

NSW Elect. Visual NSW Motor NSW NSWC1) Power Fait.

Ptagttouse min.

Power Fail.

Pump Intern. Pump Reduced Hist.

Motor Motor 9

79 Comp.

02/08/87 0400 Control Light

<5 Power RPS Elect. Visual Power Elect. RPS None None Fait.

Room min.

Oper.

Fait.

Supply Intern. Power Hist.

Xformr Supply 10 44 Conp.

02/28/87 1600 Service Water Light

<30 Power NSW Elect. Visual SW Motor SW NSW(1) None Fait.

Punphouse min.

Oper.

Fail.

Pump Winding Pump Hist.

Motor Motor 11 71 Comp.

02/28/87 --

Diesel Cen.

Medium

<30 0%

EDG Overht Visual DG Fuel DG EDG(1)

None-Fail.

Building min.

Power' Matt Engine Oil Engine Refuel.

Hist.

J-15

r

.a~

-.. -. - - ~ ~. - -...-

- - - ~ -. = - - ~. - ~ ~ - - - _. -

.-a--

.. = - -

b I

i I

TABLE II SMOKE EVENTS DATA - 01/01/86 - 12/31/96 ITEM DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT IMIT.

INIT.

COMP.

TRAIN POWER NO PLT ID OTHER D_ ATE TIINE PLY AREA SNOKE DUR M_IXIE M

SMOKE LEANS CIEN>.

CENS.

EFFECT EfFECT EFFECT

{

12 9

conp.

03/01/87 0940 Service Water Light

<1 Hr.

0%

NSW Elect. Visual ServWtr Breaker ServWtr None None-Fail.

Punphouse Power Fait.

Fan Xformr Fan 0% Pwr I

6

~

CB Intern. CB i

13 37 Conp.

03/02/87 --

Service Water Mediun <30 Power ESW Elect. Visual ESW Motor ESW None None Fail.

Puuphouse min.

Oper.

Fait.

Ptanp Intern. Pump I

Nist.

Motor Motor-I 14 59 Cong.

03/04/87 1250 Service Water Light

<1 Hr.

0%

NSW Overht Visuat NSW Pump NSW NSW(1)

None+

fait.

Pumphouse Power Matt Pump B$aring Pump Refuel.

Hist.

15 24 Comp.

03/04/87 --

Diesel Gen.

Light

<30 100%

EDG Overh t Visual DG AirCoot DG EDG(1) None W

=

Fail.

Building min.

Power Matt Turbo-Manif td Engine

(

Hist.

Charger Crack i

16 12 Comp.

03/06/87 1355 Reactor Light

<1 nr.

0%

RWCU Elect. Visual RWCU Retay RWCU RWCU(1) None-

[

Fail.

Building Power Fait.

Pung Coil Purre 0% Pwr i

Hist.

Relay 17 101 Cong.

03/09/87 2020 Reactor Light

<5 100%

SGas Elect. Visunt Fan Breaker SGBS SGBS(1) None Fail.

Building min.

Power Fait.

Contrl Relay Fan L

Hist.

Breaker Coil I

18 39 Conp.

04/08/87 2259 Turbine Light

<S 96%

cond.

Overht Visual cond.

Motor Cond.

Cond(1) Reduced Fail.

Building min.

Power Matt Pump Bearing Pump Power Hist.

Motor Lube Motor h

19 61 Conp.

05/18/87 --

Auxiliary Light

<5 0%

RKR Elect. Visual RHR Motor RHR RHR(1)

None-Fait.

Building min.

Power fail.

Punp Leads Pump 0% Pwr Hist.

[

Motor Motor 20 20 Conp.

05/19/87 0100 Auxiliary Light

<5 Power DC Elect. Visuat Standby Charger Standby None None Fait.

Building min.

Oper.

Pwr Fail.

Battery Intern. Battery Hist.

Distr.

Charger Charger i

21 37 Coap.

05/20/87 --

Turbine Light

<5 0%

Cond.

Elect. Visual Booster Motor Booster None None-Fait.

Building min.

Power Fail.

Ptep Intern. Pump 0% Pwr Hist.

DschVlv DschViv t

J-16 I

I

O TAELE II SMOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DKT/

LER/

EVENT REMalf t.OCATION EXTENT EST.

(PER.

PLT CAUSE DETECT INIT.

INIT.

COMP.

TRAIN POWER g

PLT ID OTHER DE TIME PLT AREA SMOKE LwJR.

MG)E SYS SMOKE MEAMS COMP.

COMB.

EFFECT 5?8ECT EFFECT 22 50 Comp.

06/16/87 --

Turbine Light

<20 0%

Cond.

Overht visual RHR Motor RHR RHR(1)

None-Fail.

Buildirg min.

Power Matt Crossti Oper.

Crosstic Refuel.

Hist.

Valve Winding Valve 23 3 70 87-09 07/02/87 2341 Switchgear Light

<10 0%

RPS ljnknown Visual Reactor Elect.

Reactor RPS(1)

None-Room min.

Power Trip Intern. Trip 0% P r Breaker Breaker 24 424 87-45 07/02/87 1110 Auxiliary tight 2 Hrs 100%

CVCS Overht Visual CVCS Punp CVCS(1) None None Building Power Matt Pump Intern.

25 25 Comp.

07/09/87 --

Reactor Light

<5 0%

LPCS Elect.

Visual LPCS CB LPCS LPCS(1) None-Fail.

Building min.

Power Fail.

Test Xformr Test Refuel.

Hist.

Vlv CB Viv CB 26 3

Comp.

08/01/87 --

Reactor Light

<20 0%

Reactor Elect.

Visual Dische Breaker Dischg RR(1)

None-Fail.

Building min.

Power Recirc. Fail, hcass Intern. Bypass 0% Pwr Hist.

Vlv CB Viv CB 27 87 Comp.

09/26/87 --

Turbine Light

<10 C*

Cond.

Elect.

Visual Cond.

Motor Cond.

None None fait.

Building min.

Powe.

Fail.

Pump Bea-ing Ptanp Hist.

Motor Lube Motor 28 27 Comp.

09/27/8/ --

Service Water Meditsn

<30 100%

NSW Overht Visual NSW Packing NSW None None Fail.

Pumphouse min.

Power Matt Ptsno Matts Pump Hist.

29 483 87-28 10/03/87 1027 Control Light

<10 0%

Food Smcke Food None-Room (Pantry) min.

Power Cooking Detect.

Cooking 0% Pwr 30 10 Comp.

10/21/87 1800 Auxiliary Light

<5 01.

DC Elect. Visual Battery Charger Battery DC None-Fail.

Buildirs min.

Power Pwr Fail.

Charger Intern. Charger Pwr 0% Pwr Hist.

Distr.

FiltMod Dist(1) 31 8

Comp.

11/16/87 1830 Auxiliary Light

<1 Hr.

0%

CCu Elect. Visual CCW Motor CCW CCW(1)

None-Fail.

Building Power Fail.

Punp leads Ptep Refuel.

Hist.

Metor Motor 32 39 Conp.

11/18/87 19 %

Auxiliary Light

<5 0%

DC Elect.

Visual Battery Xformr Battery DC None-Fail.

Building min.

Power Pwr Fail.

Charger Intern. Charger Pwr(1) 0% Pwr Hist.

Distr.

Xformr J-17

i IASL1 11 i

Seq 0KE EVENTS DATA - 01/01/86 - 12/31/94

~

ITEM DKT/

(ER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DEVECT INIT.

INIT.

CEBr.

TRAIN POW R 30 PLY ID OTNER DATE TitNE PLT AREA SBKlKE OtR 8MBE SYS SMOKE NEANS CGEP.

C135.

EFFECT EFFECT EFFECT 33 101 Comp.

12/05/87 -

Reactor Light

<5 0%

MS Elect. Visual MS ! sot Motor MS isot MS(1)

None-fait.

Building min.

Power Fait.

Valve Oper.

Valve 0% Pwr Hist.

Intern, t

34 35 Comp.

12/17/87 -

Auxitiary Medium

<1 Mr.

100%

Contt Overht Visual CRD Bearing CRD CRD(1) None Fait.

Building Power Rod Matt MG Set Lube MG Set Hist.

Drive Bearing 1

35 40 Comp.

01/06/88 --

Diesel Gen.

Light

<5 100%

EDG Overht Visual Engine Bearing DG Eng EDG(1) None Fait.

Building min.

Power Matt Turbo-Lube Turbo-Hist.

Charger Charger t

36 73 Comp.

01/08/88 --

Reactor Light

<10 Power HPCI Elect. Visual Torus Motor Torus HPCI None Fait.

Building min.

Oper.

Fait.

Isot Oper.

(sot Hist.

Valve Intern. Valve i

37 11 Comp.

01/14/88 0001 Switch Yard Light

<1 Hr.

100%

Plant Elect. Visuat Xformr Fan Unit Plant None Fail.

Power AC Pwr Fait.

Fan Motor Aux AC Pwr I

Hist.

Distr.

Motor Insul Xformr Dist(1) 38 30 comp.

01/21/88 ~

Auxiliary Light

<10 100%

ESFAS Elect. Visual SI Relay SI None None I

fail.

Building min.

Power Fait.

Lockout Coit Lockout I

Hist.

Motor Relay Relay t

39 13 Comp.

01/24/88 0110 Switchgear Light

<1 Hr.

0%

RCS Elect. Visual Prestr Circuit Preszr RCS(1)

None-Fail.

Room (Smoke Power fait.

Heater Breaker Heater Plant Hist.

Residue)

CB Intern. CB Startup 40 58 Comp.

02/04/88 2050 Auxiliary Light

<5 0%

AFW Overht Visual Pump Bearing AFU Mot A P.1 )

None-Fait.

Building min.

Power Matt Motor Oil Driven Refuel.

[

Hist.

Bearing Pump 6

41 10 camp.

02/06/88 1015 Auxitiary Light

<5 100%

DC Elect. Visual Battery Char,er Bat'.ry DC Unit Fail.

Building min.

Power Pwr Fail.

Charger Intern. Chorger Pwr Shutdn 1

Hist.

Distr.

FiltMod Dist(1) (Manual) i 42 10 Comp.

02/07/88 1410 Auxiliary Light

<5 98%

DC Elect. Visual Battery Charger Battery DC Unit Fait.

Building min.

Power Pwr Fail.

Charger Intern. Charger Pwr Shutdn Hist.

Distr.

FittMod Dist(1) (Manual)

I r

i J-18 e-t

• i

V TABLE il SNOKE EVENTS DATA - 01/01/86 - 12/31/94 3

ITEM DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

lulf.

CIENS.

TRAIN PERER g

PLY ID OTIER DATE TIE PLT AREA SMME DLR N_IBE T

S SNOKE KANS Ctpu>.

CtWW.

EFFECT EFFECT EFFECT E

+

43 328 88-05 02/12/88 1133 Auxiliary Light

<10 0%

CVCS Overht Visual Pt.mip Lube CVCS CVCS(1) None-Building min.

Pwr Matt Speed Oil Pung 0% Pwr i

incrsr 44 55 Conn.

02/12/88 0700 Auxiliary Light

<30 0%

CvCS overht Visual ChgPump Lube Chargng None None-faii.

Buitding min.

Power MatL Speed OiI

. Ptsnp 0% Pwr Hist.

Incrsr 45 40 Conp.

02/18/88 --

Auxitiary Light

<1 Nr.

99%

Cont.

Overht Visual Cont.

Pump Cont.

CS(1)

None fait.

Building Power Spray Matt Spray Packing Spray Hist Pump Pum 3

46 74 Conp.

03/01/88 1430 Auxiliary Light

<1 Hr.

0%

NSW Elect. Visual Circuit Elect. Valve None None-Fait.

Building Power Fait.

Breaker Intern. Oper.

Refuel.

Hist.

Heater C8 47 61 Comp.

03/20/88 1445 Auxiliary Light

<10 0%

Penetr. Elect. Visual Exhaust Circuit Exhaust penetr. None-

'l Fait.

Building min.

Power Room Fait.

Fan Breaker fan Room Hot

?

Hist.

Ventil.

CB Intern. CB Vent (1) Stdby

[

48 1

Conn.

03/30/88 --

Containment Light

<1 Hr.

0%

Cont.

Overht Visual Cont.

Cooler Cont.

Cont.

None-fait.

Power HVAC Matt Air Fan Air HVAC(1) 0% Pwr Hist.

Cooter Intern. Cooler f

i 49 74 Conp.

G4/02/88 1700 Auxiliary Light

<5 0%

DC Pur Elect. Visual Battery Charger Battery None None-fait.

Building min.

Power Distr.

Fail.

Charger Intern. Charger Refuel.

Hist.

Motor Motor

}

50 13 Conp.

04/16/88 1714 Dieset Gen.

Medium <30 100%

EDG Overht Visual DG Gene Rotor DG Genr EDG(1) None fait.

Building ein.

Power Matt Rotor Insut Rotor Hist.

Assy Assy 51 57 Conp.

04/18/88 0500 Reactor Light

<10 Power RPS Elect. Visual RPS Relay RPS RPS(1) None Fait.

Building (Smoke min.

Oper.

Fail.

MG Set Coit MG Set Hist.

Odor)

Relay 52 69 Comp.

04/30/88 --

Turbine Light

<10 5%

MS Elect. Visual MS isnt Motor MS Isol MS(1)

None

[

Fait.

Building min.

Power fait.

Valve Oper.

Valve f

Hist.

Intern, i

i t

J-19 i

4 L

r i

b i-

TABLE II SMOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

COBF.

TRAIN P0hER g

PLT ID OTNER DJA TIIE PLT AREA SHOKE DUR.

D_N._B_E_

S_ S SNOKE SEANS CIEN*.

COIs.

EFFECT EFFECT ~EFFECT Y

53 98 Comp.

05/10/88 --

Auxiliary Light

<1 Hr.

Power Cont.

Elect. Visual CS Pmp Breaker CS CS(1)

None fait.

Building Oper.

Spray Fait.

Circuit Closing Punp Hist.

Breaker Coit CB 54 27 Comp.

05/28/88 --

Auxiliary Light

<5 0%

RHR Elect. Visual LPCI Motor LPCI None None-Fait.

Building min.

Power Fait.

Pump Oper.

Ptsnp Refuel.

Hist.

Minift Intern. Minift 55 424 88-16 06/03/88 --

Cable Spreading Light

<20 100%

Plant Overht Smoke Elect. Unknown RCS None None-Room min.

Pur AC Pur Matt Detect. Duct valves 0% Pwr Distr.

Heater 56 10 Conp.

06/03/88 1015 Auxiliary Light

<10 100%

RPS Elect. Visual RPS Relay RPS RPS(1) None Fait.

Building min.

Power fait.

Relay Matt Relay Hist.

57 8

Conp.

06/04/88 --

Diesel Gen.

Light

<5 100%

EDG Elect. Visual DG Air Motor DG Air EDG(1) None Fait.

Building min.

Power Fait.

Conpr Intern. Compr Hist.

Motor 58 19 Conp.

06/13/88 0100 Auxiliary Light

<20 Power Instr Etect. Visual Instr Xformr Instr None None Fait.

Building min.

Oper.

AC Pwr Fail.

Invertr Intern. Invertr Hist.

Distr.

Xforme 59 69 Comp.

06/24/88 1245 Reactor Light

<20 100%

RPS Elect. RPS Power yformr RPS RPS(1) None Fait.

Building min.

Power Fait.

Atarm Supply CB Power Hist.

Xformr Intern. Supply 60 32 Comp.

06/15/88 0639 Auxiliary Light

<5 Power DC Elect. Visual Standby Charger Standby DC None Fait.

Building min.

Oper.

Pur Fait.

Battery Intern. Battery Pwr(1)

Hist.

Distr.

Charger Charger 61 440 88-28 06/23/88 1227 Other Btdgs Light

<20 0%

Aux.

Toxic Aux Boiler None-(Aux Boiler) min Power Boiler Gas Boiler Exhaust 0% Pwr Exhaust Detect.

Smoke 62 69 Conp.

06/24/88 --

Reactor Light

<10 100%

RPS Elect. Visual RPS Circuit RPS RPS(1) None Fait.

Building min.

Power Fail.

MG Set Breaker MG Set Hist.

CB Intern. CB J-20 A

~..

I t

s TASLE II SMOKE EVENTS DATA - 01/01/86 - 12/31/X ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

CIMP.

TRAIN POKR t

g PLT ID OTTER D_ ATE TIE PLT AREA SNEXE Otm M_tBE M

SINXE KANS CIEN*.

CKBS.

EFFECT EFFECT EFFECT 63 64 Comp.

06/27/88 0800 Auxiliary Light

<30 0%

Instr Elect. Visual Power Resistr Power None None-

+

Fait.

Building min.

Power AC Pwr Fait.

Supply Supply Cold Hist.

Distr.

Invertr Invertr Shutdn l

64 2

Comp.

07/14/28 --

Switch Yard Light

<1 Hr.

0%

Plant Elect. Visual Station Xformr Station Plant None-s Fait.

Power AC Pwr Fail.

Service Intern. Service AC Pwr 0% Pwr Hist.

Distr.

Xformr Xformr Dist(1) 65 97 Comp.

08/10/88 --

Diesel Gen.

Light"

<1 Hr.

Power EDG Elect. Visuat DG Air Motor DG Air EDG(1) None Fait.

Buitding Oper.

Fai1.

Compr Intern. Compr Hist.

Motor 66 12 Comp.

C '11/88 1405 Dieset Gen.

Light

<1 Mr.

Power EDG Overht Visual Controt Xformr DG FO None None

Fait, building Oper.

Matt Xformr Coit Supply Hist.

Pump 67 51 Comp.

08/12/88 1704 Turbine Light

<20 94%

Cond.

Elect. Ground Booster Motor Cond.

None None Fail.

Building min.

Power fait.

Alarm Planp Leads Booster Hist.

Motor Pune 68 1

Conp.

08/15/88 --

Auxiliary Light

<10 92%

Cont.

Elect. Visual ventstk Fan ventStk Cont.

None Fail.

Building min.

Power Fan Fait.

Dilutn Motor Dilutn Fan Hist.

Cootng fan Insut Fan Cootng(1) t 69 4

Comp.

09/02/88 --

Reactor Light

<5 0%

SL C Overht Visual SBLC Ptsip SLC SLC(1)

None-Fait.

Building min.

Power Matt Pump Packing Pump Cold Hist.

Matt Shutdn 70 69 Conp.

09/03/88 --

Reactor Light

<5 100%

HPCI Overht Visual Pump Gear HPCI HPCI None Fait.

Building min.

Power Matt Gear Reducer Pump l

Hist.

Reducer Lube 71 440 88-37 09/18/88 1715 Other Btdgs Light

<20 0%

Aux.

Toxic Aux Boiler None-(Aux Boiter) min.

Power Boiler Gas Boiter Exhaust 0% Pwr j

72 48 Conp.

10/30/88 --

Switch Yard Light

<5 Power Plant Elect. Visual ServBus Breaker ServBus Plant None Fait.

min.

Oper.

AC Pwr Fail.

Tie Closure Tie AC Pwr Hist.

Distr.

Breaker Coil Breaker Dist(1)

J-21 l

i i

t IABLE II SNOKE EVENTS DATA - 01/01/86 - 12/31/94 r

w ITEst DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT Inti.

tuli.

CW.

TRAIN POKR No PLT 10 OTHER DATE TIE PLT AREA SNOKE DUR M

SYS SNOKE MANS CW.

CING.

EFFECT EFFECT EFFECT I

a 73 86 Cong.

11/01/88 0911 Diesel Gen.

Light

<10 0%

EDG Elect. Fire Jacket Tenp DG Jakt None None-Fait.

Building min.

Power Fail.

Alarm WtrCool Switch Water 0% Pwr Hist.

TS Intern. Cooter 74 51 Comp.

11/02/88 0818 Auxiliary Mediun

<30 0%

RHR Overht Visual RMR Pmp Bearing RHR RHR(1)

None-Fail.

Building min.

Power Matt Motor Lube Pump Cold Hist.

Bearing Oil Motor Shutdn 75 56 Comp.

11/28/88 --

Reactor Light

<1 Hr.

Power Plant Elect. Visual Battery Relay Battery Plant None Fait.

Building (Smoke Oper.

DC Pwr Fail.

Charger Intern. Charger DC Pwr Hist.

Residue)

Distr.

Relay Dist(1) i 76 50 Conp.

11/30/88 --

Turbine Light

<20 0%

FW Elect. Visual FW Elect.

FW FW(1)

None-Fait.

Building min.

Power Fail.

Xformr Insul Xformr Refuel.

Hist.

Power Power 77 60 Conp.

12/22/88 0830 Auxiliary Light

<20 Power Instr Elect. Visual Instr Invertr Instr None None Fait.

Building (Smoke min.

Oper.

AC Pwr Fait.

Power Elect. Power l

Hist.

Smell)

Distr.

Invertr Leads Invertr 78 28 Comp.

01/06/89 --

Auxiliary Light

<10 0%

CVCS Elect. Visual Chargng Motor Chargng None None-Fait.

Building min.

Power Fail.

Pump Oper.

Punp Cold Hist.

Dischg Intern. Dischg Shutdn Valve Valve 79 5

Cong.

01/17/89 --

Reactor Light

<1 Hr.

0%

Contt Overht Visual CR0 Bearing CR0 CRD(1)

None-i Fait.

Building Power Rod Matt Supply Lube Supply Refuel.

Hist.

Drive Pump Oil Purp 80 45 Conp.

01/21/89 1500 Auxiliary Light

<1 Hr.

0%

HPSI Overht Fire HPS!

Pipe HPSI None None-Fait.

Building Power Matt Alarm Check Insul check 0% Pwr Hist.

Valve Valve 81 400 89-03 02/06/89 0008 Turbine Light

<10 100%

Turb.-

Elect. Visual Gener. Breaker Gener.

None-Building min.

Power Gen.

Fail.

XctrFld Trip XctrFid (Prior Breaker Coit Breaker Trip) 82 80 Comp.

02/07/89 1305 Turbine Light

<5 5%

Cond.

Elect. Visual Cond.

Motor Cond.

Cond(1) Reactor Fait.

Building min.

Power Fait.

Pump Surge Punp Trip Hist.

Motor Capac. Motor i

J-22 i

i

r Q

s h

TABLE II SMOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DET/

LER/

CKMT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

CUMP.

TRAIN POWER No PLT ID OTHER DATE T ipE PLT AREA SNOKE D__U_R

Nt_B_E, SYS

$NOKE MEANS CGEP.

CGIS.

EFFECT EFFECT EFFECT g

i 83 94 Comp.

02/21/89 2245 Turbine Light

<10 90%

FW Elect. Vi::ual FWDisch Motor FWTurb FW(1) done-Fail.

Building min.

Power Fait.

Valve Oper.

Driven Shutdn Hist.

[

MotOper Intern. Pump inProc.

84 65 Comp.

03/31/89 1712 Auxiliary Medium

<30 100%

Cont!

Elect.

Fire CRD MG Set CRD CRD(1) None Fall.

Building min.

Power Rod Fail.

Alarm MG Set Motor MG Set Hist.

[

Drive Winding 85 72 Cong.

04/12/89 1201 Auxiliary Light

<5 0%

Plant Elect. Visual Battery Charger Battery None None-Fail.

Building min.

Power AC Pwr Fail.

Charger Elect. Charger 0% Pwr Hist.

Distr.

SCR Intern.

i 86 41 Comp.

04/13/89 1000 Turbine Light

<5

>5%

FW Overht Temp FW Pupp Bearing FW FW(1)

None fail.

Building min.

Power Matt Alarm Bearing tube Pump Hist.

Distr.

Oil 87 8

Comp.

04/23/89 --

Auxiliary Light

<10 0%

RNR Elect. Visual RHR Motor RHR RNR(1)

None+

Fait.

Building min.

Power fail.

Dischg' Oper.

Dischg 0% Pw.

Hist.

Valve Intern. Valve 88 54 Comp.

04/24/89 1700 Auxiliary Light

<20 Power

ce Elect. Visual-IceCond Circuit IceCond Ice None Fail.

Building min.

Oper.

Cond.

Fail.

Glyco 8 Breaker Glycot Cond(1)

Hist.

Circul. Intern. Circut.

PLmp CB Pump Cb I

89 92 Comp.

04/29/89 1527 Auxiliary 6ight

<1 Hr.

Power CVCS Overht Visual Positiv Motor Positiv CVCS(1) None

[

L Fail.

Building Oper.

Matt Displac Intern. Displac I

Hist.

Pmp Mot Pmp Mot I

90 27 Coop.

05/02/89 --

Containment Light

<5 0%

Reactor Elect. Visual RAM Motor React.

None None-t Fait.

min.

Power Power Bldg Fail.

Motor Winding Bldg Cold I

Hist.

Penetr Penetr Shutdn 91 37 Comp.

05/16/89 --

Reactor Light

<5 0%

RPS Elect. Visual APRM Power APRM None None-Fait.

Building min.

Power Fait.

Power Supplyr Power 0% Pwr f

Hist.

Supply Potent. Supply I

92 84 Conp.

05/16/89 --

Reactor Light

<10 0%

RCIC Elect. Visual Turb.

Motor Turb.

None None-Fait.

Building min.

Power Fail.

Trip Oper.

Trip 0% Pwr Hist.

Valve TrpSol Valve i

s i

J-23 1

)

L

.._.__.-m.._m.

..m.

.._m...

i t

L TACLi: II SMOKE EVENTS DATA - 01/01/86 - 12/31/94

.l ITEM DET/

LER/

EVENT REPORT LOCATION EXTElitT EST.

OPER.

PLT CAdSE DETECT INIT.

INIT.

COMP.

TRAIN POKR 30 PL1 10 01NER DJA Tj.IE PL1 AREA SMEE DUR_2 M_tB_E.

3_YS SNOKE IEANS CW.

CGW.

EFFECT EFFECT EFFECT 93 92 Comp.

05/23/89 1318 Aux3ry Light

<33 Power Plant Elect. Audio 3KV Xformr 3KV Plant None fait.

autiding (Smoke min.

Oper.

AC Pwr Fail.

Alarm X f c' er Insul Xformr AC Pwr

[

Hist.

In Room)

Distr.

Dist(1)

?

94 46 C-w 05/26fa9.-

Auxiliary Light

<1 Hr.

100%

Ice Elect. Visual Ice Compr Ice Ice None Fait.

Building Power Cond.

Fait.

Cond.

Elect.

Cond.

Cond(1)

Hist.

Compr Coit Com r 95 90 Comp.

05/26/89 --

Diesel Gen.

Light

<5 0%

EDG Overht Visual DG Air Compr DG Air EDG(1)

None-Fait.

Building min.

Power Matt Comr Intern. Compr Refuel.

Hist.

Distr.

96 80 Como.

06/02/89 1900 Reactor Light

<10 0%

HPCI Elect.

"isual Fdwtr CB Fdwtr HPCI None-Fait.

Building min.

Power Fait.

IsotViv Heater IsolVlv 0% Pwr Hist.

CB Relay CB 97 84 Comp.

?";J5/89 0600 Service Water Light

<5 0'.

U Elect. Visual ServWtr hotor ServWtr ESV(1)

None-Fait.

Pumphouse min.

Powee Faii.

' q)t y Leads Supply 0% Par Hist.

Mot Valve 98 89 Comp.

06/13/89 --

Turbine LicAt

<10 Power Cond.

Elect. Visual.

Motor Cond.

Cond(1) None s

Fait.

Building min.

Oper.

Fail.

souster Insut Booster Hist.

Pmp Mot Pmp Mot C9 80 Co g.

06/19/89 0950 Diesel Gen.

Heavy

>1 Hr.

100%

EDG Overht Visual DG Crank-DE EDG(1) None Fait.

Sullding (Rote Power Matt Engine Case Engine j

Hist.

Evacu.)

LubeOil

+

100 8

Comp.

06/21/89 --

Service Water Light

<5 0%

NSW Elect. Visual SWPump Relay SarvWtr NSW(1) Wone-Fail.

Pumphouse min.

Power Fail.

Hist.

CB Cntl Closing Pump 0% Pwr Relay Coil CB 1

101 89 Conp.

06/27/89 0130 Turbine Light

<1 Hr.

Power F#

tiect. Vis sal FW ! sol Circuit FW ! sot None None Fail.

Building TSmoke Cp er.

Fait.

Valve Breaker Valve Hist.

Residue)

C8 Intern. CB 102 73 Corep.

07/04/89 --

Peactor Light

<1 Hr.

Power Plant Elect. Visual Batter y Elect. Battery Plant None Fait.

Building Oper.

I,C Pwr fait.

Charger intern. Charger DC Pwr Hist.

0.str.

Capactr Dist(1)

?

c J-24 y

I h

I

.~m m.

._m m..

6 I

e.

i TABLE II

~

sit 0KE EVENTS DATA - 01/01/86 - 12/31/94 ITEM OKT/

LER/

EVENT REPGRT LorATIG8 EXTENT EST.

OPER.

PLT CAUSE DETECT 1511.

1511.

CIBF.

' !2M!!

PGER 30 PLT ID OTNER DAg TI9E_

• t_T ANJ N

DtR.

IKPJ SYS Spq0KE IEANS CIB58

_C_INW EFFECT EFFECT EFFECT 2

g 103 27 Corm.

07/07/89 Auxitircy Light

<20 100%

Plant Elect. Visual Power X W1nr Power Plan *' Nonc j

Fait.

Built'eng min.

Power DC Pur Fail.

Supply Intern. Supply DC Pwr Hist.

}

Distr.

Xformr Xformr Dist(1) 104 1

Conp.

07/11/89 --

Auxilia9 Lisit

<20 0%

ESFAS Elect. Troubt Sequncr Elect.

Sequncr ESFAS None Fait.

Building min.

Power Fail.

Alarm Power Intern. Power (1)

Hist.

t Supply Supply 105 76 conp.

07/12/89 --

Turbine Light

<5 Power Plant Elect. Visual Alt.

Breaker Alt.

None None i

fait.

fiullding min.

Oper.

AC Pur Fail.

Feed intern. Feed Hist.

r Distr.

CB CB 106 91 Comp.

C7/18/89 --

Auxiliary Light

<10 Power Plant Elect. Visual Battery xformr Battery None None Fait.

Building (Smoke min.

Oper.

PC Pwr Fail.

Charger Relay Charge

• Hist.

Smelt)

Distr.

Xformr Intern.

1C7 28 Conp.

07/19/89 --

Auxiliary Light

<10 0%

HPSI Elect. Visual HPSI Motor HPSI None None-5 Fait.

Building min.

Power Fail.

Isol Oper.

Isol Cold Hist.

f Distr.

Valve Intern. Valve Shutdn 108 760 89-23 07/23/89 0920 Diesel Gen.

Light

<5 0%

EDG OverSt Visual Engine Elect. Engine EDG(1)

None-Bu*' ding min.

Power Matt Contt Intern. Contt 0% Pwr

=

Pane l Panel 109 18 Conp.

08/26,'B9 --

Reactor Lig%t

<10 0%

Reactor Elect. Visual Pump Relay. Punp Reactor None-Fait.

Building min.

Power Recirc. Fai..

. Set Coit MG Set Recire. 0% Pwr Hist.

_ lay (1) t 110 80 C arap.

10/07/89 2303 Diesel Gen.

Medium

<30 100%

EDG Overht Fire DG Crant DG EDG(1)

None.

Fait Building min.

Power Matt Detect. Ergine Case Engine H i', t am LMil 111 35 Comp.

10/23/89 --

Auxiliary Light

<10 0%

CVCS overht Visual Chargng Motor Chargng CVCS(1) None-Fait.

Buildir.g (Burnng min.

Power Matt Pt.ap Bearing Ptsip 0% Pwr Hist.

Odor)

Motor Lube Motor

[

112 73 Conp.

?c/2<./89 --

Reactor Light

<10 0%

RHR Elect. Visual RHR Motor RHR RHR(1)

None-Fait.

Building min.

Power Fail.

Crossti Oper.

Crosstie

Refuel, i

Hist.

Valve Winding Valve i

+

J-25 i

r

?

I

s

-i TABLE II Mi41 EVENTS DATA - 01/01/86 - 12/31/94 ITEs4 DET/

LER/

EVENT REPtRT LOCAil0N EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

Cupr.

TRAIN poler 40 PLT ID OTIER DJA E Tile PLT AR_FA_

SIKKE Ot2 DEBE SY_S SpKEE IEAtiS CEBP.

CEBe.

EFFECT EFFECT EFFECT 113 323 89-10 10/27/89 0655 Turbine Heavy 00 100%

Turb-Overht Visuat Gener Bearing Gener Turb/Trp 1

Building (Evac.) min.

Pwr Gen.

Matt.

Xcitr tube Perm ReactTrp I

Bearng Magnet 114 74 Com.

10/29/C.3 2130

?.uxiliary Light

<1 Hr.

0%

Instr Elect. Visual-Static Invertr Static Instr None-6 Fait.

BJitding Power AC Pwr Fait.

Invertr Elect.

Invertr AC Pwr Refuel.

[

Hist.

Distr.

SCR Intern.

Dist(1) 115 58 Conp.

11/11/E9 1300 Diesel Gen.

Light

<5 0%

EDG Elect. Visual DG LO Breaker DG LO EDG(1)

None-Fait.

Building min.

Fower Fail.

Supply Contac. Supply Refuel.

Hist.

CB Coil CB 116 86 Conp.

11/19/89 1805 Turbine Light

<30 Power FW Overht Visual FW Punp Bearing FW FW(1)

Power f

Fait.

Building min.

Oper.

Matt Bearing Lube Pump Reduced Hist.

Oil 117 12 Comp.

11/21/89 --

Reactor Light

<10 Power HPCI Elect. Visual Gland Blower Gland HPCI None fait.

Building min.

Oper.

Fait.

Steam Motor Steam i

Hist.

Blower intern. Blower 118 23 Comp.

11/28/89 1544 Auxiliary Light

<10 100%

CVCS Overht Visual ChgPump Speed Chargng None None Fait.

Building (Smoke min.

Power Matt Speed Inersr Punp Hist.

Swlt)

Incrsr tubecil 119 2 72 89-33 12/01/89 1544 Auxiliary Light

<10 100%

CVCs overht Visual Pump Lube CVCS CVCS(1) Turbine Building min.

Power Matt Speed Oil Pump Trip /

Increasr ReactTrp 120 106 Comp.

12/03/89 --

Diesel Gen.

Light

<5 0%

EDG Overht Visual DG Fuel DG EDG(1)

None-Fail.

Building min.

Power Matt Engine Oil Engine 0% Pwr Hist.

?

121 106 Comp.

12/06/89 --

Turbine Light

<1 Hr.

Power Instr Elect. Visual 10KVA Capa.tr 10Kt4 Instr None fait.

Building Oper.

AC Pwr Fail.

Invertr Intern. Invertr AC Pwr Hist.

Distr.

Capactr Dist(S) 9 122 29 Comp.

12/09/89 0914 Auxiliary Meditsn

<30 100%

CVCS Overht Fire ChgPump Vari-Chargng CVCS(1) None fait.

Building min.

Power Matt Alarm Vari-Drive Pump Hist.

Drive Belts I

b l

h J-26

+

s

[

h 4

=

t N

(

IABLE II i

SMOKE EVENTS DATA - 01/01/86 - 12/31/94 i

.l ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT IMIT.

INIT.

C(BF.

TFAIN POLER g

PLT 10 OTHER D_ ATE TIq

_ PLT AREA SN(ME DUR MO_D_E SY.S

$NOKE SEAMS CMP.

CEDIB.

EFFECT EFFECT EFFECT 123 58 Canp.

12/13/89 0940 Diesel Gen.

Medium <30 0%

EDG Elect. Visual DG Eng Latch DG Eng EDG(1)

None-Fait.

Building min.

Power Fait.

Control Relay-Control Refuel.

Hist.

Cabinet Intern. Cabinet 124 54 Conp.

12/15/89 --

Auxilia Light

<10 100%

Elect. Visual IceCond CB IceCond Ice None Fait.

Buildin min.

Power Cond.

Fail.

Chiller Current Chiller Cond(1)

Hist.

CB Limiter CB i

125 38 Comp.

12/26/89 0800 Auxiliary Light

<10 1001 CVCS Overht Visual C69 Pmp Vari-Chargng CVCS(1) None Fait.

Building min.

Power Matl Vari-Drive Purrp Hist.

Drive Belts l

126 66 Comp.

01/11/90 1428 Service Water Light

<1 Mr.

Power NSW Elect. Visual ServWtr Motor ServWtr None None-l Fait.

Punphouse Oper.

Fail.

Pump Insul Punp 0% Pwr 6

Hist.

Motor Motor r

i 127 91 Conp.

01/23/90 1200 Diesel Gen.

Medium

<30 0%

EDG Overht Visual DG Fuel DG EDG(1)

None-(

Fait.

Building min.

Power Matt Engine Oil Engine 0% Pwr i

Hist.

128 11 Conp.

01/29/50 0231 Auxiliary Light

<30 100%

Rad.

Elect.

Rad.

Filter Mator RMS Air RMS(1) None Fait.

Building min.

Power Mcaitr. Fail.

Monitor Paper Insul Partict Hist.

Distr.

Drive Monitor 129 71 Conp.

03/02/90 --

Auxiliary Light

<5 C%

RPS Elect. Visual Reactor Breaker Reactor RPS(1)

None-Fait.

Building min.

Power Fail.

Trip Trip Trip C% Pwr Hist.

Breaker Coit Breaker 130 38 Comp.

03/03/90 0000 Auxiliary Light

<10 100%

CVCS Overht Visual Chg Pmp Vari-Chargng CVCS(1) None Fail.

Building min.

Power Matt Vari-Drive Pung iist.

Prive Belts 131 30 Conp.

03/14/90 1024 Auxiliary Light

<30 0%

ESFAS Elect. ESF Storage Relay Storage None None-Fall.

Building min.

Power Fail.

Fire ink tvl Coit Tnt tvl Refuel.

Hist.

Detect. Relay Relay 132 8

Conp.

03/30/89 --

Auxiliary Liq 5t

<10 0%

RHR Elect. Visual HtXchgr Motor HtXchgr RHR(1)

None-Fail.

Building min.

Power Fait.

Dischg Oper.

Dischg 0% Pwr i

Hist.

Valve Intern. Valve Y

i J-27

+

-. -_ _ _ ~..

s P

i TABLE Il 9EOKE EVENTS DATA - 01/01/86 - 12/31/96 i

t ITEle ' DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

CEDIP.

TRAIN P0iER N0.

PLY 10 OTNER DATE 118E_

PLT AREA SIEOKE DER g

SyS SequKE BEAN

• Ct9F.

(XBE.

EFFECT EFFECT -EFFECT

~

t 133 77 Conp.

04/02/90 --

Turbine Light

<1 Hr.

Power FW Elect. Visual Elect. Dio&

Elect. FW(1)

None Fai!.

Buitding Oper.

Fait.

Auto.

Auto.

Hist.

Posit.

Posit.

134 10 Conp.

04/09/90 1930 Auxiliary Light

<1 ar.

0%

RCS Elect. Visual Therm. Motor Therm. RCS(1)

None-Faii Building (Smolder)

Power Fait.

Barrier Oper.

Barrier 0% Pwr Hist.

Valve Insul Valve 135 59 Conp.

04/12/90 --

Auxiliary Light

<5 Power AFW Elect. Visual FW Dsch Motorer FW Dsch AFW(1) None

{

Fait.

Building min.

Oper.

Fail.

Isot Oper.

Isot Hist.

Valve Insul Valve I

136 51 Conp.

04/22/90 1210 Auxiliary Light

<30 0%

RCS Elect. Visual Prszr Breaker Prszr None None-t Fait.

Building min.

Power Fait.

Heater Trip Heater Cold Hist.

CB Coil CB Shutdn g

137 2

Comp.

04/24/90 --

Auxiliary Light

<10 Power RHR Overht Visual RHR Motor CHR RHR(1) None Fait.

Building min.

Oper.

Matt Ptep Bearing Pung Hist.

Motor Lube Motor

}

138 15 Conp.

04/24/90 0707 Reactor Lignt

<20 0%

RPS Elect. Visual APRM Relay RPS RPS(1) N OT -

Fai1.

Buitding min.

Power Fait.

Sensci Coil APRM 0% Pwr Hist.

Relay Sensor 139 18 Comp.

04/25/90 -.

Service Water Light

<1 Hr.

0%

ESW Elect. Visual Htxchgr Xformr-

RHR, ESW(1)

None-Fait.

Ptnphouse Power Fait.

Iso!Viv Intern. HtXchgr 0% Pwr j

Hist.

Mformr IsotVtv i

140 54 Comp.

05/03/90 2200 Auxiliary Light

<30 0%

Cont.

Overht Visual CS Motor CS None None-i' Fait.

Building min.

Power Spray Matt Pump Bearing Pwp Refuel.

Hist.

Motor Lube Motor

)

141 86 Conp.

05/14/90 1456 Reactor Light

<5 100%

RHR Elect. Fire Jockey Motor RHR None None Fait.

Building min.

Power Fait.

Alarm Pwp Insut Jockey Hist.

Moto" Ptnp

[

142 60 Como.

05/17/90 --

Auxiliary Light

<30 Power Instr Elect. Visual Instr Invertr in,tr None Nc,ne Fait.

Building (Smoke min.

Oper.

AC Pwr Fait.

Power Relay Power Hist.

Smell)

Uistr.

Invertr Intern. Invertr J-28 s

t i

I u

__m _..._.

._m_

.--m m

_m.,

t.

t TANLE II SNOKE EVENTS DATA - 01/01/86 - 12/31/94.

ITEM DKTI trR/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT C2SE DETECT tuli.

INIT.

CDIN>.

TRAIN POER NO PLT ID OTMER DATE TIE PL_.,T_ djkEA SMOKE D_W M

S,.lS.

seg)KE EANS CGN5 EXBW.

EFFECT EFFECT EFFECT

_2 143 41 ronp.

05/28/90 0745 Auxiliary Light

<10 100%

Contl Elect. Visual CRD voltage CRD CRD(1) None fait.

Building Hist.

min.

Power Rod Fait.

KG Set Regul. MG Set Drive Intern.

144 97 Conp.

05/29/90 1408 Auxiliary Light

<1 Nr.

Power Penetr Elect. Visual Penetr Circuit Penetr Penetr None fait.

Building Oper.

Room Fail.

Room Breaker Room Room Hist.

HVAC Fan CB Coit Fan HVAC(1) 145 53 Comp.

05/30/90 --

Reactor Light

<1 Mr.

0%

Instr Elect. Visual UPS Xformr UPS In*tr None-Fait.

Building Power AC Pwr Fait.

Xformr Intern. Xformr AC Pwr 0% Pwr Hist.

Distr.

Dist(l) 146 28 Comp.

06/02/90 --

Turbine Light

<10 5%

Cond.

Overht Visual Cond.

Motor cond.

Cond(1) None fait.

Building min.

Power Matt Pung Bearing Punp

_t.

Motor Oil Motor 147 70 Comp.

06/05/90 1551 Auxiliary Light

<5 100%

CCW Elect. Visual CCW Motor CCW CCW(1) None Fait.

Building min.

Power Fait.

Pump Winding Punp Hist.

Motor Motor 148 10 Cony.

06/13/90 2222 Turbine Medita <30 48%

FW Elect. Visual FW Punp Motor FW Pump FW(1)

None Fait.

Building min.

Power Fait.

Motor Winding Motor Hist.

149 84 Comp.

06/13/90 --

Reactor Light

<20 0%

RCIC Elect. Visual RCIC CB RCIC None None-Fail.

Building min.

Power Fail.

Valve Contacr Valve 0% Pwr Hist.

CB Coil CB 150 79 Comp.

06/27/90 0920 keactor Light

<10 Power Contt Elect. Audio CRD Motor CRD CRD(1) None Fait.

Building min.

Oper.

Rod Fail.

Alarm MG Set Insul MG Set Hist.

Drive Moto*

Motor 151 96 Conp.

07/01/90 --

Diesel Gen.

Light

<10 60%

EDG Overht Visual DG Air Comt-OG Air hone None Fait.

Buiiding min.

Power Mat!

Conpr Lube Conpr Hist.

Oil 152 108 Conp.

07/06/90 1130 Switch Yard Light

<1 Mr.

0%

Plant Elect. Visual Xformr Xformr Main Plant None-f Fail.

Power AC Pwi Fail.

Term.

Intern. Xformr AC Pwr Hot Y

Hist.

Distr.

Box Dist(1) Stdby I

J-ES b

--.-----L

..-m

_m

~

m m._.~

,_mm

_.....a TABLE II SNOKE EVENTS DATA - 01/01/86 - 12/31/96 ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT LST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

COMP.

TRAIN P0hER g

PLY ID OTNER DATE lipg PLT AR_EA SMWE DUR M(DE SYS SNOKE 8EANS CtMP.

CCBS.

EFFECT EFFECT EFFECT 153 413 90-28 07/23/90 1135 Control Medium 3 Hrs-0%

Contt Overht Visual Contt Fan Conti Contt None-Room 2Cmin. Power Room Matt Room Belt Room Room 0% Pwr HVAC AMU Matt AHU

.HVAC(1) 154 92 Comp.

07/23/90 1334 Auxiliary Light

<30 Power Plant Elect. Audio 3KV Xforer. 3KV Plant None Fait.

Building (Smoke min.

Oper.

AC Pwr Fait.

Alarm XFormr Insul Xformr AC Pwr Hist.

In Room)

Distr.

Dist(1) 155 40 Comp.

08/02/90 --

Diesel Gen.

Light

<5 0%

EDG Overht Visual Engine Bearing DG Eng EDG(1)

None-l Fait.

Building min.

Power Matt Turbo-Lube Turbo-Cold Hist.

Charger Charger Shutdn 1

156 36 Cmp.

08/19/88 1846 Reactor Light

<30 Power NSSSS Elect. Visual FirDrn Relay FirDrn None None l

Fai1.

Buitdirs min.

Oper.

Fait.

Temp Coit Tenp Hist.

Hiirip HiTrip Relay Relay h

157 39 Conp.

09/10/90 0001 Auxiliary Light

<30 97%

Instr Elect. Annunc DC Pwr Elect. DC Instr None-Fait.

Building min.

Power AC Pwr Fail.

Alarm Supply. Intern. Power AC Pwr 0% Pwr Hist.

Distr.

AC Input Supply (1)

[

150 95 Comp.

09/21/90 1450 Auxiliary Light

<5 Power Plant Elect. Visual Battery Circuit Battery None None

[

Fait.

Building min.

Oper.

DC Pwr Fait.

Charger Breaker Charger Hist.

Distr.

CB Intern. CB i

i L

159 35 Comp.

10/12/90 --

Die et Gen.

Light

<10 0%

EDG Elect. Visual DG LO Breaker DG LO EDG(1)

None-

[

Fail.

Building min.

Power Fait.

Heater Xformr Heater 0% Pwr Hist.

CB Intern. CB 160 47 Conp.

10/17/90 1730 Auxiliary Light

<10 0%

Cont

• Elect. Smoke Reactor Breaker licactor None None-Fait.

Building min.

Power Rod Fait.

Detect. Trip Elect. Trip Cold H i s*:.

Drive Bypass Contac. Bypass Shutdn Breaker Breaker 161 109 Cwo.

10/18/90 1211 Turbine Light

<5 Pc-er MS Elect. Visuel C*pactr Elect. MS Stm None None Faio.

Building.

(Smoke min.

Oper.

Fail.

Solen.

Intern. Trap i

Hist.

Residue)

Valve Isol Vtv 162 72 Conp.

10/21/90 --

Service Water Light

<1 Hr.

0%

NSW Elect. Visual ServWtr Motor ServWir None None-Fail.

Punphouse Power Fait.

Ptsnp Intern. 6tmp C% Pwr Hist.

' lot or Motor c

i.

J-30

.*; i i

i r

b

-. ~ ~_ - _. _ - - _..

t.

4 r

TABLE !!

SMOKE EW NTS DATA - 01/01/86 - 12/31/94-

-ITEM IM(T/

LER/

EWuf ' REP 0p? LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT " INIT.

INIT.

CIBIP.

TRAIN P0hER uD PLT ID OTIER DA

'TisE' PLT AREA SENE DLR DEBE E3 SMRE MANS CIBP.

C(NE.

EFFECT EFFECT EFFECT J

163 96 Comp.

11/08/90 1050 Auxiliary Light

<20 0% _

Plant Elect. Smoke Battery Charger Battery Plant None Fait.

Building min.

Power DC Pwr Fait.

Alarm Charger Intern. Charger DC Pwr Hist.

i Distr.

Shunt Dist(1) i 164 8

conp.

11/20/90 --

Auxiliary Light

<5 Power RHR Ete:t. Visual Recire Motor Recirc RHR(1) None

'iail.

Building min.

Oper.

Fail.

Punp Oper.

Pump Hist.

Dischg Intern. Dischg i

Valve Valve 165 97 Conp.

11/26/90 --

Dieset Gen.

Light

<1 Hr.

Power EDG Elect. Visual DG Air Motor DG Air EDG(1) None

[

I Fai(.

Butiding Oper.

Fail.

Compr Intesn. Compr Hist.

Motor 166 46 Conp.

12/05/90 1736 Turbine Light 51 Hr.

0%

Plant Elect. Visual 600VAe ' Tint 600VAC Ptant None-

[

Fait.

Building Power AC Pwr Fail.

S. apply trif Supply AC Pwr 0% Pwr, Hist.

D ht r.

Breaker Coil Breaker Dist(1) 167 27 Comp.

12/08/90 --

Auxili7ry Lignt

<10 0%

AFW Overht Visual AFW Ptsrp AFW AFW(1)

None-Fail.

Building min.

Power Matt Pump Packing Pump Cold Hist.

i Shutdn 168 74 Conp.

01/03/91 1005 Diesel Gen.

Light

<5 Power EDG Overht Visual DG Fuel DG EDG(1) None Fail.

Building

liin, opet.

Matt Engine Oil Engine.

Hist.

t 169 5

Conn.

01/06/91 2053 Turbine Medium

<1 Nr.

>2%

Turb-Overht Visual Gener. Bearing Gener.

T-G Turb Fait.

Building Power Gener. Matt Magnet Lube Magnet Trip i

Hist.

Bearing Oil Bearing (Manual) 170 47 Comp.

02/17/91 --

Service Water Light

<10 100%

NSW Overht Visual ServWtr Motor JervWtr NSW(1) None 4

Fail.

Purphouse min.

Power Matt Ptyp Winding Pump Hist.

Motor Motor 171 61 Cong.

02/21/91 0830 Auxiliary Light'

<30 0%

CVCS Elect. Visual Aux Motor Aux None None-fait.

Building min.

Pcwer Fait.

Oil Intern. Dit Cold Hist.

i Pnp Mot Pmp Mot Shutdn r

1 72 368 91-08 03/09/91 0918 Controt Light

<5 0%

Contt Overht Smoke DG

-Fuet None-Room min.

Fower Room Matt Detect. Exhaust Oil 0% Pwr HVAC D

J-31 P

l I

1

TABLE Il SMOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DKT/

LER/

EVENT REPORT LUCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

COMP.

TRAIN POLER g

PLT ID OTNER DALE TIIE PLT AREA SMOKE INE 8_KBE SJS SMOKE IEANS CIMP.

CIBW.

EFFECT EFFECT EFFECT 173 80 Conp.

03/09/91 0727 Turbine Light

<5 100%

FW Elect. Visual FW Ptap Xfermr. FW Pump None None Fait.

Building min.

Power fait.

Conttr Resistr Conttr Hist.

174 86 Conp.

04/13/91 1345 Turbine Light

<30 93%

FW Overht Visual FW Punp Bearing FW FW(1)

Power Fail.

Building min.

Power Matt.

Bearisq Lutn Punp Reduced H i st t.

Oil 175-9 Cons.

03/27/41 --

Reactor Light

<5 Power HPCI Elect. Visual Test Motor Test NPCI None Fail.

Building min.

Oper.

Fait.

Returr$ Oper.

Return hist.

Valve Ler.ds Valve 176 66 Conp.

04/16/91 0001 Diesel Gen.

Light

<30 0%

EDG Elect. Visuit DG Air Motor DG Air EDG(1) None-Fait.

Building min.

Power Fait.

Conpr Intern. Start Refuel.

Hist.

Motor Cortpr 177 23 Comp.

04/27/91 --

Auxiliary Light (5

47%

RCS Elect. Visual PORV Circuit PORV None None Fait.

Building (Smoke min.

Power Fait.

Btock Breaker Block -

Hist, Smell)

Vtv CB Contacr Vlv CB 176 77 Conp.

05/03/91 --

Reactor Light

<1 Hr.

0%

RCIC Elect. Visuit Trip /

Solen.

Trip /

RCIC None-Fait.

Building Power Fait.

Thotti Coil Throttl Ol Pwr Hist.

Valve Valve 179 85 Comp.

05/04/91 1416 Auxiliary Light

<5 0%

AFW Elect. Visual AFW Motor AFW AP.;G )

None-Fait.

Building min.

Power Fait.

Pump Intern. Pump 0% Pwr Hist.

Motor Motor 180 282 91-04 05/09/91 1255 Auxiliary Light

<1C 85%

HPSI Elect. Visual Pip Elect. CVCS CVCS(1) h9ne-Building min.

Power Fai!.

Heat Intern. Eeat Reducng Tracing Tracing Pwr for Refuel.

181 107 Corp.

05/11/91 0524 Switch Yard Light

<1 Hr.

Power Plant Elect. Visual 13.8KV Breaker 13.8KV Plant None Fait.

Oper.

AC Pwr Fail.

Circuit Intern. Circuit AC Pwr Hist.

Distr.

Breaker Breaker Dist(Alt) 182 15 Conp.

05/19/91 1359 Reactor Light

<20 Power RPS Elect. Visual RPS Motor RPS RPS(1) None Fait.

Buildirr)

(Smoke min.

Oper.

Fail.

MG Set Insul MG Set Hist.

Smell)

Motor J-32

}

t

.. _ _. -. _.. ~.

.. - - -. - -. ~... - -........ - -

._ -. ~

l i

6 IABLE 11 SMOKE EVENTS DATA - 01/01/86 - 12/31/94 t

ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

COMP.

TRAIN POWER NO PLT 10 OTHER DATE TIE PL7 AREA SMOKE DUR OED_E

.SJS SMOKE MANS EIBIP.

Ct35.

EFFECT EFFECT EFFECT 2

t A

183 31 Com.

05/19/91 --

Auxiliary Light

<10 Power Cont.

Overht Visual Recire. Bearing Cont.

Cont.

None i

Fait.

Building min.

Ooer.

Coolns Matt Fan tube Recirc. Coot (1)

}

Hist.

Bearing fan 184

-9 Com.

05/30/91 --

Reactor Lisht

<1 Mr.

80%

HPCI Elect. Visual Pury Relay Turbine WCI None i

Fai!.

Buitding Power Fai!.

TurnGr Contac. Driven Hist.

Relay Pump i

185 029 91-02 06/15/91 2350 offsite

i. igh t

>2 88%

Plt Overht Visual Xformr Elect. Xformr Pit Reactor Mr.

Power AC Pur Matt Lightng Insul Lightng AC Pwr Trip Distr.

(Lightng)

Arrestr Arrestr Distr (Manual)

(

186 70 Com.

06/15/91 --

Auxiliary Light

<5 100%

RCS Elect. Visual RCJ Circuit RCS FCS None Fall.

Building (Smoke min.

Power Conti fait.

Contt Breaker Cont!

Contt Hist.

Residue)

Instr Instr Intern. Instr Instr (1)

CB CB 187 77 Comp.

09/06/91 --

Reactor Light

<1 Hr.

100%

RHR Elect.

Fire HtXchgr Breaker NtXchgr RHR(1) None i

Fail.

Buitding Power Fai!.

Alarm Vent Xformr Vent Hist.

Viv CB Intern, Viv CB 188 78 Conp.

09/11/91 --

Turbine Light

<1 Hr.

80%

FW Elect. TrouLle FW Pump Gear FW Punp FW(1)

None i

Fail.

Building Power fait.

Alarm Turning Solen.

Turning Hist.

Gear Coit Gear 189 31 Conr 09/13/91 --

Auxiliary Light

<30 Power Cont.

Elect. Visual Rad.

Motor Rad.

Cont.

None Fait.

Buildirg min.

Oper.

Rad.

Fait.

Sample Intern. Sample Rad.

Hist.

Monit.

Pmp Mot Pmp Mot Monit(1) 190 70 Conn.

09/17/91 --

Auxiliary Light

<5 0%

RHR Elect. Visual RHR Motor RHR RHR(1)

None-a Fail.

Building min.

Power Fait.

Intet Oper.

Intet Refuel.

Hist.

I Valve Intern. Valve 191 102 Conp.

09/25/91 --

Turbine Meditan

<1 Hr.

100%

FW Overht Visual FW Ptsnp Piping FW Pump FW(1)

None Fai!.

Buitding Power Matt Turbine Insul Hist.

Governr f

192 51 Copp.

09/27/91 1650 Auxiliary Light

<5 0%

CVCS Elect. Visual Chargng CB Chargng None None-I Fait.

Building min.

Power fait.

Pu@

Close Pump Refuel.

Hist.

CB Coit CB t

i l

J-33 e

_-.m.

.m._

m,_ _ _

p l

l l

l TABLE II SMOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEN

-DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

EteIP.

TRAIN POWER NO PLT ID OTNER DATE TIE PLT AREA SMOKE DE M

S.15 SNOKE MANS CGF.

CGW.

EFFECT EFFECT EFFECT i

193 40 Cono.

10/11/91 --

Auxiliary Light

• 5 01 CVCS Overht Visual Pump Gear Chargng CVCS(1) kone-Fait.

Building min.

Power Matt Speed Bow Pwp 0% Pwr Hist.

Inc rs.-

Oil i

194 2

Copp.

10/17/91 1418 Turbine Light

<20 100%

Cond.

Elect. V%al Cond.

Mctor Cond.

Cond(1) Reduced Fait.

Building min.

Power Fail.

Pwo Surge Pump Power Hist.

Motor Capac. Motor 195 4

Conp.

10/21/91 2015 Turbine Light

<20 Powar Turb-Elect. Visual Gener. Circuit Gener.

Turb-Power Fait.

Building (Smoke mia.

Oper.

Gener.

Fail.

Leads Breaker Leads Gener.

Reduced Hist.

Smelt)

Cootng Contacr Cooling 196 424 91-08 10/23/91 1110 Auxiliary Light 15 0%

Rad.

Elect. Visua; Rad.

Xformr Rad None None-Building min.

Power Monitr Fait.

Monitr Intern. mom tr 0% Pwr System Xformr xformr 197 26 Conp.

11/06/91 --

Reactor Light

<30 0%

RBCC Elect. Visual Drywell Panet Drywell RBCC(1) None-Fail.

Building min.

Power Fdit.

Chit ter Wiring Chiller 0% Pwr i

Hist.

Control Control i

148 54 Comp.

11/08/91 0056 Auxiliary Mediunt <30 100%

Plant Elect. Visual AC Pwr Pov'r AC Pwr Plant Power i

Fait.

Building min.

Power AC Pur Fail.

Bus Cables Bus AC Pwr Reduced Hist.

Distr.

Dist(1)

F 199 99 Conp.

11/18/91 --

Turbine Light

<1 Hr.

Power FW Elect. Visual FW Reg Circuit FW Reg None None Fait.

Building Oper.

Fait.

Isol Breaker Isol Hist.

Viv CB Coit Vlv CB i

200 54 Comp.

11/19/91 Auxiliary Light

<20 0%

Cont.

Person. Visual Cont.

Extens. Cont.

Cont.

None-Fait.

Building min.

Power Cooling Error Coolng Cord Cooling Coot (1) Cold Hist.

Fan Frictn Fan Sntdn 201 37 Cony.

11/27/91 --

Reactor Light

<5 Power RPS Elect. Visual IRM E let IRM RPS(1) None Fail.

Building min.

Oper.

Fail.

Voltge Intern. Voltge Hist.

Regul.

Regul.

f 202 37 Comp.

12/02/91 1100 Reactor Light

<20 0%

SBLC Overht Visual SLC Packing SLC None None-Fait.

Building min.

Power Matt Pwp Matt

. Pump 0% Pwr Hist.

Fan CB Coil Fan CB J-34

),

t a

e r

6 h

iABLt. II SNOKE EVENTS DATA - 01/01/86 - 12/31/94 6

k ITEM DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT 1511.

INIT.

COMP.

TRAIN POER NO PLT ID OTMER DJA TIE PLT AREA SNIEE DUR D_EBE S

SMDKE EATS Capu*.

C(BS.

EFFECT EFFECT EFFECT E

203 11 Comp.

01/02/92 2230 Switch Yard Light

<30 100%

Plant Elect.

Failure Xformr Fan Unit Plant kone

fail, min.

Power AC Pur Fait.

Alarm Fan Moter Aux AC Pwr j

Hist.

Distr.

Motor Insul Xformr Dist(1) 204 65 01/11/92 0230 Diesel Gen.

Light

<20 0%

EDG Overht Annunc DG Air Driv.

DG Air hone None-Buitding min.

Power Matt Alarm Compr Bett Compr 0% Pwr f

205 325 92-02 01/17/92 0215 control Light

<5 100%

Food Fire Food None-

{

Room min Power Cooking Alarm Cooking 0% Pwr i

206 71 Cocp.

03/17/92 --

Auxiliary Light

<5 0%

Contt Elect. Visual MG Set Voltge MG Set CRD(1)

None-Fait.

Building min.

Power iod Fail.

Voitge Regul. Pump Cold l

Hist.

Drive Regut.

Intern. CB Shutdn

+

2n7 352 92-04 03/21/92 --

Reactor Light

<10 0%

React E ect.

Visual HVAC Breaker HVAC React None-Building min.

Power Btdg Fait.

PwrSup Trip Pwesup Sidg 0% Pwr HVAC CB Coit CB HVAC

[

208 104 Conp.

04/10/92 2144 Auxiliary Light

<10 0%

AFW Elect. Visual AFW Motor AFW AFW(1)

None-Fait.

Building min.

Power Fail.

Swapovr Oper.

Swapovr Refuel.

Hist.

Valve Intern. Valve s

209 46 Comp.

04/21/92 --

Diesel Gen.

Light

<1 Hr.

95%

EDG Elect. Visual Bypass Breaker Bypass EDG(1) None Fail.

BuitJing Power Fail.

LO Pump Starter LO Pump i

y Hist.

CB Contac. CS I

210 26 Cong.

05/22/92 --

Reactor Light

<5 100%

RHR Elect. Visual RHR Motor RHR RHR(1) None l

t.

Fait.

Building min.

Power Fait.

Pump Stator Pump

{

Hist.

Motor Coil Motor 211 91 Conp.

06/02/91 0600 Turbine Light

<10 0%

Cond.

Elect. Visual Cond. ~ Motor Cond.

None None-Fait.

Building min.

Power Fail.

Demin. Oper.

Demin.

Cold l

Hist.

Motor IsolVlv Intern. IsotVlv Shutdn 29 2

Comp.

06/10/92 2100 Auxiliary Light

<1 Hr.

100%

AFW Elect. Visual Turb Elect. Turbine AFW(1) None Fait.

Building Power Fail.

Digitat I, tern. Driven Hist.

Control Puno

}

Panel F

f J-35 r

I i

.. m.

m

m m

.._.m

_m..

TABLE II SNnKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INti.

CDer.

TRAIN P0hER NO PLT ID OTHER DE M

PLT AREA M

DUR

_KBE S3 SNOKE SEANS EINF.'

COMB.

EFFECT EFFECT EFFECT p

213 387 92-10 06/13/92 1100 Other Bldgs Light

>2 2%

Offgas Overht

Temp, Casrc Charcol Charc None (Of f gas Recomb)

Mrs.

Power Eecombr Matt Detect. Guard Guard Distr.

Bed Bed t

214 59 Comp.

06/29/92 1345 Auxiliary Light

<5 100%

DC Elect. Visual Battery Rectifr Battery DC None Fail.

Building min.

Power Pwr Fail.

Charger Intern. Charger Pwr(1)

Hist.

Distr.

Rectifr i

215 80 Com.

06/29/92 De30 Diesel Gen.

Light

<20 100%

EDG Overht Fire DG Air tube DG Air EVA 1) None Fail.

Building min.

Power Matt Suppr Compr Oil Compr Hist.

Alarm 216 39 Com.

06/30/92 2038 Auxiliary

. Light

<1 Hr.

0%

CCW Elect. Visual CCW Limit CCW CCW(1) None-Fail.

Building Power Fail.

Isol Switch Isol-Refuel.

Hist.

Valve Intern. Valve 3

217 39 Com.

07/12/92 1854 Turbine

.ight

<30 0%

Cond.

Overht Annunc. Cond.

Puci.

Cond.

Cond(1) None-Fail.

Building Oower Matt Alarm Ptmip Cac* tr.g Pug 0% Pwr Hist.

Matt 218 33 Comp.

07/25/92 0152 Switch Yard Light

<20 100%

Plant Overht Fire Unit Bus Unit Plant None Fail.

min.

Power AC Pwr Matt Alarm Aux insul Aux AC Pwr

=

Hist.

Distr.

Xformr Xformr Dist(1) 219 4t Com.

07/28/92 0241 Diesel Gen.

Light

<5 0%

EDG Elect. Visual Jacket Motor Jacket EDG(1)

None-Fail.

Building min.

Power Fail.

Wa's er Insul Water Refuel.

Hist.

Pmp Mat Pmp Mot i

220 5

Com.

08/14/92 --

Reactor Light

<5 Power HPCI t.

Visual Aux Oil Circuit Aux Oil HPCI None Fail.

Building min.

Oper.

Fail.

Punp Breaker Pug Hist.

g CB Intern. CB 221 104 Com.

08/20/92 0700 Turbine Light

<20 100%

ESFAS Elect. Audio Card Power Card None None Fail.

Building (Smoke min.

Power Fail.

Alarm Rack Supply Rack Hist.

Smell)

Pwr Sup Intern. Pwr Sup i

222 17 Com.

08/21/92 --

Containment Light

<10 100%

Cont.

Elect. Visual Drywell Fan Drywell Cont.

None

fait, min.

Power Atmos Fail.

Cooling Control Cooling Atmos Hist.

Cooling Fan Relay Fin Cool.(1) s J-36

't i i

E TABLE 11 SMOKE EVENTS DATA - 01/01/86 - 12/31/94 l TEM DKT/

LER/

EVENT REPORT LOCATION ENTENT EST.

CPER.

PLT CAUSE DETECT INIT.

INIT.

CENF.

TRA!M POWER NO PLT ID OTNER DATE g

PLY AREA SMOKE DE E

SYS f90KE SEAMS CupF.

COIS EFFECT EFFEC 1 EFFECT 223 86 Comp.

08/28/92 1723 Turbine Light

<5 10%

Turb-Overht Visual Gener

, tor T-G Turb-Power fait.

Building min.

Power Gener. Matt Re*

Frictn. Gener.

Gener.

Reduced Hist.

224 46 Com.

08/31/92 --

Dieset Gen.

Light

<1 Hr.

0%

EDG Elect. Visual. Bypass Motor Bypass EDG(1)

Nor.e-Fait.

Buildir.g (Smoke Power Fait.

LO Pump Insut LO l'mp Refuet Hist.

Residue)

Motor Motor 225 78 Comp.

09/03/92 --

Turbine tight

<1 Hr.

0%

FW Elect. Visual FW Stop Breaker FW Stop rW(1)

None-Fait.

Building Power Fail.

Valve Reverse Valve 0% Pwr Hist.

CB Contac CB 226 85 Conp.

09/25/92 --

Service Water Light

<5 0%

NSW Elect. Visual SWBoost Breaker SWBoost NSW(1)

None-Fait.

Pmphouse min.

Power Fait.

Punp Closing Pump 0% Pwr Hist.

CB Coil CB 227 46 Com.

10/05/92 --

Turbine Light

<20 0%

Cond.

Elect. Visual Cond.

Motor Cond.

Cond(1) None-Fait.

Building min.

Power Fail.

Shutof f Oper.

Shutoff 0% Pwr Hist.

Valve Intern. Valve 228 11 Comp.

10/17/92 2014 Auxiliary Light

<5 0%

DC Elect. Visual Battery Charger Battery CC None-Fait.

Building (Burng min.

Power Pwr Fait.

Charger Intern. Charger Pwr Cold Hist.

Smell)

Distr.

Dist(1) Shutcn 229 324 92-09 10/30/92 1130 Dieset Gen.

Meditm

>8 0%

Welding Smoke Welding --

None-Building Mrs.

Power Oper.

Detect.

Matt 0% Pwr 230 34 Comp.

10/31/92 --

Reactor Light

<1 Hr.

0%

P t ar-t Elect. Visual Battery CB Battery None None-Fait.

Building Power AC Pwr Fait.

Charger Trip Charger Refuel.

Hist.

Distr.

CB Coit 231 296 92-04 11/04/92 1900 Reactor Heavy

>1 0%

xotherm Visual Epoxy None-Building (Temp.

Hour Power Chem.

Grout 0% Pwr Evac.)

React.

Compound 232 86 Com.

11/04/92 1006 Control Light

<5 100%

RPS Elect. Visual RPS Elect. RPS RPS Power Fait.

Room min.

Power Fail.

Div I Intern. Div I Red'x/

Hist.

Contact Contact SCRAM J-37

m.

__.___....m 4

IABLE II SNOKE EVENTS DATA - 01/01/86 - 12/31/94 I

ITEN DET/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

tutT.

COMP.

TRAIN P0hER h

g PLT 10 OTHER DJA M

PLT AREA SNOKE DUR M

SYS SMOKE DEANS CIEN*.

M2 EFFECT EfFECT EffECT 233 105 Com.

11/09/92 1025 Auxiliary Light

<5 0%

HPS!

Elect. Visual Hot Leg Motor Hot Leg HPS!(1) None-fait.

Building mir.

Power Fait.

Isot Oper.

Isot 0% Pwr Hist.

Valve Intern. Valve 234 29 Comp.

11/21/92 --

Auxiliary Light

<20 Power HPSI overht visual St Pump St None None Fait.

Building min.

Oper.

Matt Recire. Seat Recirc.

Hist.

Ptmp Matt Pump 235 41 Co@.

12/10/92 --

Auxiliary Light

<5 100%

CVCS Overht visual Chg Pmp vari-Chargng CVCS(1) None h-fait.

Building min.

Power Matt Vari-Drive Puy Hist.

Drive Betts 236 16 Comp.

12/16/92 --

Service Water Light

<1 Hr.

100%

NSW Elect. Visual SWPump Breaker ServWtr NSW(1) None Fait.

Ptsphouse Power Fait.

Circuit Trip Punp Hist.

Breaker Coit C8 237 60 Com.

12/19/92 1420 Controt Light

<10 100%

Instr Elect. Vinsat Annunc Power Annunc None None Fai1.

Room min.

Power AC Pwr Fait.

Power Suppty Power Hist.

Distr.

Supply Intern. SJpply 238 71 Conp.

01/04/93 --

Auxiliary Light

<5 100%

CVCS overht Visual Packing Motor Packing CVCS(1) None i

Fait.

Building (Smoke min.

Power Matt Cooting Intern. Cooling Hist.

Smell)

Pnp Mot Pep Mot 239 20 Conp.

01/08/93 1630 Auxiliary Light

<30 Power-Instr Elect. Visual Battery Invertr Battery None None fait.

Building min.

Oper.

AC Pur fait.

Invertr Intern. Invertr Hist.

Distr.

i 240 6

Conp.

01/14/93 1440 Auxiliary Medium

<30 98%

CVCS Overht Fire Chg Pmp Vari-Chargng CVCS(1) None Fait.

Building min.

Power Matt Alarm Vari-Drive Punp Hist.

Drive Betts 241 4

Conp.

02/07/93 --

Reactor Light

<20 Power RPS Overht Fire MG Set Bearing MG Set RPS(1) None fait.

Building min.

Oper.

Matt Alarm Bearing tube Hist.

242 106 Comp.

02/09/93 2236 Turt;ine Light

<20 0%

Cond.

Overht Bearing cond.

Motor Cond.

Cond(1) None-Fail.

Building min.

Power Matt Tenp Booster Bearing Booster 0% Pwr Hist.

Alarm Pnp Mot Oil Pmp Mot J-38 1

~

l

rhb TABLE II SNOKE EVENTS DATA - 01/01/86 - 12/31/94 ITE91 DICT /

LER/

EVENT REPORT iOCATION EXTENT EST.

OPER.

PLT CAUSE DETECT tulT.

INIT.

CEDIP.

TRAIN P0bER m3 PLY ID OTNER DJA litg PLY AREA SB M E DLR I _G E

_SlS 9EE 94' AIIS Ct3P.

CtBW.

EFFECT EFFECT EFFECT 243 106 Comp.

02/10/93 0015 Auxiliary Light

<5 0%

RHR Elect. Visual Cid Leg Motor Cld Leg RHR(1)

None.

Fait.

Building min.

Power Fait.

Isot Oper.

Isot 0% Pwr Hist.

Valve Intern. Valve 244 31 Cump.

02/11/93 --

Auxiliary Medium <30 100%

Plant Elect, Visual Battery Elect. Battery None None Fall.

Building min.

Power DC Pwr Fait.

Cett Contac. Cett Hist.

Distr.

Bank Bank 245 52 Conp.

03/03/93 --

Reactor Light

<5 0%

SBLC Overht Visual Ptsrp Packing SBLC SBL C'.1 ) None-Fait.

Building min.

Power Matt Packing Mat t Ptep Cold Hist.

Ring Shutdn 246 31 Cocp.

03/11/93 --

Auxiliary Light

<5 0%

Instr Elect. Visual Static Voltmtr Static Instr None-Fait.

Building min.

Power AC Pwr Fait.

Invertr Intern. Invertr AC Pwr 0% Pur Hist.

Distr.

Voltmtr Dist(1) 247 8

Conp.

03/12/93 --

Dieset Gen.

Light

<5 0%

EDG Elect. Visual FO Punp Elect. DG FO EDG(1)

None-Fait.

Building min.

Power fait.

Control Intern. Transfr Refuel.

Hist.

Xformr Ptsnp 248 109 Comp.

03/14/93 1813 Diesel Gen.

Light

<5 100%

EDG Elect. Fire DG DC Circuit DG DC EDG(1) None Fait.

Building (Smoke min.

Power fait.

Alarm Control Breaker Control Hist.

Residue)

Pant CB Rectif r Panet 249 24 Comp.

03/16/93 --

Auxiliary Light

<5 0%

RPS Elect. Visual 480VAC Power 480VAC None None-Fail.

Building min.

Power Fait.

Power Supply Power Refuel.

Hist.

Supply Intern. Supply 250 99 Comp.

03/18/93 --

Auxiliary Light

<1 Hr.

100%

Cont.

E l ec t. Visual Cont Circuit Cont None None Fail.

Building Power Cool.

Fait.

Cool Breaker Cool Hist.

HVAC Fan CB Coit Fan 251 89 Cong.

03/23/93 --

Auxiliary Light 41 Mr.

0%

HPSI Overht Visual HPSI Motor HPS!

HPSI(1) None-Fait.

Buitding Power Mat 1 Punp Bearing Pump Refuet.

Hist.

Motor Oil Motor 252 4

Comp.

03/27/93 2055 Controt Light

<5 0%

RPS Elect. Annta r IRM Elect.

IRM None None-Fait.

Room min.

Power fait.

Alarm Power Resistr Power Refuel.

Hist.

Suppty Suppty J-39

- - = - -

TASLE II i

SMOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DET/

LER/

EVENT REPORT LOCATI(El EXTENT EST.

OPER.

PLT CAUSE DETECT tutT.

INIT.

COMP.

TRAIN POWER NO PLT 10 OTNER DATE lig PLT AREA SNOKE DUR M

HS Su,_o_KE MANS M,

CGE.

EFFECT EFFECT EFFECT A

253 54 Comp.

03/31/93 --

Auxiliary Light

<5 0%

CVCS Elect. Visual Chargng Circuit Chargng None None-l Fail.

Building min.

Power Fait.

_ Pump Breaker Pump 0% Pwr i

Hist.

CS Intern. CB 254 60 Comp.

04/22/93 --

Auxiliary Light

<5 100%

Cont.

Elect. Visual RadMon Motor RadMon Cont.

None Fait.

Building min.

Power R&d.

Fait.

Sample Intern. Sanple Rad.

7 Hist.

Monit.

Fan Mot Fan Mot Monit(1)

~

255 327 93-13 05/14/93 1315 Other Heavy 2 Hrs-0%

Welding Fire Welding --

None-Buildings (Evac.) 20 min.

Power Oper.

Atarm Matt 0% Pwr 256 15 Comp.

05/24/93 0820 Turbine Light

<5 0%

Cond.

Elect. Visual Drain Circuit Drain Nore None-Fait.

Building min.

Power fail.

Cooler Breaker Cooler Refuel.

I Mist.

Iso!Vlv Intern. IsolVlv 257 75 Comp.

05/25/93 --

Auxiliary Light

<5 0%

CVCS overht Visual Pump Seat' Charg CVCS(1) None-Fail.

Building min.

Power Matt Mech.

Matt Purp 0% Pwr Hist.

Seal l

258 45 Conp.

06/02/93 1513 Auxiliary Light

<10 Power Instr Elect. Audio / Static Xformr Static Instr None Fait.

Building min.

Oper.

AC Pwr Fail.

Visual Invertr Intern. Invertr AC Pwr Hist.

Distr.

Alarm Xformr Dist(1)

I I

259 108 Comp.

06/16/93 0055 Turbine Light

<5 0%

FW Elect. Visual FW Pnp Control FW None None-Fait.

Building min.

Power Fait.

Turbine Panel Turbine Refuel.

I 3

i Hist.

Control Intern. Driven Panet Punp 260 96 Conp.

06/26/93 --

Auxiliary Light

<20 0%

RCS Elect. Visual Prstr Elect. Prszr None None-Fait.

Building min.

Power Fait.

Htr Pwr Intern. Heater 0% Pwr 4

Hist.

Conttr 1

261 29 Conp.

07/15/93 0158 Auxiliary Light

<30 100%

CVCS Elect. P mp Chargns Motor Chargng CVCS(1) None L

i Fait.

Building min.

Power Fait.

Overflo Ptsnp Leads Pump i

Hist.

Trip Motor 262 42 Conp.

07/19/93 1600 Auxiliary Light

<5 Power RPS Elect. Visual IRM Relay IRM None None fait.

Building min.

Oper.

Fait.

HiFlux Coit HiFlux f

Hist.

Block.

Block.

Relay Relay J-40 7

i L

1; ?

- - =

t

ft TABLE 11 SIIOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEft OKTI LER/

kVENT REPtRT LOCAft(Ni EXTENT EST.

OPER.

PLT CAUSE DETECT INIT.

INIT.

CINEP.

TRAIN poler J

WO PLT ID OTNER DATE TI9E PLT AREA SIEEE E

M SJS 58e0KE BEANS CIBr.

' CIES.

EFFECT EFFECT EFFECT i

263 32 Comp.

07/24/93 --

Auxitiery Light

<1 Hr.

Power DC Elect. Visual Battery Surge Battery DC None t-Fait.

Building Oper.

Pwr Fail.

Charger Suppres Charger Pwr(1)

Hist.

Distr.

SurgSup intern.

264 58 Comp.

08/13/93 --

Auxiliary Light

<30 Power Rad Overht Smoke RMS Pump RMS RMS(1) None Fall.

Building min.

CDer.

Monitor.

Alarm Sanple Intern. Sample Hist.

Pmp Punp 265 29 conp.

03/15/93 2154 Turbine Light

<5 50%

FW Elect. Visual FW Pump Motor FW None None Fait.

Building min.

Power Fait.

Motor Stator Pupp Hist.

i T

266 82 Comp.

08/21/93 1331 Auxiliary Light

<1 Hr.

100%

Instr Elect. Visual Invertr Capactr Invertr Instr None l

Fail.

Building Power AC Pwr Fail.

Capactr Matt AC Pwr Hist.

Distr.

Dist(1) 1 267 46 Conp.

09/11/93 0410 Turbine Light

<1 Hr.

100%

FW Overht visual FW LO Lube FW LO FW(1)

Reduced Fail.

Building Power Matt Pump Oil Pump Power 3

Hist.

268 112 Conp.

09/13/93 0330 Auxiliary Light

<20 100%

Instr Elect.

Visual 7.5KVA Capac.

7.5KVA Instr None Fail.

Building min.

Power AC Pwr Fail.

Invertr Intern. Invertr AC Pwr Hist.

[

Distr.

Motor Capac.

Dist(1) i 269 76 Comp.

10/05/93 --

Diesel Gen.

Light

<5 0%

EDG Overht Visual DG Eng Fuel DG Eng EDG(1)

None-

[

Fait.

Building min.

Power Matt fuet Oil Fuel 0% Pwr Hist.

Inject.

Inject.

{

270 36 Conp.

10/28/93 0100 Turbine Light

<5 0%

Plant Elect. Visual Altern CB Altern None None-I r

fail.

Building min.

Power AC Pwr fail.

Feeder Test Feeder 0% Pwr Hist.

Distr.

CB Button CB

[

2 71 92 Conp.

11/10/93 0845 Auxiliary Light

<1 Hr.

Power Instr Elect. Visual 480VAC Unknown 480VAC Instr None Fail.

Building (Smoke Oper.

AC Pwr Fail, Xformr Xformr AC Pwr i

Hist.

In Room)

Distr.

Dist(1) 2 72 96 Comp.

11/13/93 2200 Auxiliary Light

<30 0%

Instr Elect. Annunc 7.5KVA Capac.

7.5KVA Instr None-

't Fail.

Building (Smoke min.

Power AC Phr Fait.

Alarm Invertr Intern. Invertr AC Pwr 0% Pwr Hist.

Smett)

Distr.

Capac.

Dist(1)

J-41 i

i l

t i

TABLE !!

SMOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DKT/

LER/

EVENT REPORT LOCATION EXTENT EST.

OPE R.

PLT CAUSE DETECT INIT.

INIT.

CEBIP.

TRAIN POKR g

PLT ID OTIER DATE TIIE PLT AREA 5B M E DUR M

SYS SMOKE IEANS CESP.

CGW.

EFFECT EFFECT EFFECT 2 73 48 Comp.

11/24/93 --

Switchgear Light

<10 100%

CCW Elect.. Visual CCW Circuit CCW CCW(1) None Fait.

Room min.

Power Fait.

Ptsp Breaker Ptsp Hist.

CB Intern. CB 2 74 86 Conp.

12/19/93 1350 Reactor Light

<10 100%

Plant Elect. Visual Battery Charger Battery None None Fait.

Building min.

Power DC Pwr Fail.

Charger Firing Charger Hist.

Distr. Distr.

Board 275 52 Cor p.

02/01/94 --

Diesel Gen.

Light

<1 Mr.

100%

EDG Overtht Visual Jacket Pump Jacket EDG(1) None Fall.

Building Power Matt WtrHtr Motor WtrHtr Hist.

Pump Winding Pump 276 16 Comp.

02/04/94 2310 Service Water Light

<5 0%

NSW Overht Visual Service Packing Service NSW(1)

None-Fail.

Ptenphouse min.

Power Matt Water Matt Water.

0% Pwr Hist.

Pump Ptmp 277 41 Comp.

02/08/94 2100 Auxiliary

-isht

<5 100%

CVCS Overht Visual Chg Pmp Vari-Chargng CVCS(1) None Fail.

Building min.

Power Matt Vari-Drive Ptap Hist.

Drive Belts 278 16 Comp.

02/12/94 --

Dieset Gen.

Light

<5 25%

EDG Overht Visual DG Air Fuel DG EDG(1) None faii.

Building min.

Power Matt Inlet Oil Engine Hist.

Valve 279 78 Cornp.

02/23/94 --

Reactor Light

<1 Hr.

Power RPS Elect. Visual MG Set Relay RPS RPS(1) None Fait.

Building Oper.

Fail.

Relay Matt MG Set Hist.

280 269 94-02 02/26/94 0657 Turbine Light

<10 100%

Plt Elect. Visual ICS Elect.

ICS Pit Turbine Building min.

Power AC Pwr Fait.

Power Intern. Power AC Pwr Trip /

Distr.

Supply Supply Distr Reactor Trip 281 69 Conp.

03/05/94 --

Reactor Light

<10 0%

Reactor Elect. Visual RR Ptsnp breaker RR Pump None None-Fail.

Building min.

Power Recirc. Fail.

Trip Trip Trip Refuel.

Hist.

Breaker Coit Breaker J-42 4

t TABLE II SMDKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM IMCT/

LER/

E'WENT REPORT LOCATIcel EXTENT EST.

(PER.

PLY CAUSE DE1ECT IBIT.

INIT.

CGF.

TRAIN POER g

PLY 10 OTER DATE TIE _

PLT AREA SMDKE DLR S_EBE SYS SMDKE KANS CGF.

CGE.

EFFECT EFFECT EFFECT 2n2 47 Conp.

03/07/94 --

Auxiliary Light

<1 Hr.

0%

Ice Elect. Visual Ice Chi t ter Ice Ice None-Fall.

Building Power Cond.

Fait.

Cond.

Motor Cond.

Cond(1) Refuel.

Hist.

Distr.

Chiller Intern. Chitter 283 52 Comp.

03/10/04 --

Reactor Light

<1 Hr.

Power Contt Overht Visual CRD Bearing CRD CRD(1) None Fall.

Building Oper.

Rod Matt Ptsp Libe Ptmp Hist.

Drive Bearing 284 95 Comp.

04/21/94 2245 Switchgear Medium <30 0%

Plant Elect. Fire 13.8KV Xformr 13.8KV None None-Fait.

Room min.

Power AC Pwr Fait.

Alarm Xformr Intern. Xformr Refuel.

Hist.

Distr.

285 80 camp.

05/05/94 --

Diesel Cen.

Light

<30 100%

EDG Overht Visual DG Exhst DG EDG(1) None Fait.

Building (Smoke

.iin.

Power Matt Turbo-Line Engine Hist.

Residue)

Charger Insul 286 69 Comp.

05/16/94 0525 Reactor Light

<10 0%

RPS Elect. Visual IRM Elect. IRM RPS(1) None*

Fait.

Building (Smoke min.

Power Fall.

Aux Intern. Aux 0% Pwr Hist.

Smell)

Contacr Contacr 787 40 comp.

06/16/94 --

Dieset Gen.

Light

<5 100%

EDG Overht Viscal Engine Fuel DG Eng EDGt1) None Fait.

Building min.

Power Matt Turbo-Oil Turbo-Hist.

Charger Chargr 288 52 Comp.

07/03/94 --

Turbine Light

<1 Nr.

607 Cond.

Overht Visual Pts:p Excess Cond.

Cond(1) None Fait.

Building Matt Mech Frictn Booster Hist.

Seat Pump 289 65 Comp.

07/13/94 2141 Diesel Gen.

Light

<20 100%

EDG Overht Fire DG Air Compr DG Air None None Fait.

Building min.

Power Matt Alarm Conpr Drive Conpr Hist.

Distr.

Belt 290 70 Coop.

07/17/94 0602 Auxiliary Light

<10 100%

Contt Elect. Visual CRD Power CRD CRD(1) None Fail.

Building min.

Power Rod Fail.

Power Supply Power Hist.

Drive Supply Intern. Supply 291 68 Conp.

09/11/94 2200 Turbine Light

<20 85%

Plant Elect. Visual Load Xformr Load None None Fait.

Building (Smoke min.

Power AC Pwr Fait.

Center Insut/ Center Hist.

Residue)

Distr.

Power Winding Power Xformr Xformr J-43

m iAsLE II SHOKE EVENTS DATA - 01/01/86 - 12/31/94 ITEM DKTI LER/

EVENT REP (RT LOCATIGI EXTENT EST.

OPER.

PL1 CAUSE DETECT INIT.

INIT.

CINF.

TRAIN POKR E

PLT ID OTIER D_A_TE M

PLT AREA SEME OLN II(BE HS UEEE IEAIIS CENF.

CIB5.

EFFECT EFFECT EFFECT 292 112 Conp.

09/28/94 1905 Turbine Light

<20 100%

FW Overht Temp FW Ptsp Bearing FW FW(1)

Power Fail.

Building min.

Power Matt Alarm Bearing Lube Ptsip Reduced Hist.

Dit 293 53 Conp.

09/26/94 --

Reactor Light

<1 Hr.

Power Canbst Elect. Visual H2/02 Ptsp H2/02 None None l

Fait.

Building Oper.

Cas Fait.

Sanpt Motor Anatzr Hist.

Ptap Intern.

294 E3 Conp.

12/20/94 --

Auxiliary Medita <30 47%

RPS Elect. Visual RPS Diode RPS RPS(1) None Fait.

Building min.

Power Fall.

IRM Bridge IRM Hist.

Xformr Rectifr Xformr NOTES:

1.

The Auxiliary Building is For PWR only.

For this tab'e, PWR Reactor Building, Control Building, Cable Spreading Room, and Switchgear Room are included with Auxilary Building.

2.

The Reactor Building is for BWR use only. For this table, BWR Control Building, Waste Treatment Building, Cable Spreading Room, and Switchgear Room are included with the Reactor Building.

3.

Smoke events listed do not include Fire Events for this period (see Appendix A - Table 11).

J-44

'?

-~

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