ML20214N488
| ML20214N488 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1986 |
| From: | Harper M, Higgins K, Wolf T NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | |
| Shared Package | |
| ML20214N466 | List: |
| References | |
| TASK-AE, TASK-P603 AEOD-P603, NUDOCS 8609160319 | |
| Download: ML20214N488 (106) | |
Text
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, 't g AE0D/P603 Engineered Safety Feature Actuations At Comercial United States Nuclear Power Reactors July 1 Through December 31, 1984 August 1986 Program Technology Branch Office for Analysis and Evaluation of Operational Data e
Principal Author:
Marcel R. Harper Contributing Assistants:
Thomas R. Wolf Kathy Higgins NOTE: This report documents the results of a study by the Office for Analysis and Evaluation of Operational Data. The findings and recomendations do not necessarily represent the position or requirements of either the responsible program office or the Nuclear Regulatory Comission.
8609160319 e60820 NEXD PDR ORG
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CONTENTS Page LIST OF FIGURES ................................................... iii LIST OF TABLES .................................................... iv EXECUTIVE
SUMMARY
................................................. 1
1.0 INTRODUCTION
................................................. 5 2.0 GENERAL OBSERVATIONS ......................................... 6 3.0 ACTUATION TYPES ..............................................
13 3.1 Valid Actuations ............'............................ 13 3.1.1 General Characteristics ......................... 13 3.1.2 Valid Actuations - Measured Parameters and Equipment Actuated ............................. 14 3.1.r.1 Valid Design Basis Actuations .................. 14 3.1.2.2 Valid Non-Design Basis Actuaticns .............. 21 3.2 False Actuations ........................................ 26 3.2.1 General Characteristics ......................... 26 3.2.2 False Actuations From Radiation Monitors ........ 26 3.2.3 False Actuations From Loss of Power Supply ...... 37 3.2.4 Miscellaneous False Actuations .................. 38 3.3 Conclusions and Recommendations ......................... 38 3.3.1 Conclusions ...................................... 38 3.3.2 Recommendations .................................. 40 4.0 EMERGENCY CORE COOLING SYSTEMS - SAFETY INJECTIONS............ 41 4.1 Discussion .............................................. 41 4.2 Conclusions ............................................. 42 5.0 FAILURES TO ACTUATE AND ASSOCIATED FAILURES .................. 43 5.1 ESF Fa ilu res to Ac tua te Properly . . . . . . . . . . . . . . . . . . . . . . . . 43 5.1.1 Quad Cities 1 - Loss of Standby Gas Treatment System (LER 84-012) ............................ 43 i
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CONTENTS (Cont'd)
Page 5.1.2 Susquehanna 2 - Loss of Off-site and On-site AC Electrical Power (LER 84-013) ............... 44 5.1.3 Trojan-Reactor Trip, Safety Injection, and Subsequent ESF Failures (LER 84-016) ........... 45 5.2 Associated Failures ...................................., 45 5.3 Cor.clusions ............................................. 46 6.0
SUMMARY
OF FINDINGS, CONCLUSIONS AND RECOMMENDATIONS ......... 48 APPENDIX .......................................................... 51 11
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- c ls Ab
.' / l LIST OF FIGURES fage
- 1. Unit Distribution of 1984 Engineered Safety Features .......... 7 Actuations
- 2. ES F Ac tuation Di stri bu ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 (July 1 - December 31)
- 3. Unit Distribution of Valid ESF Actuations . . . . . . . . . . . . . . . . . . . . . 15
- a. Design Basis
- b. Non-Design Basis
- 4. Measured Parameters and Associated System Functions for ........ 20 Valid ESF Actuations (July 1 - December 31,1984)
- 5. ESF Toxic Gas Monitor ESF Actuations (Valid Non-Design Basis) a t S a n O no f re 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22
- 6. Radiation Monitor ESF Actuations (Valid Non-Design Basis) ..... 23
- 8. Unit Distribution of False ESF Actuations (1984) . . . . . .. ..... . . 27
- 9. False ESF Actuations Characteristics (July-December 31,1984).. 31
- 10. Causes vs. Activity in False ESF Actuations (2nd Half 1984) ...
34
- 11. Fal se Radiation Monitor ESF Actuations . . . . . . . . . . . . . . . . . . . . . . . . 36 e
111
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LIST OF TABLES fage A.1 Number of ESF Actuations Reported By Commercial U.S. Nuclear Power Plants ,2nd Half of 1984 .............................. 51 A.2 ESF Actuations Reported by Commercial U.S. Nuclear Power Plants
- July 1,1984 through December 31, 1984 ...................... 52 A.3 Valid (Design Basis) ESF Actuations ........................... 62 A.4 Valid (Non-Design Ba sis ) ESF Actuations . . . . . . . . . . . . . . . . . . . . . . . 64 A.5 ESF Actuations - Hea ting and Ventilation Systems . . . . . . . . . . . . . . 87 A.6 Fa l se ES F Ac tua ti on s . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . 88 A.7 ESF Actuations - Safety Injection Events - 2nd Half of 1984 ... 94 A.8 ESF Actuations - Associated Failures - 2nd Half 1984 .......... 99 i
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EXECUTIVE
SUMMARY
In order to gain an understanding of the challenges to safety systems, the Conunission reqtlired that, effective January 1,1984, actuation of any Engi-neered Safety Festure (ESF) be reported to the Nuclear Regulatory Conunission as a Licensee Event Report (LER). Prior to this date, such actuations were not directly reportable. As a consequence of this revised reporting requirement, and as part of the AE00 trends and patterns analysis program, a study was initiated of ESF actuations which occurred between January 1 and June 30, 1984(AEOD/P503, August 1985). The investigation was limited to those ESF actuations which occurred in systems other than the reactor protection system (RpS), which are the subject of a companion AE00 study. The present study covers the period of July I to December 31, 1984. Subsequent studies will be conducted on a yearly basis. The objectives of this study are to: (1) gain an understanding of the frequency and causes of ESF actuations on both an individual unit and an industry-wide basis; (2) determine the significance and implications of the current rate of actuations; (3) determine if specific action by the NRC or the industry appears warranted; and (4) investigate the usefulness of ESF actuation data as a valid indicator of licensee performance.
It was found that 601 actuations occurred during the last six months of 1984 Of the 93 units
- eligible to issue LERs (that is, they had an operating li-cense from NRC), 72 units reported at least one ESF actuation. On a percentage basis, 23 percent of the eligible units did not report an ESF actuation during the period, 45 percent reported between one and three actuations, 9 percent ,
reported between four and six actuations and 23 percent reported more than six actuations. Sixteen units (17 percent) reported more than ten ESF actuations.
The maximum number of actuations at any one unit was 70. Only about 7 per-cent of all reported ESF actuations involved an Emergency Core Cooling System (ECCS), and none of these occurrences were necessary to control an actual loss- '
of-coolant accident (LOCA). Over 70 percent of the actuations that occurred in ESF Systems were associated with either an isolation function or a ventilation function.
- The initial operating license for Shoreham was December 7; 1984 and for Palo Verde 1 December 31, 1984. These two plants were not included in the study I because they had very little time to issue LERs in the second half of 1984.
-- B G $
l r The 601 ESF actuations were found to be the result of several causes. In 257 cases (43 percent), a measured parameter reached the intended setpoint for ESF actuation. However, the rate for valid and necessary ESF actuations because of design basis events is very low. Only 22 such actuations, or less than four percent of all reported actuations, occurred in the six month study period; none of these were necessary to control a significant safety event. Thus, there is httle indication that any unit is experiencing serious unresolved safety problems which have required mitigating ESF actuations. The remaining 235 cases where a setpoint was reached were considered to be valid, but did not represent a needed response to a design basis event. These actuations resulted from non-design basis conditions such as radioactive trash being moved near a radiation monitor. These valid non-design basis events were primarily the result of reactor vessel water level, loss of power, flow, or toxic gas signals, and resulted primarily in isolation or ventilation actuations such as reactor water cleanup (RWCU) or containment isolations, or control room ventilation actuations.
The remaining 57 percent (344 out of 601) of the ESF actuations were deemed
'to be invalid and unnecessary false actuations. False actuations were caused mostly by spurious actuations (almost 90 percent of them during operation),
equipment fail'u res (over 80 percent during operation), and personnel errors
]
(about 75 percent during test or maintenance). Therefore these actuations could be decreased most efffectively by: (1) improvements in equipment; (2) reductions in personnel errors during maintenance and testing; and (3) electromagnetic interference (EMI) protection and other measures to reduce spurious actuations due to electrical noise spikes'. The functions most affect-ed by false ESF actuations were isolation (46 percent) and ventilation (31 per-cent). Equipment failures causing false ESF actuations were associated with power (29 percent), temperature monitoring (19 percent), toxic gas monitoring (18 percent), radiation monitoring (60 percent), fire detection (10 percent),
and flow measurements (9 percent).
A few specific units are experiencing frequent or unnecessary challenges.
In general, corrective actions and improvement programs have been implemented, but the offectiveness has varied. The specific units and concerns where prob-lems appear to persist are: San Onofre 2 and 3 (toxic gas and radiation
, monitor actuations), Byron 1 (radiation actuations), Callaway 1 (radiation actuations), Sequoyah 1 and 2 (radiation actuations), WPPSS 2 (radiation 2 .
e 4
, actuations and RWCU isolations) and LaSalle 1 and 2 (RWCU isolations).
Depending on the actuation trends, further actions may be warranted, such as thorough investigation into causes and corrective actions taken.
In 44 of the ESF actuations at 32 units, an emergency core cooling system (ECCS)wasactuated. Fluid was actually injected into the reactor coolant sys-tem in 20 of the 44 events. Nineteen units experienced these safety injection events, with no unit experiencing more than two injections. Of the 20 actual injection events, none were needed to control an actual LOCA, and only one was considered a valid design basis actuation. Ten of the events resulted from setpoints being reached, about half of these as a result of lor! water level fol-lowing reactor scrams. The remaining nine safety injection events were false actuations, primarily the result of personnel errors during maintenance or testing. The number and severity of safety injection events occurring during the period of this study do no appear to be sufficient to prompt immediate con-cern. Thus, the safety injections that occurred during the period of this study do not appear to warrant further action. AE0D will continue to monitor these actuations during subsequent studies.
- In only three of the 601 ESF actuations did an ESF system fail to actuate prop-t erly. In 45 additional cases the ESF actuations performed properly, but one or more failures were associated with the actuation sequence. There was no identifiable trend or pattern for these failures, and redundant systems were available to perform required safety functions.
Finally, the wide variety of ESF systems and the differences in the types of ESF actuations (including variations in immediate safety significance) make comparisons among units very difficult. Limiting the actuations included in the statistics to more significant events such as safety injections (which are more or less comparable across plants) does not seem practical because such events are rare and little discrimination in performance would result either among plants or over time for a given plant.
The distribution of ESF actuation rates Smeng plants (i.e., the vast majority of plants have fairly low rates, and only 25 percent or so have relatively high rates) and the variety of ESF actuations suggest a two-step strategy for using 3
. . . . . . ~ . . .
.' P ESF actuations as a performance indicator: first, to use a value of 10 ESF actuatinns in a 6 month period as an alert level (plants with a value below this frequency are deemed acceptable with no further analysis made); and secondly, to perform a detailed examination of the circumstances for the plants exceeding the threshold, with unacceptable performance being frequent actuations as a result of ineffective corrective actions. Sustained operation (e.g., two consecutive 6 month periods) with a high rate of ESF actuations may be indicative of a willingness to accept ESFs that are not performing as intended.
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1.0 INTRODUCTION
All licensed commercial nuclear power plants in the United States contein systems which are designed to control and mitigate occurrences that might chal-lenge the integrity of the reactor or adversely affect plant personnel or the general populace. Generally known as engineered safety features (ESFs), these systems include those designed to control reactor core reactivity, isolate and cool containment, supply emergency cooling to the reactor fuel, remove residual decay heat, provide emergency power, assure habitability of the control room, and control radioactivity releases to the environment.
Prior to 1984, the nuclear power plant licensees were not required to routinely report ESF actuations. However, knowledge of such actuations was recognized as one of the essential elements needed to understand the operational performance of each reactor and to measure the type, frequency, and safety significance of events requiring mitigation. Consequently, the Commission, as part of the re-vised reporting requirements which became effective in January of 1984, now requires the licensees to report [per 10 CFR 50.73(a)(2)(iv)]:
Any event or condition that resulted in manual or automatic actuation of any E,ngineered Safety Feature (ESF), including the Reactor Protection System (RPS). However, actuation of any ESF, including the RPS, that resulted from and was part of the preplanned sequence during the testir.g or reactor operation need not be reported.
In late 1984, AE00 began a comprehensive study of the ESF actuations reported under the new 10 CFR 50.73 requirements. This investigation focused on actua-tions of ESF systems other than the RPS which occurred during the first six months of 1984 at all licensed commercial U.S. nuclear plants.* The results of that study were documented in AE0D/P503 August 1985. The present study covers the period July 1 to December 31, 1984. Future ESF actuation studies will be conducted on a yearly basis.
- Separate AE0D studies of RPS actuations are being conducted and documented.
For example, see AE0D Report P504 " Trends and Patterns Report of Unplanned Reactor Trips at U.S. Light Water Reactors in 1984," issued in August 1985.
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2.0 GENERAL OBSERVATIONS During the period July-December,1984, there were 601 engineered safety feature (ESF) actuations (other than reactor protection system actuations) reported in licensee event reports (LERs).*
The 601 ESF actuations occurred at 72 of the 93 reactors that were eligible for reporting per 10 CFR 50.73. In more detail, of the 93 units eligible, 21 units (23 percent) experienced no actuations during the six month study period, 42 units (45 percent) had between one and three actuations, 8 units (9 percent) had from four to six actuations, and 6 units (6 percent) had between seven and nine actuations. Sixteen units (17 percent) experienced ten or more ESF actuations, with the maximum number of actuations at any one unit being 70.
Distribution by unit of the 601 ESF actuations is shown in Figure 1, along with the distribution of the 501 events which occurred in the first half of 1984.
Figure 2 shows the distribution of the unit ESF actuation count for the second half of 1984.
Table A.1 of the Appendix is a listing of the units eli,gible to report ESF actuations and the number of such actuations reported by each unit during the second six months of 1984. Table A.2 of the Appendix gives details of these actuations.
In addition to the number of actuations certain other characteristics were compiled. These included: (1) actuation types, measured parameters, equipment actuated, and basic causes (Section 3); (2) actuations leading to fluid in-jection into the reactor vessel (Section 4); and (3) failure to actuate properly and problems discovered as a result of the actuations (Section 5).
This study included actuations of the auxiliary feedwater (AFW) system at Westinghouse units only when the licensee specifically stated that the AFW was started in an ESF operational mode.
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. Figure 1
+ >
UNIT DISTRIBUTION OF 1984 ENGINEERED SAFETY FEATURES ACTUATIONS SAN ONOFRE 2 ---+- z+-*:
WPPSS 2 -- >z - ummuummanuma r
,,Fg'/'
- x,'; 1 s t LA SALLE 2 -
Immmeuumum m Half SEQUOYAH 1 +z- - -
BRUNSWICK 1 -El 2nd Half LA SALLE 1 -m CALLAWAY -m BYRON 1 ---
DUANE ARNOLD + w - une o MONTICELLO -- +z e
~
E D. C. COOK 2 -w-s S FORT CALHOUN -NEmius y GRAND GULF 1 -
aus
~2 LI MERICK 1 - '
3 -mme SEQUOYAH 2 DIABLO CANYON 1 -EZW ; ; j , , ,
SAN ONOFRE 3 65 SUSQUEHANNA 1 -EM ' '
! i E. I. HATCH 2 m E. I. HATCH 1 -Buus SUSQUEHANNA 2 -luus BRUNSWICK 2 -95 KEWAUNEE -05 PALISADES -
DI O 20 40 60 80 100 120 140 160 180 200 Counts
Figure 1 UNIT DISTRIBUTION OF 1984 ENGINEERED SAFETY FEATURES ACTUATIONS l .
(Continued)
YANKEE ROWE -BW ...'
BROWNS FERRY 3 -BE gg CATAWBA -EE 1 st Half MCGUIRE 1 -01 ARKANSAS 2 -El 2nd Half LACROSS$ -m PILGRI M 1 -III ST. LUCIE 2 -m SUMMER 1 -al m a> BROWNS FERRY 1 -DI -
E MAINE YANKEE -0 z TURKEY POINT 4 -BI y D.C. COOK 1 -BI ,
'E QUAD CITIES 1 -R D QUAD CITIES 2 -E TROJAN
-El ! I CRYSTAL RIVER 3 -Ri ,
OYSTER CREEK -E PEACH BOTTOM 2 -0
-4
POINT BEACH 2 SALEM 1 -11 VERMONT YANKEE -il BEAVER VALLEY -H FITZ PATRICK -H o o o ho o 1do 1bo 1Io 1bo ido 200 Counts
( n
Figure 1 ' -
UNIT DISTRIBUTION OF 1984 ENGINEERED SAFETY FEATURES ACTUATIONS (Co ntin u ed)
INDIAN POINT 2 -l INDIAN POINT 3 -I
[rfj/j j 1 st Half MCGUIRE 2 -1 MILLSTONE 2 -I 2nd Half NINE MILE POINT -I PEACH BOTTOM 3 -1 PRAIRIE ISLAN D 1 -1 SAN ONOFRE 1 -
I e SURRY 1 -I
9 39 .n st 19 s 0 10 20 30 40 50 ,
70 80 ESF ACTUATIONS / 6 MONTHS 1 .
l The 601 ESF actuations reported in the second half of 1984 represent an increase of 100, or 20 percent, compared to the first half of 1984. The addition of Byron (37 actuations), Limerick (28 actuations), and Catawba (8 actuations) to the units reporting, and the fact that Callaway (45 actuations) only began reporting in June 1984 explains the difference in the total number of ESF actuations in the two periods. The unit distribution of ESF actuations and the average ESF actuation rates appear to be fairly similar for the two six month periods.
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! 3.0 ACTUATION TYPES One fundamental characteristic of tne ESF actuations studied was whether or not a measured parameter actually reached its intended setpoint. For discussion purposes, those cases in which a setpoint was reached were defined to be " val-id" actuations. Actuations which resulted from something other than a measured parameter reaching its intended setpoint were considered to be invalid and un-necessary, and thus are referred to as " false" actuations.
3.1 yalid Actuations .
3.1.1 General Characteristics In 257 of the 601 cases studied (43 percent), the measured parameter reached the in-tended setpoint for ESF actuation; however, in only 22 of these 257 cases were the actuations considered needed in terms of providing a required ESF system response for protection from an actual design basis event. These 22 " design basis" ESF actuations represented less than 4 percent of the 601 cases. They occurred at 15 different units. They included nine cases involving loss of offsite power, four high radiation events, five cases involving water level (BWR Suppression Pool Level), and four other cases. None of these 22 design basis ESF actuations were necessary to control significant safety events such as a LOCA or a steam-line break. In the remaining 235 cases where a setpoint I
was reached, the ESF actuation resulted from conservative alarm setpoints, equipment failures, or personnel errors. These ESF actuations were considered
- to be valid (i.e., the measured parameter reached the intended actuation set-point) but did not represent a response to a design basis event. Rather, they were actuations resulting from non-design basis conditions, such as radioactive
, trash being moved near a radiation monitor. These valid but non-design basis actuations were primarily associated with water level (reactor water level in BWRs and steam generator level in PWRs), loss of power, flow (about 90 percent were reactor water cleanup flow), or toxic gas monitors. Most of them were associated with isolation of the reactor water cleanuo system or the containment, or the actuation of the control room ventilation. A t1tal of 51 units experienced i
valid non-design basis actuations. '
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The unit distribution of the valid design and non-design basis is shown in Figures 3(a) and (b) for both halves of 1984. Two units (Sequoyah 1 and LaSalle 1) comprise almost 30 percent of the valid design basis actuations, and just four units (San Onofre 2, LaSalle 2, Callaway 1, and Sequoyah 1) comprise almost 50 percent of the valid non-design basis ESF actuations for both halves of 1984. Detailed listings of these 257 ESF actuations are given in Tables A.3 and A.4 of the Appendix.
3.1.2 Valid Actuations - Measured Parameters and Equipment Actuated The 2E7 valid ESF actuations resulted from several different parameters reaching their setpoints and involved a wide range of ESF systems. Figure 4 shows the types of parameters measured and the general ESF system functions which were involved. As can be seen in this figure, some parameters were associated with nore than one system function. That is, certain sensed plant conditions re-quire equipment to perform multiple functions in response. It was determined that the use of gereral functional characteristics was necessary for ease in system comparison since there appears to be no comon definition or title for ESF systems at the various units. For example,15 different systems were associated with a heating and ventilation function, as is shown in Table A.5 in the Appendix.
3.1.2.1 Valid Design Basis Actuations As discussed in the AE0D analysis of ESF actuations in the first half of 1984, Sequoyah 1 accounted for six valid design basis actuations, primarily due to radioactive releases into the auxiliary building during waste transfer opera-tions. Sequoyah I had no valid design basis ESF actuations in the second half of 1984, and Sequoyah 2 had only one. Thus, corrective actions appear to have been effective in preventing further similar occurrences.
The 22 valid design basis actuations during July-December 1984 appear to be i isolated events, with the exception of the five high pressure core spray suc-tion transfers at LaSalle 1 and 2. In this transfer, suction from the Suppres-sion Pool is opened, while the normal suction valve from the condensate tank is closed. The cause for these transfers was high suppression pool level due to valve cycling for operating surveillance and minor valve leakage. Transfer l 14 i
Figure 3(a) .
UNIT DISTRIBUTION OF VALID ESF ACTUATIONS ~':
(Design Basis) l LEGEN D !
Sequoyah 1 -
NEMW2' *m4MWA' 4 4MMF#2*wfMMZ1 M
LaSalle 1 -
bh First Half of 1984 I '
McGuire 1 -Nr4MEM&t '
Se nd Half of 1984 l Cod 2 .
H a dda rn Neck -
H a tch 2 -m ,
j LaSalie 2 - m i i
i o Monticello -WM5WWewi ,
G h Callo way 1 -m !
Z Catawba -- -
[
-j I
Duane Arnold -
U Grand Gulf 1 -waw1 ,.
Indian Point 3 - m ; ,
1 La Crosse - M I '
Sale rn 2 -
p San O nofre 1 -N#M1 :
San Onofre 3 -M .
i Sequoyah 2 -M Yankee Rowe -
o i b 5 I 5 6 7 Nurnber of Valid ESF Actuations :
(Desig n Basis) l
Figure 3(b)
UNIT DISTRIBUTION OF VALID ESF ACTUATIONS '!
(Non Design Basis)
. j SAN ONOFRE 2 -- w"e- w"""z w"e"e -
LA SALLE 2 -"" -
V fgJ 1 st Half CALLAWAY -menemuumum u.i SEQUOYAH 1 --uni BRUNSWICK 1 E2 2nd Half LA SALLE 1 -E2231 FORT CALHOUN -r"-NM WPPSS 2 -EZisumumme D. C. COOK 2 *=mi .
GRAND GULF 1 -Enams g <u CATAWBA -um E DIABLO CANYON 1 -mul S SUSQUEHANNA 1 -EE
, PILGRIM 1 -But ,
'E BRUNSWICK 2 -is 3 DUANE ARNOLD -m i
E. 1. HATC H 1 -u ; ;
- ,; i ,
FITZPATRICK -El ,
MONTICELLO -u i
, , , , l i
POINT BEACH 2 -u i PRAIRIE ISLAND 1 -u ST. LUCIE 2 -u SUSQUEHANNA 2 -u ,
TURKEY POINT 4 -is !
YANKEE ROWE -u ARKANSAS 2 -E O 10 20 30 40 SO 60 70 BO 90 100 Counts a
Figure 3(b) (cont'd) -
UNIT DISTRIBUTION OF VALID ESF ACTUATIONS 'l (Non Dssign Basis)
'(Co ntin u ed)
D.C. COOK 1 -H , , ,, ,
W DRESDEN 3 -s
-m MM 1 st Half !
E. I. HATCH 2 !
LACROSSE -E 2nd Half LIMERICK 1 -m l PEACH BOTTOM 3 -u SEQUOYAH 2 -H SUMMER 1 -H l ZION 1 -B {
~
ARKANSAS 1 -l O BEAVER VALLEY -i '
E BROWNS FERRY 2 4 S BROWNS FERRY 3 -t ,
, BYRON 1 -l c CALVERT CLIFFS 1 -t D CALVERT CLIFFS 2 -t 7.
I ;I '
COOPER -t DAVIS BESSE 1 -t ,
' II INDIAN POINT 2 -I MCGUIRE 2 -t MILLSTONE 2 -l NIN E MILE POINT -i ,
NORTH ANNA 1 -i OYSTER CREEK -I ,
PALISADES -l QUAD CITIES 1 -i o io do do 40 do s'o io do so 1oo Counts i t
Figure 3(b) (cont'd} l UNIT DISTRIBUTION OF VALID ESF ACTUATIONS
-( N o n Design Basis)
(Co ntin u ed)
OUAD CITIES 2 -i ,,
I- EGEN D TROJAN -i BIG ROCK POINT --
!bbb 1 st Half BROWNS FERRY 1 - -
CRYSTAL RIVER 3 -- '
2nd Half DRESDEN 2 --
FARLEY 1 --
FARLEY 2 --
FT. ST. VRAIN -- '
GI NNA --
E o HADDAM NECK ---
E HUMBOLDT BAY --
S INDIAN POINT 3 --
., KEWAUNEE --
'E MAINE YANKEE --
'D MCGUIRE 1 MILLSTO NE 1 -- '
NORTH ANNA 2 --
OCONEE 1 --- I '
I i OCONEE 2 --
OCONEE 3 --
PALO VERDE 1 --
l PEACH BOTFO M 2 --
i POINT BEACH 1 --
PRAIRIE ISLAND 2 --
RANCHO SECO --
l o io do do 40 do do 70 do do 100 Counts ,
. Figure. ~;(b) (cont'ri) , ,
i .
UNIT DISTRIBUTIO'N OF VALID ESF ACTUATIONS 1' (Non Design Basis) ' '
'(Co ntin u ed) .
ROBINSON 2 --
LEGEND j SALE M 1 --
rgsp; <
NA SALEM 2 -- 1 st Half SAN ONOFRE 1 --
SAN ONOFRE 3 -- 2nd Half i SHOREHAM --
ST. LUCIE 1 --
l SU RRY 1 --
SU RRY 2 --
THREE MILE ISLAND 1 --
- THREE MILE ISLAND 2 --
E TURKEY POINT 3 -- !
S VERMONT YANKEE l
WATERFORD 3 --
l' i= ZION 2 --
] ..
' I i
l ll 1
l1 t i
'I tI l l ..
0 10 NO 30 dO 50 60 70 NO NO 100 '
Counts
-- _ _ _ _ _ _ . . . . . . ._ - _ _ _ _ _ . _ . _ _ . . . . . . _ .m ,
General System Function Actuated
- Measured Heating and Emergency Not Total Parameter Fluid Ventilation Isolation Power Defined (HVAC)
Radiation 0 1 18 0 0 19 Loss of Power 2 2 8 39 0 51 Temperature 0 1 19 0 0 20 Pressure 4 10 5 1 5 25 Level 27 4 22 1 0 53 Toxic Gas 0 36 0 0 0 36 Flow 0 0 43 0 0 43 Fire Detection 0 5 0 0 0 5 Other 15 2 23 1 3 44 Total Actuations 48 61 138 41 8 296
- Examples: Fluid = High Pressure Coolant Injection (HPCI)
HVAC = Standby Gas ~ Treatment System (SBGT)
Isolation = Primary Containment Isolation System (PCIS)
Emergency Power = Diesel Generator (DG)
Note: Some parameters were associated with more than one system function.
That is, certain sensed plant conditions require multiple functions in response (e.g., isolation and HVAC). Therefore, total functions exceed the total number of events.
Figure 4: Measured Parameters and Associated System Functions for Valid ESF Actuations (July 1 - December 31,1984) 20
on high suppression pool level is a designed function, so no corrective actions were taken other than lowering the Suppression Pool back to normal and restor-ing the normal HPCS' suction path.
3.1.2.2. Valid Non-Design Basis Actuations Six units account for almost 60 percent of the valid non-design basis actuations:
San Onofre 2 (17 percent), LaSalle 2 (15 percent), Callaway 1 (10 percent),
Brunswick 1 (6 percent), WPPSS 1 (5.5 percent) and LaSalle 1 (5 percent).
At San Onofre 2*, all but four of the 40 actuations involved the control room emergency air cleanup system (CREACUS) responding to an indicated high toxic gas level. In these actuations, the technical specification setpoints for the monitors are such that minor variations in the background readings resulted in the setpoint being reached. Various corrective actions have been undertaken to alleviate this problem. In September 1984, the time delay for the annonia and carbon dioxide analyzers was increased, which has been effective in reducing the number of actuations from an average of about 30 for each of the previous quarters to eight in the last quarter.
A proposed Technical Specification amendment has been submitted to request more appropriate satpoints to further reduce the number of actuations.
Figure 5 illustrates the monthly rate of actuations for 1984, and shows the gradual decrease in toxic gas monitor actuations. No other unit reported valid, non-design basis toxic gas actuations in 1984.
In the first half of 1984, three units had more than ten valid non-design basis ESF actuations resulting from radiation monitors reaching their set-points. Figure 6 shows the monthly distribution of these actuations.
Sequoyah 1, which had 13 actuations in the first six months, had only five in the second six months. Cook 2 had 11 actuations in the first half year and none in the second, and Fort Calhoun went from 11 actuations in the first half year to six in the second half of 1984. Minor corrective actions such as
- These actuations are reported under Unit 2, but affect both Units 2 and 3 because of the common control room.
21
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procedures, fixing leaks, and changing setpoints appear to have decreased the number of such actuations. In general, in the second half of 1984, no unit had more than six valid non-design basis radiation monitor ESF actuations.
Another type of valid non-design basis actuation that occurred frequently in the first six months of 1984 was isolation of the reactor water cleanup (RWCU) system. Four units (LaSalle I and 2, Grand Gulf 1, and WPPSS 2) had a combined '
total of 22 RWCU isolations in the first six months of 1984. The monthly distribution of these actuations is shown in Figure 7. In this case, the number of actuations increased in the second half of the year, especially in the fourth quarter. Grand Gulf decreased the number of actuations from five in the first half to two in the second half, but WPPSS 2 increased from four to 12, LaSalle 1 from six to 10, and LaSalle 2 from seven to 24 in the second half.
The RWCU isolations were the consequence of setpoints reached on instrumenta-tion designed to sense RWCU pressure boundary failures. Such detection is based on RWCU flow or environmental temperatures around the RWCU system. About 70 percent of the RWCU isolations in the last six months were based on flow perturbations from valve alignments, filter changes, and differences between start up and rated flow conditions. The rest of the RWCU isolations were due to temperature variations associated with conservative setpoints, or ventilation system problems.
To help prevent recurrence of these RWCU isolations, various modifications were being implemented, including re-evaluation of monitor setpoints and modifica-tion to procedures. Based on the limited data, these changes appear to have resolved the RWCU isolation problems at Grand Gulf. At WPPSS 2, conservative temperature monitor setpoints were reset, and minor modifications made to try to prevent flow isolations. No RWCU isolations occurred at WPPSS 2 in the the last quarter, so perhaps they have also resolved the RWCU isolation prob-lem. At LaSalle, RWCU isolation setpoints were still being investigated at the end of 1984.
There were 39 valid non-design basis emergency power actuations (diesal generator) during July-December, 1984. No unit had more than four such actuations, and no trend or pattern could be discerned.
24
t Figure 7, i
R\NC U ISO LATIO N ESF ACTUATIONS (Va lid Non! Dsdignl iI Basis) 3 i : LEGEND La Salle 2 2s - M WPPSS 2 asz La S olic 1 20-- Gra n d Gulf 1 Other a .
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Jan Feb Mar Apr Mcy Jun Jul Aug Sep Oct Nov Dec Month (1984) -
3.2 False Actuations 3.2.1 General Characteristics False actuatio.ns are actuations caused by something other than a measured pa-rameter reaching its intended setpoint. Figure 8 shows the unit distribution .
of these false actuations, and Figures 9 a, b, and c illustrate some of their basic characteristics. A total of 344 false actuations, or 57 percent of the 601 ESF actuations, occurred at 54 units. These false ESF actuations princi-pally affected systems whose functions were associated with either isolation (157 events) or ventilation (106 events). False ESF actuations were caused mostly by spurious equipment failures, or prqblems related to personnel. The main parameters involved with these false actuations were radiation and loss of power. Table A.6 of the Appendix gives a comprehensive listing of the individual occurrences.
Over 50 percent of the false ESF actuations occurred at just six units (WPPSS 2, Byron 1, San Onofre 2, Limerick 1, Brunswick 1, and Callaway 1).
Figure 10 presents the causes and activities involved in false ESF actuations.
Leading causes for these actuations are spurious actuations, equipment fail-ures, personnel errors, and combinations of causes. Spurious actuations and equipment failures occurred mostly during operation, but personnel errors .
occurred mostly during test and maintenance.
3.2.2 False Actuations From Radiation Monitors Of the 344 false ESF actuations,118 (34 percent) were associated with radiation monitors at 20 units. Over 70 percent of these radiation actuations (86 of 118) occurred at only five units. These units and the number of false actuations were:
Unit False Radiation Actuations Byron 1 33 San Onofre 2 25 WPPSS 2 11 Callaway 1 10 .
, Sequoyah 1 7
, 26
~
Figure 8 .
~
UNIT DISTRIBUTION OF FALSE ESF 'ACTUATIONS (1984) .
WASHINGTON NUCLEAR 2 ***==w"*'d LEGEND SAN ONOFRE 2 *=""*""-
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FORT CALHOUN *+we ! i DIABLO CANYON 1 **=um SUSQUEHANNA 1 -mse E. l. HATCH 1 -m E . 1. HATCH 2 -Bumuuu KEWAUNEE -NTaent SUSQU EHANNA 2 -6m PALISADES -NEW BROWNS FERRY 3 -QEul O 10 20 30 40 50 60 70 Cou n ts I
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Figurd 8 UNIT DISTRIBUTION OF FALSE ESF ACTUATIONS (1984)
(Co ntin ued)
BRUNSWICK 2 -EE BROWNS FERRY 1 -Gu MAINE YANKEE 6
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Figure 8 i
UNIT DISTRIBUTION OF FALSE ESF ACTUATIONS (1984)
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UNIT DISTRIBUTION OF FALSE ESF ACTUATION 5 (1984)
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j Cause*
Number ~
of Events Parameter E0 PE SP PR OT C0 UN 118 Radiation 10 11 59 5 5 24 4 63 Loss of Power 21 17 5 7 1 9 3 28 Temperature 14 2 6 3 0 1 2 12 Pressure 3 2 0 2 0 4 1 13 Level 1 5 0 1 1 4 1 31 Toxic Gas 13 5 5 0 0 2 6 23 Flow 4 3 9 1 1 4 1 15 Fire Detection 0 0 10 0 1 0 4 3 Cond. Vac. 2 0 0 1 0 0 0 1 Reactor Trip 0 0 0 0 0 0 1 14 Manual 1 7 0 3 1 2 0 23 Other 3 3 4 1 3 4 5 344 Totals -72 55 98 24 13 54 28
- Cause - EQ = Equipment PE = Personnel SP = Spurious PR = Procedure OT = Other C0 = Combination UN = Unknown Figure 9a: False ESF Actuation Characteristics (July 1 - December 31,1984) 31
Function **
Number of 1 Events Parameter FL HV IS P0 OT C0 118 Radiation 0 53 43 0 15 7 63 Loss of Power 1 8 33 6 1 14 28 Temperature 0 0 28 0 0 0 12 Pressure 1 1 5 0 4 1 13 Level 2 0 4 0 0 7 31 Toxic Gas 0 24 7 0 0 0 23 Flow 0 0 21 0 1 1 15 Fire Detection 0 15 0 0 0 0 3 Cond. Vac. 0 0 3 0 0 0 1 Reactor Trip 0 0 0 1 0 0 14 Manual 4 2 4 2 1 1 23 Other 0 3 9 2 6 3 344 Totals 8 106 157 11 28 34
C0 = Combination Figure 9b: False ESF Actuation Characteristics (July 1 - December 31,1984)
! i l
l
i
~
Activity *** -
Number of Events Parameter MA TE OP CN 118 Radiation 8 6 92 2 63 Loss of Power 12 20 27 4 28 Temperature 1 8 19 0 12 Pressure 2 7 2 1 13 Level 4 9 0 0 31 Toxic Gas 1 'O 30 0 23 Flow 1 3 19 0 15 Fire Detection 0 0 13 2 3 Cond. Vac. 0 1 2 0 1 Reactor Trip 0 0 1 0 14 Manual 2 8 2 2 Other 23 1 7 15 0 344 Totals 32 69 222 11
False ESF Actuations (2nd Half 1984)
L Cause Equipment Personnel Spurious Procedure Other Combination Unknown Total Activity 15 3 6 2 2 0 32 Maintenance 4 26 7 11 2 20 4 79 Test 9 10 87 6 8 30 22 222 Operation 59 1 2 2 11 Construction 0 4 1 1 N 72 55 98 24 13 54 28 344 FALSE ESF ACTUATIONS ASSOCIATED WITH RADIATION LEVELS s !
Cause Equipment Personnel Spurious Procedure Other Combination Unknown Total ;
- Activity ,
0 3 3 1 0 0 8 ,
Maintenance 1 5 0 7 0 16 l Test 0 3 1 l
53 4 16 4 92 Operation 10 4 1 Construction 0 1 0 0 0 1 0 2 10 11 59 5 5 24 4 118 q
Figure 10: Causes vs. Activity in False ESF Actuations
FALSE ESF ACTUATIONS WITH LOSSES OF POWER Cause Equipment Personnel Spurious Procedure Other Combination Unknown Total Activity Maintenance 2 7 2 1 0 0 0 12 Test 5 7 0 4 0 4 0 20 Operation 14 1 3 1 1 5 2 27 Construction 0 2 0 1 0 0 1 4 w
21 17 5 7 1 9 3 63 Figure 10: Causes vs. Activity in False ESF Actuations (cont'd) 4
I i 1 ,
F;igure 11 ,
l ?
FALSE RADIATION MONI-OR ESF ACTUATIONS '.
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l The monthly distribution of false radiation monitor ESF actuations for the entire year of 1984 is shown in Figure 11. In the first six months of 1984, Cook 2 had 13 false radiation monitor actuations. No such actuations occurred j from June-December 1984, so the false radiation actuation problem at Cook'2 may have been solved.
l Sequoyah 2 had 16 containment building ventilation isolations due to false
. high radiation signals in the first six and a half months of 1984, but no such isolations the rest of the year. Electromagnetic interference (EMI) protection measures that were taken by the licensee may therefore have solved the spurious radiation monitor isolations at Sequoyah 2.
False radiation actuations decreased at Sequoyah I from 29 in the first half of 1984 to 7 in the second half (and only one in the last quarter).
Actions being taken to eliminate false radiation actuations did not appear to be successful at San Onofre or WPPSS as of the end of 1984.
Byron did not begin operating until November, and Callaway in June, so no comparison between the first and second halves of 1984 can be made for these units. Most of the actuations at Callaway involve Control Room Ventilation Isolations. At Byron, the problems involve the Control Room HVAC System and the Boron Dilution Protection System. Since these events at Byron only oc-curred over a two month period, no trend can be detected.
3.2.3 False Actuations From Loss of Power Supply The second major false actuation type (after radiation) is loss of power, accounting for 63 events (18 percent of the false actuations). Only one unit experienced more than 10 percent of these loss of power actuations; Callaway 1, with seven actuations. All seven of these actuations were isolation of the control room ventilation, containment purge, or fuel building isolation systems, resulting from loss of power to radiation monitors. Loss of power to the radiation monitors resulted in downscale trips of the monitors, causing the ESF actuations (isolations). All other units experienced fewer than 10 percent of these actuations, and no clear pattirn was evident.
37
3.2.4 Miscellaneous False Actuations -
The rest of th? false ESF actuations (163, or 47 percent) were associated with ten other measured parameters. These actuations were widely distributed,
~
and occurred during operation about 64 percent of the time, during testing about 25 percent of the time, and during maintenance about 7 percent of the time. The primary causes were spurious (21 percent), equipment failures (25 percent) and personnel errors (16 percent). The primary ESF functions were isolation (50 percent) and ventilation (28 percent).
Limerick 1 experienced 26 false actuations, and Brunswick I had 24. Brunswick had 15 false actuations of the Control Building Emergency Air Filtration System, caused by spurious fire alarms. The other false actuations at Limerick and Brunswick were spread among several parameters and functions.
3.3 Conclusions and Recommendations 3.3.1 Conclusions o The rate for valid and necessary ESF actuations because of design basis events is very low. Only 22 such actuations, or less than four percent of all reported actuations, occurred in the six month study period; none of these were necessary to control a significant safety event. Thus, thare is little indication that any unit is experiencing serious unresolved safety problems which have required mitigating ESF actuations.
o The majority of the ESF actuations reported were false or unnecessary.
False actuations were caused mostly by spurious actuations (almost 90 percent of them during operation), equipment failures (over 80 percent during operation), and personnel errors (about 75 percent during test or maintenance). Therefore these actuations could be decreased most effectively
! by: (1) improvements in equipment; (2) reductions in personnel errors during maintenance and testing; and (3) electromagnetic interference (EMI) l protection and other measures to reduce spurious actuations due to electrical noise spikes. The functions most affected by false ESF actuations were isolation (46 percent) and ventilation (31 percent). Equipment failures 38
I causing false ESF actuations were associated with power (29 percent),
temperature monitoring (19 percent), toxic gas monitoring (18 percent),
radiation monitoring (60 percent), fire detection (10 percent), and flow measurements (9 percent).
o A few specific units are experiencing frequent or unnecessary challenges.
In general, corrective actions and improvement programs have been imple-mented, but the effectiveness has varied. The specific units and concerns where problems appear to persist are:
- 1. The frequency of occurrence of toxic gas isolations at San Onofre 2 was a concern in the first half of 1984 (65 actuations). There has been a gradual decrease in the number of actuations in the second half of 1984 (36 ac tuations) . The licensee has been attempting to further reduce the number of actuations.
- 2. There was a concern about ESF actuations based on radiation in the first half of 1984. Sequoyah 1, Cook 2, and Fort 4
Calhoun all had more than ten valid radiation monitor actuations, and Sequoyah 1, Sequoyah 2, San Onofre 2, San Onofre 3. WPPSS 2, and Cook 2 all had more than ten false radiation ESF actuations in the first half of 1984.
In the second half of 1984, Cook 2 had no radiation ESF actuations, Sequoyah 1 and 2 cut their radiation actuations by more than a factor of three, and Fort Calhoun cut their valid radiation ESF actuations by about 50 percent. Actions taken to eliminate radiation actuations at San Onofre 2 and 3 (26 false radiation actuations in the second half of 1984) and WPPSS 2 (11 false radiation actuations in the second half of 1984) do not appear to have been as successful. In addition, two new units appear to have problems with false radiation ESF actuations in the second half of 1984 - Byron 1 with 33 such actuations, and Callaway with 10 actuations.
39
- - - - -- +,y--
- - - - m , - - , ,
,- e _
- 3. Valid, non-design basis ESF actuations associated with RWCU isolations at LaSalle 1 and 2 were a concern in the first half of 1984 (13 actuations). There were even more such isolations at LaSalle 1 and 2 in the second half of 1984 (34 actuations),
and there was also an increase in RWCU isolations at WPPSS 2 from 4 to 12 actuations.
3.3.2 Recommendations
. o It is recommended that AE0D continue to trend ESF actuations. These future studies should continue to assess the general characteristics of the actuations while focusing on the actuation trends at San Onofre 2 and 3 (toxic gas and radiation monitor actuations), Byron 1 (radiation actuations), Callaway 1 (radiation actuations), Sequoyah 1 and 2 (radiation actuations), WPPSS 2 (radiation actuations and RWCU isola-tions) and LaSalle 1 and 2 (RWCU isolations) to better determine the effectiveness of the corrective actions taken by each licensee.
Depending on the actuation trends, further actions may be warranted, such as thorough investigation into causes and corrective actions taken.
40
4.0 EMERGENCY CORE COOLING SYSTEMS , SAFETY INJECTIONS 4.1 Discussion One of the most critical functions of the engineered safety features is to provide emergency injection of fluid into the reactor vessel. This safety injection assures reactor fuel cooling in events where reactor coolant is lost.
The ESF systems which perform this vital function are collectively known as emergency core coolfng systems (ECCS.s). Obviously, these emergency core cooling systems must work properly when called upon. However, when these systems actuate unnecessarily, the temperature difference between the ECCS safety injection fluid and the reactor coolant impose cyclical thermal stresses which challenge the design life of the affected components. Thus, .
unnecessary safety injections are of concern from the standpoint of continued system integrity.
Frequent ECCS actuations are also of concern since they may cause the reactor operators to become accustomed to such actuations and, as a result, tiiey may respond to the actuations in a routine manner without fully comprehending the Yeasons for such actuations. Consequently, this conditioning may result in the operators prematurely tenninating a necessary safety injection. Thus, frequent ECCS actuations are of concern from the aspect of improper reactor operator response.
Of the 601 actuations, 44 of the occurrences (7.3 percent) involved ECCS actua-tions. These actuations were spread among 32 units, w'ith the majority of these units experiencing one or two ECCS actuations. No units had more than three such actuations. Only 20 of the 44 ECCS actuations resulted in actual in-jections of fluid. These 20 injections occurred in 19 different units, with no unit experiencing more than two injections. Details of these 20 actual injection events are presented in Table A.7 of the Appendix. (In.the first half of 1984, 49 ESF actuations involved ECCS actuations, and 23 of these events resulted in actual injection of fluids.)
Of these 20 actual injection events, none were needed to control an actual LOCA 41
and only one was considered a valid design basis actuation (Salem 2 LER 84-018 on July 25, a low RCS pressure safety injection). Ten of the events were con-sidered valid non-design basis ESF actuations. Of these, half resulted in low water level following reactor scrams. The nine false safety injection actuations were primarily the result of personnel errors during maintenance or testing.
4.2 Conclusions o The number and severity of safety injection events occurring during the period of this study do not appear to be sufficient to prompt immediate concern. Thus, the safety, injections that occurred during the period of this study do not appear to warrant further action. AEOD will continue to monitor these actuations during subsequent studies.
e' 42
5.0 FAILURES TO ACTUATE AND ASSOCIATED FAILURES A positive aspect of ESF actuations, whether valid or false, is that these occurrences verify that the ESF systems perform as designed so that their intended safety functions are fulfilled. Conversely, failures of any ESF system to actuate properly requires immediate resolution. In addition, ESF actuations can reveal failures that occur simultaneously with or subsequently to the actuation, such as an undetected failure in an ESF support system.
These " associated" failures may significantly affect the ability of the ESF systems to. function properly or they may indicate potentially significant equipment or personnel deficiencies which need to be addressed.
5.1 ESF Failures To Actuate Properly Only in three of the 601 ESF actuations (less than 1 percent) did an ESF system (the entire system) fail to actuate properly. Discussion of each of these events follows.
5.1.1 Quad Cities 1 - Loss of Standby Gas Treatment System (LER 84-012)
On August 2,1984, Quad Cities Nuclear Power Station Unit 1 experienced an isolation of the Reactor Building Vent System. The "B" Standby Gas Treat-ment System (SBGTS) train auto started, but its heater tripped. When the "A" train was started, its heater also tripped, making both SBGTS trains inoperable. The cause of the trips was an incorrect electrical wiring drawing for temperature switches dating back to the time of initial plant construction.
The poor drawing led to jumpers being installed on the wrong terminals, result-ing in a short circuit.
l Standby Gas Treatment System failures were addressed in an AE00 Engineering Evaluation Report (AE00/E410, May 21, 1984)*. This report includes three
- Engineering Evaluation Report AE0D/E410 " Operational Experiences Involving Standby Gas Treatment Systems Which Illustrate Potential Common Causa Failure or Degradation Mechanisms", May 21, 1984.
43
events at Quad Cities during 1982-1983, including a high temperature trip of a heater. However, none of the events involved incorrect drawings. This report resulted in IE Information Notice No. 84-88, " Standby Gas Treatment System Problems," December 3, 1984.
The safety objective of the SBGTS in conjunction with other ESF systems is to limit the release of radioactive materials to the environment following a pos-tulated design basis accident. In the above event, the unit was in a refueling shutdown. Presumably, installing jumpers would not occur while at power.
5.1.2 Susquehanna 2 - Loss of Offsite and Onsite AC Electrical Power (LER84-013) -
On July 26, 1984, with Susquehanna Steam Electric Station Unit 2 operating at 30 percent power, a loss of Turbine Generator and Offsite Power Startup Test was initiated. As expected, this resulted in a. reactor scram and a primary con-tainment isolation. However, the four emergency diesel generators did not automatically start, resulting in a temporary loss of all AC power for Unit 2.
This loss of AC power resulted in most instrumentation in the control room failing downscale. The cause of the diesel generator failure to start was the operator opening the wrong switch on all four circuits.
In addition to the total loss of AC power, a relief valve opened to limit reac-tor vessel pressure. The resulting loss of inventory caused a decrease in ves-sel level. Reactor core isolation cooling (RCIC) was manually initiated to maintain vessel level. Other problems in the event included three of the four diesels tripping after manually starting, and the failure of the breaker on the fourth diesel to close.
Because of the major degradation of essential safety-related equipment in this event, it was reported to Congress as an abnormal occurrence (Report to Congress on Abnormal Occurrences, July-September 1984, NUREG-0090, Vol. 7, No. 3, April 1985). This event also resulted in IE Information Notice No. 84-76, " Loss of All AC Power," October 19, 1984.
44
5.1.3 Trojan - Reactor Trip, Safety Injection, and Subsequent ESF Failures (LER84-016)
~
On September 20, 1984, a reactor trip was followed by a safety injection from T
a spurious high steam flow signal coincident with a' valid low-low AVG signal.
One emergency diesel generator failed to automatically start. The steam-driven auxiliary feedwater pump automatically started, but tripped from low suction pressure, and the diesel-driven auxiliary feedwater pump failed to automatically start. The cause of the event was a combination of equipment (recorder) failure and operator errors. The diesel-driven auxiliary feedwater pump failure to start was caused by four improperly set relays. These relays were not addressed by maintenance or surveillance procedures, so that the.
failures had not been detected. The turbine-driven auxiliary feedwater pump tripped on low suction pressure, caused by failure of an electrical component in a pressure transmitter. The pump was restarted, but pressure fluctuations and flow oscillations caused the operator to manually trip the pump.
Although the non-ESF electrical auxiliary feedwater pump was available, the event resulted in a total loss of the safety-grade auxiliary feedwater system.
In an Engineering Evaluation Report (Core Damage Precursor Event at Trojan, AE0D/E514, October 1985), the event was considered a severe accident precursor.
5.2 Associated Failures During or subsequent to an ESF actuation, failures may be discovered that are not directly caused by the condition that necessitated the ESF actuation, and thus appear to be separate random events. A total of 45 of the 601 ESF actua-tions (about one out of 13) involved " associated failures." These failures occurred at 33 different units, and only one unit had more than three associated failures (Hatch 1).
At Hatch 1, three of the four associated failures involved an inboard reactor water cleanup (RWCU) isolation valve not isolating three times during a twelve hour period. (Because the redundant outboard isolation valves isolated, these events are not considered total ESF system failures to actuate.) These i
failures were caused by a design error which had existed since the unit began 45
commercial operation in 1975. As a result of these events, the RWCU system's isolation logic circuitry was changed so that inboard and outboard isolation valves would isolate. The remaining associated failures appeared to be random
~
events involving valves, breakers, pumps, and other equipment. Table A.8 in the appendix gives a detailed listing of these associated failures.
5.3 Conclusions o Associated failures are occurring when an ESF actuation is experienced, but no specific trend or pattern could be identified for the failures being experienced.
o While the immediate consequences of the failures experienced were minor for the particular cases investigated, a few of the problems discovered may be significant at other units or under other circumstances. These problems are:
- 1. Failures that have adversely affected the availability of auxiliary feedwater (AFW) have been the subject of several recent reports *. The loss of the safety-grade auxiliary
- (1) Technical Review Report AEOD/T416, " Loss of ESF Auxiliary Feedwater Pump Capability at Trojan on January 22, 1983," dated August 1, 1984.
(2) Engineering Evaluation Report AE00/N402, " Engineering Evaluation of Events Involving Undetected Unavailability of the Turbine-Driven AFW Pump," dated June 15, 1984.
(3) IE Information Notice No. 84-66: " Undetected Unavailability of the Turbine-Driven Auxiliary Feedwater Train," dated August 17, 1984.
46
f .. .
feedwater system at Trojan in September 1984 [Re: LER 84-016]
shows that AFW reliability may still not be uniformily high at all plants.
- 2. Trip devices for electrical heate'rs in Standby Gas Treatm'e nt Systems (SGTs) have been a concern in the past as potential common cause failure mechanisms. The August 2, 1984 loss of Standby Gas Treatment System at Quad Cities 1 [Re: LER84-012]
indicated that high temperature trips of the electric heaters are still a concern.
- 3. The loss of offsite and onsite AC electrical power at Susquehanna 2 on July 26, 1984 discussed in Section 5.1.2
[Re: LER 84-13] has possible generic implications as follows:
(1) adequacy of annunciation and control room indication; (2) restart capability of emergency diesel generators under abnormal conditions; and (3) adequacy of human engineering aspects including labels, administrative controls, and inde-pendent verification requirements. As noted in Section 5.1.2, this event war discussed in Information Notice 84-76.
- 4. The discovery of a design error that has existed since a unit began operating in 1975 during an ESF actuation [Re: Hatch 1 LER 84-029] raises the question of whether other such problems j exist at other operating reactors. AE0D is currently studying design and construction problems at operating nuclear plants.
l l
i I
i 47 i
~ -- - . __
i 6.0
SUMMARY
OF FINDINGS, CONCLUSIONS AND RECOMMENDATIONS It was found that 601 actuations occurred during the last six months of 1984.
Of the 93 units
- eligible to issue LERs (that is, they had an operating li-cense from NRC), 72 units reported at least one ESF actuation. On a percentage basis, 23 percent of the eligible units did not report an ESF actuation during the period, 45 percent reported between one and three actuations, 9 percent reported between four and six actuations and 23 percent reported more than six actuations. Sixteen units (17 percent) reported more than ten ESF actuations.
. The maximum number of actuations at any one unit was 70. Only about 7 per-cent of all reported ESF actuations involved an Emergency Core Cooling System (ECCS), and none of these occurrences were necessary to control an actual loss-of-coolant accident (LOCA). Over 70 percent of the actuations that occurred in ESF Systems were associated with either an isolation function or a ventilation function.It was found that 601 actuations occurred during the last six months of 1984. Of the 93 units
- eligible to issue LERs (that is, they had an opera-ting license from NRC), 72 units reported at least one ESF actuation. On a percentage basis, 23 percent of the eligible units did not report an ESF actua-tion during the period, 45 percent reported between one and three actuations, 9 percent reported between four and six actuations and 23 percent reported more than six actuations. Sixteen' units (17 percent) reported more than ten ESF actuations. The maximum number of actuations at any one unit was 70. Only about 7 percent of all reported ESF actuations involved an Emergency Core Cool-ing System (ECCS), and none of these occurrences were necessary to control an l actual loss-of-coolant accident (LOCA). Over 70 percent of the actuations that occurred in ESF Systems were associated with either an isolation function or a
- ventilation function.
i The 601 ESF actuations were found to be the result of several causes. In 257 cases (43 percent), a measured parameter reached the intended setpoint for ESF actuation. However, the rate for valid and necessary ESF actuations because of design basis events is very low. Only 22 such actuations, or less than four
- percent of all reported actuations, cccurred in the six month study period; l none of these were necessary to control a significant safety event. Thus, l there is little indication that any unit is experiencing serious unresolved
( safety problems which have required mitigating ESF actuations. The remaining 235 cases where a setpoint was reached were considered to be valid, did not 48 1
L .
r-p.. .
~
represent a needed response to a design basis event. These actuations resulted from non-design basis conditions such as radioactive trash being moved near a rai cion monitor. These valid non-design basis events were primarily the result of reactor vessel water level, loss of power, flow, or toxic gas signals, and resulted primarily in isolation or ventilation actuations such as reactor water cleanup (RWCU) or containment isolations, or control room ventilation actuations.
The remaining 57 percent (344 out of 601) of the ESF actuations were deemed to be invalid and unnecessary false actuations. False actuations were caused .
mostly by spurious actuations (almost 90 percent of them during operation),
equipment failures (over 80 percent during operation), and personnel errors (about 75 percent during test or maintenance). Therefore these actuations could be decreased most efffectively by: (1) improvements in equipment; (2) reductions in personnel errors during maintenance and testing; and (3) electromagnetic interference (EMI) protection and other measures to reduce spurious actuations due to electrical noise spikes. The functions most affect-ed by false ESF actuations were isolation (46 percent) and ventilation (31 per-cent). Equipment failures causing false ESF actuations were associated with power (29 percent), temperature monitoring (19 percent), toxic gas monitoring (18 percent), radiation monitoring (60 percent), fire detection (10 percent),
and flow measurements (9 percent).
A few specific units are experiencing frequent or unnecessary challenges.
In general, corrective actions and improvement programs have been implemented, but the effectiveness has varied. The specific units and concerns where problems appear to persist are: San Onofre 2 and 3'(toxic gas and radiation monitor actuationd, Byron 1 (radiation actuations), Callaway 1 (radiation dCtuations), Sequoyah i and 2 (radiation actuations), WPPSS 2 (radiation actua-tions and RWCU isolatfor.s) and LaSalle 1 and 2 (RWCU isolations). Depending on the actuation trends, further actions may be warranted, such as thorough investigation into causes and corrective actions take1.
In 44 of the ESF actuations at 32 units, an emergency core cooling system (ECCS) was actuated. Fluid was actually injected into the reactor coolant sys-tem in 20 of the 44 events. Nineteen units experienced these safety injection 49
events, with no unit experiencing more than two injections. Of the 20 actual injection events, none were needed to control an actual LOCA, and only one was considered a valid design basis actuation. Ten of the events resulted from setpoints being reached, about half of these as a result of low water level fol-lowing reactor scrams. The remaining nine safety injection events were false actuations, primarily the result of personnel errors during maintenance or testing. The number and severity of safety injection events occurring during -
the period of this study do no appear to be sufficient to prompt immediate con-cern. Thus, the safety injections that occurred during the period of this study do not appear to warrant further action. AE00 will continue to monitor these actuations during subsequent studies.
In only three of the 601 ESF actuations did an ESF system fail to actuate prop-erly. In 45 additional cases the ESF actuations performed properly, but one or more failures were associated with the actuaticn sequence. There was no identifiable trend or pattern for these failures, and redundant systems were available to perform required safety functions.
1
\'
Finally, the wide variety of ESF systems and the differences in the types of ESF actuations (including variations in immediate safety significance) make comparisons among units very difficult. Li'miting the actuations included in the statistics to more significant events such as safety injections (which are more ar less comparable across plants) does not seem practical because such events are rare and little discrimination in performance would result either among plants or over time for a given plant.
The distribution of ESF actuation rates among plants (i.e., the vast majority of plants have fairly low rates, and only 25 percent or so have relatively high rates) and the variety of ESF actuations suggest a two-step strategy for using ESF actuations as a performance indicator: first, to use a value of 10 ESF actuations in a 6 month period as an alert level (plants with a value below this frequency are deemed acceptable with no further analysis made); and '
secondly, to perform a detailed examination of the circumstances- for the plants exceeding the threshold, with unacceptable performance being fre@ent actuations as a result of ineffective corrective actions. Sustained operation (e.g., two consecutive 6 month periods) with a high rate of ESF actuations may be indicative of a willingness to accept ESFs that are not performing as intended.
50
. . . . ....m ... ___..__m
Table A.1 Number of ESF Actuations 2nd Half of 1984 Unit ESF Actuations Unit ESF Actuations San Onofre 2 CE 70 Haddam Neck W 2 WPPSS 2 GE 49 Dresden 3 GE- 2 LaSalle 2 GE 49 Browns Ferry 1 GE 2 Callaway 1 W 45 Vermont Yankee GE 2 Brunswick 1 GE 39 Salem 1 W 2 Byron 1 W 37 Surry 1 W 2 LaSalle I GE 32 Cook 1 W- 2 Limerick 1 GE 28 North Anna 2 W -
2 Sequoyah I W 18 Trojan W 2 Hatch 1 GE - 13 Arkansas 2 CE 2 Hatch 2 GE 13 McGuire 1 W 1 Grand Gulf 1 GE 12 Summer 1 W- 1 Ft. Calhoun CE 12 Arkansas T B&W 1 Duane Arnold GE 11 Crystal River 3 B&W 1 Susquehanna 2 GE 10 Beaver Valley 1 W 1 Monticello GE 10 /itzpatrick GE 1 Diablo Canyon 1 W ~
9 Ir;dian Point 3 W 1 Catawba W 8 Millstone 2 CE - 1 Susquehanna 1 GE 7 iiine Mile Point GE 1 St. Lucie 2 CE 7 San Onofre 1 W-1 Cook 2 W- 7 Cooper GE 1 Pilgrim 1 GE 7 Calvert Cliffs 1 CE 1
~
Yankee Rowe W 6 Calvert Cliffs 2 CE 1 Sequoyah 2 W- 5 Davis Desse 1 B&W 1 Browns Ferry 5 GE 5 Ginna W I Lacrosse AC 5 North Knna 1 W 1 Quad Cities 1 GE 5 Robinson 2 W -
1 Quad Cities 2 GE 4 Humbolt Bay GE 1 Brunswick 2 GE 4 Salem 2 W 1 Kewaunee W 4 St. Lucie 1 CE 1 Indian PoTnt 2 W -
3 Surry 2 W 1 McGuire 2 W 3 Zian 2 W- 1 Oyster Creik GE 3 Waterford 3 CE 1 Palisades CE 3 Dresden 2 GE O Peach Bottom 3 GE 3 Farley 1 W 0 Point Beach 2 W- 3 Farley 2 W 0 Prairie Island ! W- 3 Oconee 1 H&W 0 San Onofre 3 CE 3 Oconee 2 B&W 0 Turkey Point 4 W 3 Maine Yankee CE 0 Oconee 3 B&W ~ 0 Millstone 1 GE 0 Point Beach 1 W~
0 Peach Bottom 2 GE O TN! 1 B&W 0 Prairie Island 2 W 0 TMI 2 B&W 0 Rancho Seco B&W - 0 Big Rock Point GE 0 Turkey Point 3 B&W 0 Browns Ferry 2 GE 0 Zion 1 W 0 Ft. St. Vrain GA 0 Palo Verde 1 CE O Shoreham GE 0 51 L ;
TABLE A.2 ESF ACTUATIONS REPORTED BY COWERCIAL U.S. NUCLEAR POLER PLANTS JULY 1 1984 T) ROUGH DECEMBER 31. 1984 DOCKET REPORT EVENT UNIT NAE NUMBER MJMBER DATE/ TIE REACTOR (NSSS) VENDOR REACTOR TYPE
" PRESSURIZED LIGHT ETER
- 4. BEAVE9 VALLEY 50-334 84-012 841018/1435 ESTINGHOUSE PRESSLRIZED LIGHT ETER
- 5. BR0lM3 FERRY 1 50-259 84-032 840814/0938 GOERAL ELECTRIC BOILINGLIG!ifWATER
- 7. BROW O FERRY 3 50-296 84-000 840727/2217 OEERAL ELECTRIC BOILING LIGHT WATER
- 8. BR0lMS FERRY 3 50-296 84-009 840913/1443 GDERAL ELECTRIC BOILING LIGHT WATER
- 9. BR0lMS FERRY 3 50-296 84-009 840915/1523 GEERAL ELECTRIC BOILING LIGHT WATER
- 11. BR0lMS FERRY 3 50-296 84-015 841209/ MISSING GDERAL ELECTRIC BOILING LIGHT WATER
- 12. R NSWICK 1 50-325 84-0!! 8M711/1215 GENERAL ELECTRIC BOILING LIGHT WTER
- 15. BRUNSWICK 1 50-325 84-016 840007/0134 GEERAL ELECTRIC BOILING LIGHT ETER
- 16. BPU G ICK 1 50-325 84-013 840817/1301 GDERAL ELECTRIC BOILING LIGHT ETER
- 17. BRUNSWICK 1 50-325 84-020 8M902/1625 CDERAL ELECTRIC BOILING LIGHT WATER
- 19. BRUNSWICK 1 50-325 84-022 840906/1240 GEERAL ELECTRIC BOILING LIGHT WATER
- 21. BRUNSWICK 1 50-325 84-026 840918/1039 00ERAL ELECTRIC BOILING LIGHT WATER
- 23. BRUNSWICK 1 50-325 84-027 840930/0926 GDERAL ELECTRIC BOILING LICHT ETER
- 24. BRUNSWICK 1 50-325 84-029 841022/1624 GDERAL ELECTRIC BOILING LIGHT 1ATER
- 25. BRtNSWICK 1 50-325 84-028 841029/1430 GDERAL El.ECTRIC BOILING LIGHT ETER
- 26. BRU G ICK 1 50-325 84-031 841106/2325 GDERAL ELECTRIC BOILING LIGHT WATER
- 27. BRt G ICK 1 50-325 84-031 841107/0016 GDERAL ELECTRIC BOILING LIGHT WATER
- 29. BRlNSWICK ! 50-325 84-031 841109/1119 ODERAL ELECTRIC BOILING LIGHT WATER
- 30. BRUNSW!CK 1 50-325 84-031 841109/1528 GENERAL ELECTRIC BOILING LIGHT WATER '
- 32. BRt G ICK 1 50-325 84-031 841113/ MISSING GENEPAL ELECTRIC BOILING LIGHT WATER
- 33. BRU G ICK 1 50-325 84-031 841113/1955 GDERAL ELECTRIC BOILING LIGHT E TER 34 BRtMWICK 1 50-325 84-031 841113/2336 COERAL ELECTRIC BOILING LIGHT WATER
- 35. BRtNSW!CK 1 50-325 84-032 841116/0150 GOERAL ELECTRIC BOILING LIGHT WATER
- 36. IGUNSWICK 1 50-325 84-032 841116/0202 GENERAL ELECTRIC BOILING LIGHT ETER
- 37. BRU G ICK ! 50-325 84-032 841116/0400 CDERAL E11CTRIC BOILINGLICHTWATER
- 39. BRUNSWICK 1 50-325 84-032 841116/0605 GENERAL ELECTRIC BOILING LICHT WATER
- 41. BRU G ICK 1 50-325 84-030 841208/0359 ODERAL ELECTRIC B0ILING LIGHT WATER
- 42. BRU G ICK 1 50-325 84-030 841208/1624 GENERAL ELECTRIC B0! LING LIGHT WATER
- 43. BRL W ICK 1 50-325 84 030 841208/1751 GEERAL ELECTRIC BOILING LIGHT WATER
- 44. BRLNSWICK 1 -
50-325 84-036 841211/1547 ODERAL ELECIRIC E LING LIGHT WATER
- 46. BRU G ICK 1 50-325 84-036 841212/1458 00ERAL ELECTRIC BOILING LIGHT WATER 47 BRUN?. LICK 1 50-325 84-030 841213/0912 CEERAL ELECTRIC POILING LIGHT WATER
- 48. BRU G ICK 1 50-325 84-036 841217/0030 CENERAL ELECTRIC BOILING LIGHT WATER 49 R O ICK 1 50-325 84-036 841213/2040 CEERAL ELECTRIC BOILING LIGHT E TER
- 51. BRl G ICK 2 50-324 84-011 840924/2134 CEERAL ELECTRIC BOILING LIGHT WATEA
- 53. BAMWICK 2 50-324 84-014 841128/0100 CEERAL ELECTRIC BOILING LIGHT E TER 54 R NSWICK 2 50-324 84-017 841130/1 W CEERAL ELECTRIC BOILING LIGHT WATER 52
- 55. BYI10N 50-454 M-011 M1100/1000 ESTINGHOUSE PIESSLftIZED LIGHT MTER.
SE BYRON 50-454 M410 841112/0830 ESTINGHOUSE PRESSlft! ZED LIGHT 11TER.
- 57. BYRON 50-454 84410 841119/NISSING ESTINGHOUSE PIESSLftIZED LIGHT WATER
- 58. BYRON 50-454 M-017 841123/2145 ESTINGHOUSE PRESSURIZG LIGHT M TER
- 59. BYRON 50-454 84-019 841127/0746 ESTINGHOUSE PESSURIZG LIGHT MTER
- 60. BYRON 50-454 M421 841127/1114 ESTINGHOUSE PESSlft!ZG LIGHT MTER
- 61. BYRON 50-454 84-019 841127/1540 ESTINGHOUSE PESSLRIZED LIGdT WATER
- 62. BYRON 50-454 84-018 841128/0837 ESTINGHOUSE PIESSlftIZED LIGHT MTER
- 63. BYRON 50-454 84-021 841128/1130 ESTINGHOUSE PIESSLAt! ZED LIGHT MTER
- 64. BYRON 50-454 84419 841128/1135 ESTINGHOUSE PRESSURIZED LIGHT WATER
- 65. . BYRON 50-454 84422 841129/2312 ESTINGHOUSE P!ESSt#tIZED LIGHT WATER
- 66. BYRON 50-454 84421 M1130/0311 lESTINGHOUSE PfES$lRIZE LIGHT WATER
- 67. BYRON 50-454 84-021 Mll30/1210 IESTIleCUSE PIESSLft!!ED LIGli MTER
- 68. BYRON 50-454 M422 841130/2114 ESTINGHOUSE PflESSURIZED LIGHT MTER
'69. BYRON 50-454 84-021 841201/1115 IESTINGHOUIE PRESSURIZG LIGHT M TER
- 70. BYRON 50-454 M-019 M1202/1458 lESTIN0 HOUSE PflESSURIZED LIGHT WATER
- 71. BYRON 50-454 M-022 841202/2059 lESTINGHOUSE PESSURIZE LIGHT WATER
- 72. BYRON 50-454 84421 841203/0313 IESTINGHOUSE PilESSlftIZG LIGHT MTER
- 73. BVRON 50-454 84422 841203/1358 IESTINGHOUSE PIESSLft! ZED LIGHT MTER
- 74. BYRON 50-454 84429 841205/0541 lESTINGHOUSE PflESSURIZG LIGHT WATER
- 75. BYRON 50-454 84-028 841207/0041 ESTINGHOUSE PIESSt#t!ZG LIGHT WATER
- 76. BYRON 50-454 84-028 841212/01 % ESTINGHOUSE PRESSURIZED LIGHT WATER
- 77. BYRON 50-454 84-027 841212/0750 lESTINGHOUSE PRESSURIZG L10HT WATER
- 78. BYRON 50-454 84-031 841215/2025 ESTINGHOUSE P!ESSURIZG LIGHT MTER
- 79. BYRON 50-454 84-031 841217/1704 IESTINGHOUSE PRESSURIZZD LIGHT M TER
- 80. BYRON 50-454 84-030 841218/0334 ESTINGHOUSE PfESSLRIZED LIGHT WCER'
- 81. BYIl0N 50-454 84-033 841218/2250 ESTINGHOUSE PIESSURIZG LIGHT WATER
- 82. BYRON 50-454 84431 841219/0013 lESTINGH00SE PIESSURIZED LIGHT MTER
- 83. BYll0N 50-454 84-027 841221/0026 ESTINGHOUSE PIESSLRIZED LIGHT WATER
- 84. BYRON 50-454 84-027 841222/1522 lESTINGHOUSE PfESSLRIZED LIGHT WATER
- 85. BYR0h 50-454 84-039 841225/0755 lESTIN0 HOUSE PflESSURIZED LIGHT WATER
- 86. BYRON 50-454 84-033 841226/1034 lESTINGHOUSE PflESSURIZED LIGHT WATER
- 87. BYRON 50-454 84-035 841226/1214 lESTIN0 HOUSE PfESSLRIZED LIGHT MTER
- 88. BYRON 50-454 84-033 841226/1N0 lESTINGHOUSE PRESSLAIZED LIGHT MTER
- 89. BYRON 50-454 84-037 841226/2315 ESTINGHOUSE PRESSLRIZG LIGHT WATER
- 90. BYRON 50-454 84-033 841230/0557 lESTINGHOUSE PflESSLRIZE LIGHT WTER
- 91. BYRON 50-454 84-038 841231/0937 lESTINGHOUSE PRESSLRIZG LIGHT WATER
- 92. CALLAWAY 50-483 84-018 840718/1455 WESTINGHOUSE PflESSURIZED LIGHT WATER
- 93. CALLAWAY 50-483 84-019 840719/0912 ESTINGHOUSE PRESSLRIZED LIGHT WATER
- 94. CALLAWAY 50-483 MISSING 840808/ MISSING ESTINGHOUSE PflESSLRIZED LIGHT WATER I
- 95. CALL M Y 50-483 84425 840810/1412 WESTINGHOUSE PflESSURIZED LIGHT WATER
- 96. CALLAWAY 50-483 8',-028 840813/1225 lESTINGH0VSE PRESSURIZED LIGHT WATER
- 97. CALLAWAY 50-483 8 427 840813/1640 ESTINGHOUSE PRESSURIZED LIGHT M TER
- 98. CALLAWAY 50-483 84-027 840817/1525 ESTINGHOUSE PRESSURIZED LIGHT WATER
- 99. CALLAWAY 50-483 84-032 840820/0246 ESTINGHOUSE PflESSLRIZED LIGHT WATER 100. CALLAWAY 50-483 84-034 840822'2317 ESTIN0 HOUSE PRESSLRIZED LIGHT WATER 101. CALL M Y 50-483 04-036 840824/0551 WESTINGHOUSE PRESSURIZED LIGHT WATER 102. CALLAWAY 50-483 84-036 840625/1323 ESTINGHOUSE PRESSURIZED LIGHT WATER 103. CALL M Y 50-483 84-036 840026/1431 WESTINGHOUSE PfqESSlRIZED LIGHT MTER 104 CALL M Y 50-483 84-036 840827/1825 WESTINGHOUSE PRESSURIZED LIGHT W TER 105. CALLAWAf 50-483 84436 840828/0040 WESTINGHOUSE PRESSURIZED LIGHT W TER <
106. CALL M Y 50-483 84 435 840907/1030 ESTINGH0VSE PRESSLRIZED LIGHT WATER 107. CALLAWAY 50-483 84-036 840908/1841 ESTINGHOUSE PRESSLRIZED LIGHT MTER 108. CALLAWAY 50-483 84-036 840914/0927 WESTINGHOUSE P!ESSURIZED LIGHT WATER 109 CALL M Y 50-433 84-040 840915/1023 WESTI'G0JSE PRESSURIZED LIGHT WATER 110. CALLAWAY 50-483 84-042 840923/0605 WESTINGHOUSE PRESSURIZED LIGHT WATER 111. CALLAWAY 50-483 84-045 840930/1029 ESTINGHOUSE PRESSURIZED LIGHT WATER 112. CALLAWAY 50-403 84-046 841005/1720 ESTINGHOUSE PRESSURIZED LIGHT WATER 113. CALLAWAY 50-483 84-047 841006/1437 ESTINGHOUSE PRESSURIZED LIGHT WATR 114. CALLAWAY 50-483 84440 84100e/2120 WESTINGHOUSE , PRESSURIZED LIGHT MIER 113. CALLAWAY 50-483 84-040 841010/1424 ESTINGHOUSE PflESSURIZED LIGHT MTER
!!6. CALL M Y 50-403 84448 8410!!/0334 IESTINGHOUSE PRESSURIZED LIGHT WATER 117. CALLAWAY 50-483 84-051 841014/1848 IESTINGHOUSE PRESSURIZED LIGHT WATER 53
!!81 CALL M Y 50-483 84-052 841016/1310 ESTINGHOUSE PRESSWIZED LIGHT WATER 119. CALL e y 50-483 84-054 841019/1549
- ESTINGHOUSE PRESSLRIZED LIGHT WATER 120! CALLAWAY 50-483 84-055 841021/0518 WESTINGHOUSE PRESSURIZED LIGHT WATER 121. CALLAWAY 50-183 04-054 841021/1208 WESTINGHOUSE PRESSLRIZED LIGHT WATER 122. CALLAWAY 50-433 84-056 841022/0513 WESTINGHOUSE PRESSLRIZED LIGHT WATER 123. CALL M Y 50-483 84-048 841022/1652 ESTINGHOUSE PRESSURIZED LIGHT WATER 124. CALLAWAY 50-483 84-056 841023/1527 ESTINGHOUSE PRESSURIZED LIGHT WATER 125. CAL.WAY 50-483 84-057 841027/0350 WESTIN0HQJSE PRESSLRIZED LIGHT WATER 126. CALL M Y 50-483 84-058 841030/1152 WESTIN0riOUSE PRESSURIZED LIGHT WATER 127. CALL E Y 50-483 84-059 841105/1156 WESTINGHOUSE PRESSWIZED LIGHT WATER 128. CALAWAY 50-483 84-059 841106/0450 ESTINGHOUSE PRESSURIZED LIGHT WATER 129. CALL M Y 50-483 84-060 841114/1451 ESTINGHOUSE PRESSURIZED LIGHT WATER 130. CALL M Y 50-483 84-061 841129/0305 ESTINGHOUSE PRESSURIZED LIGHT WATER 131. CALLAWAY 50-483 84-062 841207/2103 ESTINGH015E PRESSURIZED LIGiT WATER 132. CALL M Y 50-483 84-063 841209/1449 WESTINGH3fSE PRESSLRIZED LIGHT ETER 7133. CALLAWAY 50-483 84-063 841214/1229 ESTINGiOUSE PRESSURIZED LIGHT WATER 134. CALLAWAY 50-483 84-065 841217/1208 ESTINGHOUSE PRESSW IZED LIGHT WATER .
135. CALLAWAY 50-483 84-065 841218/0036 ESTINGHOUSE PRESSLRIZED LIGHT WATER 136. CALLAWAY 50-483 84-067 841230/0813 WESTINGHOUSE PRESSURIZED LIGHT ETER 137. CALVERT CLIFFS 1 50-317 84-007 840724/1249 C0MPJST!0N ENGIEERING PRESSURIZED LIGHT WATER 138. CALVERT CLIFFS 2 50-318 84-000 841003/1948' COMBUSTION ENGIEERING PRESSLRIZED LIGHT WATER 139. CATAWBA 50-413 84-008 840822/1401 ESTINGHOUSE PRESSLRIZED LIGHT WATER 140. CATAWBA 50-413 84-017 841012/0635 WESTINGH0lf3E PRESSURIZED LIGHT WATER 141. CATAWBA 50-413 84-021 841114/1029 ESTIN00)SE PRESSURIZED LIGHT WATER 142. CATAWBA 50-413 84-023 841119/0645 WESTINGHOUSE PRESSURIZEDLIGHTWATER 143. CATAWBA 50-413 84-024 841124/1339 ESTINGHOUSE PRESSURIZED LIGiT WATER 144. CATAWBA 50-413 84-025 841127/M34 WESTINGHOUSE PRESSURIZED LIGHT WATER 143. CATAWBA 50-413 84-028 841205/0!!! ESTING0JSE PRESSLRIZED LIGHT WATER 146. CATAWBA 50-413 84-031 841216/1606 ESTINGHOUSE PRESSURIZED LIGHT ETER 147. C00K-1 50-315 84-017 840810/1524 ESTINGHOISE PRESSWIZED LIGHT WATER 148. C00K-1 50-315 84-018 840814/1529 ESTINGHOUSE PRESSURIZED LIGHT WATER 149. C00K-2 50-316 84-020 840805/1414 ESTINGHOUSE PRESSLRIZED LIGHT WATER 150. C00K-2 50-316 84-024 840911/1517 ESTINGHOUSE PRESSURIZED LIGHT WATER 151. C00K-2 50-316 84-025 840912/0733 WESTINGHOUSE PRESSURIZED LIGHT WATER 152. C00K-2 50-316 84-029 841111/0737 WESTINGHOUSE PRESSURIZED LIGHT WATER 153. C00K-2 50-316 84-031 841120/1610 ESTINGHOUSE PRESSlRIZED LIGHT WATER 154. C00K-2 50-316 84-034 841223/0203 ESTINGHOUSE PRESSWIZED LIGHT WATER 155. C00K-2 50-316 84-034 841223/M49 WESTINGHOUSE PRES 9A! ZED LIGHT WATER 156. COOPER 50-298 84-010 840808/ MIS $1NG GENERA ELECTRIC BOILING LIGHT WATER 157. CRYSTAL RIVER 3 50-302 84-015 840713/1752 BAK0CK & WILCOI PRESSURIZED LIGHT WATER 158. DAVIS BESSE I 50-346 84-013 840911/1235 BABC0CK & WILCOX PRESSURIZED LIGHT WATER 159 DIABLO CANYON 1 50-275 84-018 840706/0340 WESTIEH0lGE PRESSLRIZED LIGHT WATER 160. DIAR O CANYON 1 50-275 84-019 840714/1417 WESTINGH0l5E FRESSURIZED LIGHT WATER 161. DIABLO CANYON 1 50-275 84-020 840719/0925 WESTIEHOUSE PRES $lRIZED LIGHT WATER 162. DIABLO CANYON 1 50-275 84-022 840728/0709 WESTIEHOUSE PRESSLRIZED LIGHT WATER 163. DIARO CANYON 1 50-275 84-023 840730/1327 ESTINGHOUSE PRESSURIZED LIGHT WATER 164 DIAR O CANYON 1 50-275 84-023 841029/2121 WESTINGHOUSE PRESSURIZED LIGHT WATER 163. DIABLO CANYON 1 50-275 84-029 841104/2328 WESTINGHO)SE PRESSURIZED LIGHT WATER 166. DIABLO CANYON 1 50-275 84-030 841124/!416 WESTIMH0)SE PRES 9)RIZED LIGHT WATER 167 DIAR 0 CANYON 1 50-275 84-034 841215/2316 WESTINGHOUSE PRESSWIZED LIGHT WATER 168. DRESDEN 3 50-249 84-007 840722/ MISSING C{NERA ELECTRIC BOILING LIGHT WATER 169 DRESDEN 3 50-249 84-020 841026/0908 GEERAL ELECTRIC B0! LING LIGHT WATER 170. DJANE ARNOLD 50-331 84-027 840713/0902 GENERAL ELECTRIC BOILING LIGPT WATER 171. DUAE ARNCLD 50-331 84-028 840714/1524 GCERAL ELECTRIC BOILING LIGHT WATER 172. DUAT ARNOLD 50-331 84-032 840904/0240 GEERAL ELECTRIC BOILI E LIGHT WATER 173. Dl m E AR ELD 50-331 84-032 840916/0225 CENERAL ELECTRIC BOILING LIGii WATER 174. DUAE ARNOLD 50-331 84-032 840916/0500 GENERAL ELECTRIC B0! LING LIGHT WATER 175. DUAE ARELD 50-331 84-036 840925/0331 GEERAL ELECTRIC BOILING LIGHT WATER 176. DJANE ARNOLD 50-331 84-036 840930/0256 GENERAL ELECTRIC BOILING LIGiT WATER 177. DUANE ARN0LD 50-331 84-036 841020/1515 OENERAL ELECTRIC BOILING LIGHT WATER 173. Dl M E ARNOLD 50-331 84-039 841101/1331 GENERAL ELECTRIC BOILIE L10HT WATER 179 DUANE ARNDLD 50-331 84-042 841123/0640 GEERAL ELECTRIC B0! LIE LIGHT WATER 180. DUANE ARNOLD 50-331 84-043 841206/0730 CENERA ELECTRIC BOILING LIGiT WATER 54
181.' FITZPATRICK 50-333 84-023 841104/ MIS $1NG GEERE ELECTRIC BOILING LIGHT WATER
=
182. FT. LALHOUN 50-285 84414 840703/1100 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 183. FT. CALHOUN 50-285 84-017 840003/1645 COMBUSTION ENGIEERING PRESSLRIZED LIGHT ETER 184. FT. CALHOUN 50-285 84-018 840807/1105 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 185. FT. CRHOUN 50-285 64-019 840902/0442 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 186. FT. CALHOUN 50-285 84-010 840921/1245 COMBUSTION ENGINEERING PRESSlRIZED LIGHT WATER 187. FT. CALHOUN 50-285 84-023 841118/2101 COMBUSTION ENGIEERIW PRESSURIZED LIGHT WATER 188. FT. CALHOUN 50-285 84-023 841118/2145 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 189. FT. CALWUN 50-285 84-023 641119/0110 COMBUSTION ENGINEERING PRESSURIZED LIGHT ETER 190. FT. CR HOUN 50-285 84-023 841119/0044 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 191. FT. CALHOUN 50-285 84-023 841124/2000 COMBUSTION ENGINEERING PRESSLRIZED LIGHT WATER 192. FT. CALHOLN 50-285 84-024 841126/0644 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 193. FT. CALHOUN 50-285 84-025 041207/1329 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 194. GIWA 50-244 84-009 840817/1445 WESTINGHOUSE PRESSLRIZED LIGHT WATER
'195. GRAND OULF 1 50-416 84-039 840818/1345 GEERAL ELECTRIC BOILING LIGHT WATER 196. GRAND GLLF 1 50-416 84-043 841002/0945 GEERAL ELECTRIC BOILING LIGHT WATER 197. GRAND GlLF 1 50-416 84-044 841006/0440 GEERAL ELECTRIC BOILING LIGHT WATER 198. GRAND OULF 1 50-416 84-045 841014/1700 GENERAL ELECTRIC BOILING LIGHT WATER 199. GRAND 00LF 1 50-416 84-046 841017/1450 GEERE ELECTRIC BOILING LIGHT WATER 200. ORAND GULF 1 50-416 84-051 841102/1921 GEERAL ELECTRIC BOILI E LIGHT WATER 201. ORAND OULF 1 50-416 84-051 841103/0650 GEERAL ELECTRIC BOILING LIGHT WATER 202. GRAND GLLF 1 50-416 84-053 841129/0055 GEERAL ELECTRIC BOILING LIGHT WATER 203. GRAND GlLF 1 50-416 84-056 841219/2035 GEERE ELECTRIC BOILING LIGHT WATER 204. GRAND GULF 1 50-416 84-057 841221/0448 GENERAL ELECTRIC BOILING LI0hT WATER 205. GRAND GULF 1 50-416 84-059 841221/1000 GEERAL ELECTRIC BOILING LIGHT WATER 206. GRAND GULF 1 50-415 84-058 841224/1232 GEERAL P.ECTRIC BOILING LIGHT WATER 207. HADDAM ECK 50-213 84-009 840001/1051 ESTINGHOUSE PRESSLRIZED LIGHT WATER 208. %DDAM ECK 50-213 04-014 840824/1325 WESTINGHOUSE PRESSLEIZED LIGHT WATER 209. HATCH-1 50-321 84-013 840727/ MISSING GEERAL ELECTRIC BOILING LIGHT WATER 210. HATCH-1 50-321 84-015 840803/2151 GENERAL ELECTRIC BOILING LIGHT WATER 211. HATCH-1 50-321 84-010 840820/0907 OEERAL ELECTRIC BOILING LIGHT WATER 212. HATCH-1 50-321 84-010 840822/2136 GENERAL ELECTRIC BOILING LIGHT WATER 213. HATCH-1 50-321 84-023 841106/2115 GEERAL ELECTRIC BOILING LIGHT WATER 214. HATCH-1 50-321 84-023 841107/1911 GENERAL E1.ECTRIC BOILING LIGHT ETER 215. HATCH-1 50-321 84-020 841216/1700 GEERAL ELECTRIC BOILING LIGHT ETER 216. HATCH-1 50-321 84-020 841219/0930 GEERAL ELECTRIC BOILING LIGHT WATER 217. HATCH-1 50-321 84-029 841224/1213 GENERAL ELECTRIC BOILING LIGHT E TER 218. HATCH-1 50-321 84-029 841224/1345 GENERAL ELECTRIC BOILING LIGHT ETER 219. HATCH-1 50-321 84-029 841225/0105 CEERAL ELECTRIC BOILING LIGHT WATER 220. HATCH-1 50-321 84-029 841225/1801 GEERAL ELECTRIC BOILING LIGHT WATER 221. ETCH-1 50-321 84-020 841228/1231 GEERAL ELECTRIC BOILING LIGHT WATER 222. HATCH-2 50-366 84-009 840711/0745 GEF_RAL ELECTRIC BOILING LIGHT WATER 223. HATCH-2 50-366 84-012 840008/0535 GENERAL ELECTRIC BOILING LIGHT WATER 224. HATCH-2 50-366 84-016 840815/1830 GENERAL ELECTRIC BOILING LIGHT WATER 225. HATCH-2 50-366 84-010 840908/1500 GEERAL ELECTRIC BOILING LIGHT WATER 226. HATCH-2 50-366 84-007 840908/2317 GENERAL ELECTRIC BOILING LICHT WATER 227. HATCH-2 50-366 84-021 840921/1701 GEERAL ELECTRIC BOILINGLIGHTWATER 228. HATCH-2 50-366 84-019 840924/1757 GENERAL ELECTRIC BOILING LIGHT WATER 229. HATCH-2 50-366 84-019 840924/1823 GEERAL ELECTRIC BOILING LIGHT WATER 230. HATCH-2 50-366 84-019 840924/1948 CENERAL ELECTRIC BOILING LIGHT WATER 231. HATCH-2 50-366 84-019 840924/2220 GENERAL ELECTRIC BOILING LIGHT WATER 232. HATCH-2 50-366 84-024 841011/1715 CENERAL ELECTRIC BOILING LIGHT WATER 233. HATCH-2 50-366 84-031 841031/2200 GEERAL ELECTRIC BOILING LIGHT WATER 234. HATCH-2 50-366 84-035 841213/2109 GENERAL ELECTRIC BOILING LIGHT WATER 235. HUMBOLDT BAY 50-133 84-002 841206/1500 CENERAL ELECTRIC BOILING LIGHT ETER 236. INDIAN POINT 2 50-247 84-008 840713/1445 WESTIWHOUSE PRESSURIZED LICeT ETER 237. INDIfW POINT 2 50-247 84-016 841016/2126 WESTINGH0lGE PRES $URIZED LIGHT E TER 238. INDIAN POINT 2 50-247 84-026 841228/2220 WESTINGHOUSE. PRESSLRIZED LIGHT WATER 239. INDIAN PT. S 50-286 84-015 841116/1242 ESTINGHOUSE PRESSURIZED LIGHT ETER 240. KEWAUNEE 50-305 84-013 840702/0105 WESTINGHOUSE PPISSURIZED LICcT ETER 241. KEWAUNEE 50-305 84-016 840914/1026 WESTINGHOUSE PRESSURIZED LIGHT ETER 242. KEElhEE 50-305 84-019 841114/0322 WESTINGHOUSE PRESSURIZED LIGHT WATER 243. KEWAUNEE 50-305 84-020 841216/0405 WESTINGHOUSE PRESSLRIZED LIGhi ETER 55
244,* LACROSSE 50-409 84411 840716/1750 OTER BOILING LIGHT WATER
. 245 LACROSSE 50-409 84-015 840829/0945 OTER BOILING LIGHT E TER 246. LACROSSE 50-409 84-017 841016/0915 OTER BOILING LIGHT WATER 247. LACROSSE 50-409 84-020 841113/0809 OTER BOILING LIGHT WATER 248. LACROSSE 50-409 84-021 841124/1340 OTER BOILING LIGHT WATER 249. LASALLE 1 50-373 84-045 840715/0511 GEERAL ELECTRIC BOILING LIGHT WATER 250. LASALLE 1 50-373 84-046 840727/2140 GEERE ELECTRIC BOILING LIGHT M TER 251. LASALLE 1 50-373 84-046 840727/2150 GENERAL ELECTRIC BOILING LIGHT WATER 252. LASALLE 1 50-373 84-046 84M77/2200 GENERAL ELECTRIC BOILING LIGHT WATER 253. LASALLE 1 50-373 84-046 840723/0441 GEERAL ELECTRIC BOILING LIGHT WATER 254. LASALLE 1 50-373 84-047 840007/2137 GEERAL ELECTRIC BOILING LIGHT WATER 255. LASALLE 1 50-373 84-049 840824/1550 GOERAL ELECTRIC BOILING LIGHT E TER 256. LASALLE 1 50-373 84-049 840824/1725 GDERAL ELECTRIC BOILING LIGHT E TER 257. LASALLE 1 50-373 84-050 840828/0105 GOERAL ELECTRIC BOILING LIGHT WATER
-258. LASALLE 1 50-373 84-052 840915/0820 GDERAL ELECTRIC BOILING LIGHT E TER
'259. LASALLE 1 50-373 84-053 840916/0440 GEERAL ELECTRIC BOILING LIGHT WATER 260. LASALLE 1 50-373 84-056 840921/NISSING GOERAL ELECTRIC BOILING LIGHT WATER 261. LASALLE 1 50-373 84-055 840921/1647 GDERAL ELECTRIC BOILING LIGHT WATER 262. LASALLE 1 50-373 84-054 840921/2005 GDERAL ELECTRIC
' BOILING LIGHT WATER 263. LASALLE 1 50-373 84-060 840929/1000 GOERAL ELECTRIC BOILING LIGHT WATER 264. LASALLE 1 50-373 84-058 841001/1256 GDERAL ELECTRIC BOILING LIGHT WATER 265. LASALLE 1 50-373 84-057 841001/2211 GDERE ELECTRIC BOILING LIGHT E TER 266. LASALLE 1 50-373 84-066 841015/0249 GDERAL ELECTRIC BOILING LIGHT WATER 267. LASALLE 1 50-373 84-071 841024/1330 GEERAL ELECTRIC BOILING LIGHT WATER 268. LASALLE 1 50-373 84-068 841101/0344 GENERAL ELECTRIC BOILING LIGHT WATER 269. LA%LLE 1 50-373 84-073 841106/1130 GDERAL ELECTRIC BOILING LIGHT ETER 270. LASALLE 1 50-373 84-074 841107/1255 GDERAL ELECTRIC BOILING LIGHT WATER 271. LASALLE 1 50-373 84-076 841111/1019 GOERAL ELECTRIC BOILING LIGHT WATER 272. LASALLE 1 50-373 84-077 841115/0815 GOERAL ELECTRIC BOILING LIGHT WATER 273. LASALLE 1 50-373 84-078 841117/1331 GDERAL ELECTRIC BOILING LIGHT WATER 274. LASALLE 1 50-373 84-081 841123/0924 GDERR ELECTRIC BOILING LIGHT WATER 275. LASALLE 1 50-373 84-082 841124/1044 GDERAL ELECTRIC BOILING LIGHT WATER 276. LASALLE 1 50-373 84-004 841130/2040 GEERAL ELECTRIC BOILING LIGHT MTER 277. LASALLE 1 50-373 84-091 841220/1930 GENERAL ELECTRIC BOILING LIGHT WATER 278. LASALLE 1 50-373 84-087 841222/0000 GDERAL ELECTRIC BOILING LIGHT WATER 279. LASALLE 1 50-373 84089 841225/1716 GDERAL ELECTRIC BOILING LIGHT WATER 280. LASALLE 1 50-373 84-090 841226/2045 GDERAL ELECTRIC BOILING LIGHT WATER 281. LASALLE 2 50-374 84-069 840912/ MISSING GEERAL ELECTRIC BOILING LIGHT E TER 282. LASALLE 2 50-374 84-036 840706/0120 GEERAL ELECTRIC BOILING LIGHT E TER 283. LASALLE 2 50-374 84-037 840718/2108 GDERAL ELECTRIC BOILING LIGHT WATER 284. LASALLE 2 50-374 84-041 840728/2206 GDERAL ELECTRIC BOILING LIGHT E TER 285. LASALLE 2 50-374 84-042 840726/2353 GDERAL ELECTRIC BOILING LIGHT WATER 286. LASALLE 2 50-374 84-044 840801/1451 GENERAL ELECTRIC BOILING LIGHT WATER 287. LASALLE 2 50-374 84-046 840805/0640 GEERAL ELECTRIC BOILING LIGHT WATER 283. LASALLE 2 50-374 84-054 840818/2101 GDERAL ELECTRIC BOILING LIGHT WATER 289. LASALLE 2 50-374 84-054 840818/2151 GEERAL ELECTRIC BOILING LIGHT WATER 290. LASALLE 2 50-374 84-054 840818/2241 GFNERAL ELECTRIC BOILING LIGHT WATER 291. LASALLE 2 50-374 84-051 840823/0944 GDERAL ELECTRIC BOILINGLIGHTWATER 292 LASALLE 2 50-374 84-058 840826/0830 GDERAL ELECTRIC BOILING LIGHT WATER 293. LASALLE 2 50-374 84-056 840827/1145 GENERAL ELECTRIC BOILING LIGHT WATER 294. LASALLE 2 50-374 84-062 840827/2212 GENERAL ELECTRIC BOILING LIGHT WATER 295. LASALLE 2 50-374 84-061 840830/0030 GDERAL ELECTRIC BOILING LIGHT WATER 296. LASALLE 2 50-374 84-061 840830/0515 GDERAL ELECTRIC BOILING LIGHT WATER 297. LASALLE 2 50-374 84-061 840830/1100 GOERAL ELECTRIC BOILING LIGHT WATER 298. LASALLE 2 50-374 84-061 840830/1110 GENERAL ELECTRIC BOILING LIGHT WATER 299. LASALLE 2 50-374 84-061 840330/1410 GENERAL ELECTRIC BOILING LIGHT WATER 300. LASALLE 2 50-374 84-061 840830/1415 GENERAL ELECTRIC BOILING LIGHT WATER 301. LASALLE 2 50-374 84-063 840901/1158 CENERAL ELECTRIC BOILING LICHT E TER 302. LASALLE 2 50-374 84-066 840902/1022 GENERAL ELECTRIC BOILING LIGHT WATER 303. LASALLE 2 50-374 84-057 840906/1800 CENERAL ELECTRIC BOILING LIGHT WATER 304. LASALLE 2 50-374 84-064 840907/0325 GEERAL ELECTRIC BOILING LIGHT WATER 305. LASALLE 2 50-374 84-069 840912/0852 GDERAL ELECTRIC BOILING LIGHT WATER 306. LASALLE 2 50-374 84-065 840913/1557 ODERAL ELECTRIC BOILING LIGHT WATER 56
307[ LASALLE 2 50-374 84-067 840918/1132 GEERAL ELECTRIC BOILING LICHT WATER
- 308, LASALLE 2 50-374 84 072 841029/1952 GEERAL ELECTRIC BOILING LICMT WATER 309. LASALLE 2 50-374 84-075 841112/1010 GCERAL ELECTRIC BOILING LIGHT WATER 310. LASALLE 2 50-374.84-073 841112/1340 GENERAL ELECTRIC BOILING LIGHT WATER 311. LASALLE 2 50-374 84-073 841112/1501 GEERAL ELECTRIC BOILIts LIGHT WATER 312. LASALLE 2 50-374 84-073 841112/2355 GEERAL ELECTRIC BOILING LIGHT WATER 313. LASALLE 2 50-374 84-077 841115/1419 GEERAL ELECTRIC BOILING LIGHT WATER 314. LASALLE 2 50-374 84-077 841116/0844 GENEPA ELECTRIC BOILING LIGHT WATER 315. LASALLE 2 50-374 84-074 841116/0859 OEERAL ELECTRIC BOILING LIGHT WATER 316. LASALLE 2 50-374 84-077 841116/1128 OENERAL ELECTRIC BOILING LIGHT WATER 317. LASALLE 2 50-374 84-078 841117/1244 GENERAL ELECTRIC BOILING LIGHT WATER 318. LASALLE 2 50-374 84-079 841121/0158 GEERAL ELECTRIC BOILING LIGHT WATER 319. LASALLE 2 50-374 84-080 841121/0443 GEERAL ELECTRIC BOILING LIGHT WATER 320. LASALLE 2 50-374 84-081 . 841127/1506 GEERAL ELECTRIC BOILING LIGHT WATER 331. LASALLE 2 50-374 84-083 841208/1423 GEERAL ELECTRIC BOILING LIGHT WATER 322. LASALLE 2 50-374 84-084 841214/1045 GEERAL ELECTRIC BOILING LIGHT WATER 323. LASALLE 2 50-374 84-089 841215/0216 GEERAL ELECTRIC BOILING LIGHT WATER 324. LASALLE 2 50-374 84-090 841216/1014 GEERAL ELECTRIC BOILING LIGHT WATER 335. LASALLE 2 50-374 84-091 841219/1430 GEERAL ELECTRIC MILING LIGHT WATER 326. LASALLE 2 50-374,84-093 841220/0325 GEERAL ELECTRIC BOILING LIGHT WATER 327. LASALLE 2 50-374 84-092 841220/0839 GEERAL ELECTRIC BOILING LIGHT WATER 328. LASALLE 2 50-374 84-087 841224/0437 GEERAL ELECTRIC BOILING LIGHT WATER 339. LASALLE 2 50-374 84-088 841228/1746 GEERAL ELECTRIC BOILING LIGHT WATER 330. LIERICK 1 50-352 84-006 841113/1300 GEERAL ELECTRIC BOILING LIGHT WATER 331. LIERICK 1 50-352 84-007 841114/1251 GENERAL ELECTRIC BOILING LIGHT WATER 332. LIERICK 1 50-352 04-008 841115/0300 GENERAL ELECTRIC BOILING LIGHT WATER 333. LIMERICK 1 50-352 84-021 841115/2157 GEERAL ELECTRIC BOILING LIGHT WATER 334. LIERICK 1 50-352 84-011 841118/0640 GENERAL ELECTRIC BOILING LIGHT WATER 335. LIMERICK 1 50-352 84-010 841118/0945 GENERAL ELECTRIC BOILING LIGHT WATER 336. LIERICK 1 50-352 84-014 841121/2225 GEERAL ELECTRIC BOILING LIGHT WATER 337. LIERICK 1 50-352 84-020 841123/1035 GEERAL ELECTRIC BOILING LIGHT WATER 338. LIERICK 1 50-352 84-019 841126/0323 GENEFA ELECTRIC BOILING LIGHT WATER 339. LIERICK 1 50-352 84-015 841126/%50 GENERAL ELECTRIC BOILING LIGHT WATER 340. LIMERICK 1 50-352 84-015 841126/0752 GENERAL ELECTRIC BOILING LIGHT WATER 341. LIERICK 1 50-352 84-024 841205/0800 OENERAL ELECTRIC BOILING LIGHT WATER 342. LIERICK 1 50-352 84-028 841209/0710 GEERAL ELECTRIC BOILING LIGHT WATER 343. LIERICK 1 50-352 84-030 841210/2120 GEERAL ELECTRIC BOILING LIGHT WATER 344. LIMERICK 1 50-352 84-031 841211/0825 GENERAL ELECTRIC BOILING LIGHT WATER 345. LIMERICK 1 50-352 84-032 841211/1540 GEERAL ELECTRIC BOILING LIGHT WATER 346. LIMERICK 1 50-352 84-033 841211/2115 GENERAL ELECTRIC BOILING LIGHT WATER 347. LIERICK 1 50-352 84-034 841212/0520 CEERAL ELECTRIC BOILING LIGHT WATER 348. LIERICK 1 50-352 84-012 841215/1405 GENERAL ELECTRIC BOILING LIGHT WATER 347. LIERICK 1 50-352 84-026 841216/0135 GENERAL ELECTRIC BOILING LIGHT WATER 350. LIMERICK 1 50-352 84-035 841216/1113 GENERAL. ELECTRIC BOILING LIGHT WATER 351. LIERICK 1 50-352 84-036 841217/0515 CENERAL ELECTRIC BOILING LIGHT ETER 352. LIMERICK 1 50-352 84-029 841220/0521 GENERAL ELECTRIC BOILING LIGHT WATER 353. LIERICK 1 50-352 84-039 841221/0252 GEEPA ELECTRIC BOILING LIGHT WATER 334. LIERICK 1 50-352 84-040 841221/0442 GENERAL ELECTRIC BOILING LIGHT WATER 355. LIERICK 1 50-352 84-041 841222/1243 CENERAL ELECTRIC BOILING LIGHT WATER 356. LIMERICK 1 50-352 84-045 841230/0627 GENEFA ELECTRIC BOILING LIGHT WATER 357. LIMERICK 1 50-352 G4-046 841230/1014 GENERAL ELECTRIC E0! LING LIGHT WATER 353. f00VIRE 1 50-369 84-024 840821/2148 WESTIEH0VSE PRESSURIZED LIGHT E TER 359. MCOUIRE 2 50-370 84-015 840703/1545 WEST!EHOU9E PRESSURIZED LIGHT WATER 360. MCOUIRE 2 50-370 84-018 840819/1626 WESTIEHOUSE PRESSURIZED LIGHT WATER 361. MCOUIRE 2 50-370 84-028 841113/0012 WESTINGOUSE PRESSLRIZED LIGHT WATER 363. MILLSTONE 2 50-336 84-012 841128/ MISSING COMBUSTION ENGIfEERING PRESSURIZED LIGHT ETER 363. f0NT! CELLO 50-263 84-025 840715/1234 OENERAL ELECTRIC BOILING LIGHT ETER 364. MONTICELLO 50-263 84-026 840710/1530 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 365. MONTICELLO 50-263 84-027 840912/0821 GEERAL ELECTRIC BOILING LIGHT ETER 366. MONTICELLO 50-263 84-023 840914/1515 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 367. f0NTICELLO 50-263 84-029 840915/1835 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 368. MONTICELLO 50-263 84-029 840915/1933 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 369. f0NTICELLO 50-263 84-030 841009/1800 COMBU$il0N ENGIEERING PRESSLRIZED LIGHT WATER 57
370. MONTICELLO 50-263 84-031 841016/0001 COMBUSTION ENGIEERING PRES 9AIZED LIGHT WATER 371s MONTICELLO 50-263 84-033 841127/2137 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 372. MONTICELLO 50-263 84-034 841207/0809 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 373. NIE MILE PT. 50-220 84-016 841001/1759 OEERAL ELECTRIC BOIL M LIGHT WATER 374. NORTH ANNA 1 50-338 84-019 841114/0640 ESTINGHOUSE PRESSURIZED LIGHT ETER 375. NORTH ANNA 2 50-339 84-009 841025/ MISSING ESTINCNCUSE PRESSURIZED LIGHT WATER 376. NGRTH ANNA 2 50-339 84-010 841101/1128 WESTINGHOUSE PRESSURIZED LICHT WATER 377. OYSTER CREEK 50-219 84-020 840910/ MISSING GEERAL ELECTRIC ' BOILING LIGHT WATER 378. 0YSTER CREEK 50-219 84-021 840925/2020 GENERAL ELECTRIC BOILING LIGHT WATER 379. 0YSTER CREEK 50-219 84-025 841029/0203 GENERAL ELECTRIC BOILING LIGHT WATER 380. PALISADES 50-255 84-009 840704/0940 COMBUSTION ENGINEERING PRESSlRIZED LIGHT WATER 381. PN.!SADES 50-255 84-011 840719/2242 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 382. PALISADES 50-255 84-015 840004/1355 COMBUSTION ENGINEERING PRESSlRIZED LIGHT WATER 383. PEACH BOTTOM 3 50-278 84-010 840816/0341 GEERAL ELECTRIC BOILING LIGHT WATER ,
4 84. PEACH BOTTOM 3 50-278 84-011 840821/1401 GEERAL ELECTRIC BOILING LICHT WATER
'385. PEACH BOTTOM 3 50-278 84-014 841114/1705 GEERAL ELECTRIC BOILING LIGHT WATER 386. PILGRIM 1 50-293 84-011 840828/1005 CEERAL ELECTRIC BOILING LIGHT WATER 387. PILGRIM 1 50-293 84-012 840920/1529 GEERAL ELECTRIC BOILING LIGHT WATER 388. PILORIM 1 50-293 84-015 840929/ MISSING GEERAL ELECTRIC BOILING LIGHT WATER 389. P!LGRIM 1 50-293 84-016 841207/ MISSING GENERAL ELECTRIC BOILING LIGHT WATER 390. PILORIM 1 50-293 84-017 841219/1358 OEERAL ELECTRIC BOILING LIGHT ETER 391. PILORIM 1 50-293 84-019 841225/1905 GENERAL ELECTRIC BOILING LIGHT WATER 392. PILGRIM 1 50-293 84420 841225/1905 GENERAL ELECTRIC BOILING LIGHT WATER 393. PRAIRIE ISLAND 1 50-282 84-004 840718/0934 WESTINGHOUSE PRESSURIZED LIGHT WATER 394. PRAIRIE ISLAND 1 50-232 84-007 840905/2300 ESTINGHOUSE PRESSURIZED LIGHT WATER 395. PRAIRIE ISLAND 1 50-282 84-009 841002/1646 ESTIMUSE PRESSURIZED LICHT WATER 396. PT. BEACH 2 50-301 84-005 841022/1547 WESTINGHOUSE PRESSAIZED LIGHT WATER 397. PT. BEACH 2 50-301 84-006 841023/1057 ESTINGH)USE PRESSURIZED LI0hi WATER 398. PT. BEACH 2 50-301 84-007 841100/0130 ESTINGHOUSE PRESSURIZED LIGHT WATER 3M. QUAD CITIES 1 50-254 84-012 840002/0845 GEERAL ELECTRIC BOILING LIGHT WATER 400. QUAD CITIES 1 50-254 84-013 840808/22 % GEERAL ELECTRIC BOILING LIGHT WATER 401. QUAD CITIES 1 50-254 84-016 840828/1352 GEERAL ELECTRIC BOILING LICHT WATER 402. QUAD CITIES 1 50-254 84-018 840922/2350 CEERAL ELECTRIC BOILING LIGHT WATER 403. QUAD CITIES 1 50-254 84-018 840924/1030 GEERAL ELECTRIC BOIL M LIGHT WATER 404. QUAD CITIES 2 50-265 84-009 840805/1044> GENERAL ELECTRIC BOILING LIGHT WATER 405. QUAD CITIES 2 50-265 84-010 841025/0546 GENERAL ELECTRIC BOILING LIGHT WATER 406. QUAD CITIES 2 50-265 84-011 841130/1250 GENEFA. ELECTRIC BOILING LIGHT ETER 407. QUAD CITIES 2 50-265 84-012 841201/0925 GEGL ELECTRIC BOILING LIGHT WATER 408. ROBINSON 2 50-261 84-010 841107/ MISSING ESTINGHOLSE PRESSURIZED LIGHT WATER 409. SALEM i 50-272 84-018 840713/1557 WESTINGHOUSE PRES 9AIZED LICHT WATER 410. SALEM 1 50-272 84-024 841020/2300 WESTINGHOUSE PRESSURIZED LIGHT WATER 411. SALEM 2 50-311 84-018 840725/1320 ESTINGH0lCE PRESSURIZED LIGHT WATER 412. SAN ONOFRE 1 50-206 84-015 841116/1134 WESTINGHOUSE PRESSURIZED LIGHT WATER 413. SAN ONOFRE 2, 50-361 84-042 MISSING / MISSING COMBUSTION ENGINEERING PRESSURIIED LIGHT WATER 414. SAN ONOFRE 2 50-361 84-037 840703/0522 COMBUSTION ENGINEERING PRESSURIZED LIGkT WATER 415. SAN ONOFRE 2 50-361 84-037 840705/1630 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 416. SAN ONOFRE 2 50-361 84-037 840705/1637 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 417. SAN ONOFRE 2 50-361 04-037 840705/1740 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 418. SAN ONOFRE 2 50-361 84-037 840707/1320 COMBUSTION ENGINEERING PRESSURIZED LIGHT ETER 419. SAN ON0FRE 2 50-361 84-037 840707/1332 COM9ETION ENGINEERING PRESSURIZED LIGHT E TER 420. SAN ONOFRE 2 50-351 84-037 840707/1606 COMBUSTION ENGINEERING PRESSURIZED LIGHT E TER 421. SAN ONOFRE 2 50-361 84-038 840708/1039 COMBl5 TION ENGINEERING PRES 9A! ZED LICHT WATER 422. SAN ONOFRE 2 50-361 84-038 840708/1043 COMBETION ENGINEERING PRESSA! ZED LIGHT WATER 423. SAN ON0FRE 2 50-361 84-037 840708/1107 '
COMBETION ENGINEER M PRES 9RIZED LICHT WATER 424. SAN ONCFRE 2 50-361 84-037 840708/1236 COMHSTION ENGINEER M PRESSURIZED LIGHT E TER ;
425. SAN ONGFRE 2 50-361 84-037 840709/1122 CCMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 426. SAN CNOFRE 2 50-361 84-037 840709/1250 COMBUSTION ENGINEERING PRESSURIZED LICHT WATER 427. SAN ONOFRE 2 50-361 84-040 840723/1335 COMBUSTION ENGIEERING PRESSA! ZED LIGHT WATER l 428. SAN ONCFRE 2 50-361 84-038 840723/1507 '
COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 429. SAN ONOFRE 2 50-361 84-038 840726/0053 COMBUSTION ENGINEER M PRESSURIZED LIGHT WATER 430. SAN ONOFRE 2 50-361 84-042 840730/0943 COM9)STION ENGIEERING PFESSW IZED LIGHT WATER 431. SAN ONOFRE 2 50-361 84-042 840802/0736 CUMBUSTICN ENGINEERING PRESSURIZED LIGHT ETER 432. SAN ONOFRE 2 50-361 84-042 840803/ MISSING COMBUSTION ENGINEERING PRESSURIZED LIGHT ETER 58 __ _ __ ___ __ _
433.* SM ONOFRE 2 50-361 84-042 840003/0020 00t9USTION ENGIEERING PRESSURIZED LIGHT WATER
, 434: SM ONOFRE 2 50-361 84-042 840003/0120 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER-435. SM ONOFRE 2 50-361 84-044 840803/1010 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 436. SAN ONOFRE 2 50-541 84-042 840803/2125 COMBUSTION ENGINEERING _ PRESSURIZED LIGHT WATER 437. SM ON0FRE 2 50-361 84-042 040804/ MISSING COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 438. SAN ON0FRE 2 50-361 84-042 840808/0916 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 439. SAN ON0FRE 2 50-361 84-043 840808/1710 COMBUSTION ENGIEERIE PRESSLRIZED LIGHT WATER 440. SAN ONOFRE 2 50-361 84-047 840811/1141 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 441. SM ONOFRE 2 50-361 64-047 840811/1144 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 442. SAN ON0FRE 2 50-361 84-047 840811/1302 COMBUSTION ENGINEERING PRESSLRIZED LIGHT ETER 443. SM ONOFRE 2 50-361 84-047 840811/2242 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 444. SAN ON0FRE 2 50-361 84442 840823/2121 COMBUSTION ENGIEERING PRESSLRIZED LIGHT WATER 443. SM ONOFRE 2 50-361 84-042 840823/2211 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 446. SAN ON0FPI 2 50-361 84-049 840824/1445 COP 9USTION ENGIEERING PRESSURIZED LIGHT WATER 447. SAN OEFRE 2 50-361 61-052 840903/0142 COMBUSTION ENGIEERING PRESSLRIZED LIGHT WATER
'448. SAN ONOFRE 2 50-361 84-052 340906/0920 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 449. SAN ONOFPI 2 50-361 84-052 840906/1100 COMBUSTION ENGIEERIE PRESSURIZED LIGHT ETER 450. SAN ONOFRE 2 50-361 E4-052 840906/1130 COMBUSTION ENGIEERING PRESSURIZED LIGHT ETER 431. SM ONOFRE 2 50-361- E4-052 840911/0718 CmMSTinM ENGIEERING PRESSURIZED LIGHT WATER 452. SM ONOFRE 2 50-361 84-053 840919/2218 COMBUSTION ENGIEERING PRESSLRIZED LIGHT WATER 433. SAN ONOFRE 2 50-361 84-055 840928/1905 COMBUSTION ENGIEERING PRESSE!IED LIGHT WATER 434. SM ONOFRE 2 50-361 84-056 841002/1812 COMBUSTION ENGINEERIE PRES 9EIZED LIGHT WATER 455. SM OEFRE 2 50-361 84-057 841003/0025 COMBUSTION ENGIEERING PRESSURIZED LIGHT E TER 436. SM ONOFFI 2 50-361 84-061 841022/0515 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 437. SM ONOFFE 2 50-361 84-061 841022/0555 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 433. SAN ONOFRE 2 50-361 84-062 841023/0630 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 459. SAN ONOFRE 2 50-361 84-055 841024/0456 COMBUSTION ENGIEERING PRES 9AIZED LIGHT WATER 460. SAN ONOFRE 2 50-361 84-063 841024/1355 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 461. SM ONOFFE 2. 50-361 84-055 841025/0505 COMBUSTICN ENGIEERING PRESSURIZED LIGHT WATER 462. SAN ONOFRE 2 50-361 84-064 841030/1505 COMBUSTION ENGIE ERING PRESSLRIZED LIGHT WATER 463. SAN ON0FRE 2 50-361 84-069 841109/1536 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 464. SAN ONCFRE 2 50-361 84465 841101/0657 COMBUSTION ENGINEERING PRESSLRIZED LIGHT WATER 463. SM ONOFRE 2 50-361 84-068 841102/1557 COMBUSTIONENGINEERING PRESSJRIZED LIGHT WATER 466. SAN 0EFFI 2 50-361 84-065 841103/1853 COMBUSTION ENGINEERING RESSURIZED LIGHT WATER 467. SM ON0FRE 2 50-361 84-061 841107/1120 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 468. SAN ONOFRE 2 50-361 84-061 841108/0414 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 469. SAN ONOFRE 2 50-361 84-065 841108/1102 CCMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 470. SAN ONOFRE 2 50-361 84-065 841110/1557 COMBUSTION ENGINEERING PRESSURIZED LIGHT ETER 471. SAN ONUFRE 2 50-361 84-069 841113/ MIS $!NG COMBUSTICN ENGIEERING PRESSLRIZED LIGHT WATER 412. SM ONOFRE 2 50-361 84-065 841113/1440 00MBUSTION ENGINEERING PRESSURIZED LIGHT WATER 473. SM ONOFRE 2 50-361 84-069 841113/1712 COMBUSTION ENGIEERING PRESSA! ZED LIGHT WATER 474. SAN ONCFRE 2 50-361 84-071 841120/0138 COMBJSTION ENGIEERIPG PRESSURIZED LIGHT WATER 475. SAN ONOFRE 2 50-361 84-071 841121/0320 COMBUSTION ENGIEERING mESSLRIZED LIGHT WATER 476. SAN ONOFRE 2 50-361 84-073 ' 841130/1045 COMBUSTION ENGIEERING PRES 3)RIZED LIGHT WATER 477. SAN OEFRE 2 50-361 84-074 841203/0947 COMBUSTION ENGIEERING PRESSLRIZED LIGHT WATER 473. SAN ONCFRE 2 50-361 84-077 841210/1115 COMBUSTION ENGIEERING PRESSLRIZED LIGHT WATER 479 SM ONnFRE 2 50-361 84-080 841219/0745 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 480. SAN ONOFRE 2 50-361 84-076 841222/2028 COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 481. SM ONOFRE 2 50-361 84-081 841223/1245 COMBUSTION ENGINEERING PRES 9AIZED LIGHT WATER 482. SAN ONOFRE 2 50-361 84-076 841227/1444 COMBUSTIGN ENGINEERING PRESSURIZED LIGHT WATER 483. SAN ON0FRE 3 50-362 84-030 840727/1758 CON 9JSTICN ENGINEERING PRESSURIZED LICHT ETER 484. SAN CNOFRE 3 50-342 84-031 840803/1845 CCNBUSTION ENGINEERIO PRESSA! ZED LIGHT WATER 485. SAN ONOFRE 3 50-362 84-041 841126/0354 COMBUSTICN ENGIEERING PRESSURIZED LIGHT E TER 486. SEQUOYAH 1 50-327 84-044 840705/1907 WESTINGHOUSE PRESSURIZED LIGHT WATER 487. SEQUOYAH 1 50-327 84-047 840717/0720 WESTINGHOUSE PRESSURIZED LIGHT WATER 488. SEQUOYM 1 50-327 84-050 840807/0728 WE5TINGHOUSE PRESSURIZED LIGHT WATER 489 SEQU0)AH 1 50-327 84-056 840330/0818 WESTINGKUSE PRESSLRIZED LIGHT WATER 4?O. SEOUOYAH 1 50-327 84-053 840917/0109 WESTINGHOUSE PRES 9AIZED LIGHT WATER 491. SEQUOYAH I 50-327 84-062 640918/0730 WESTINGHOUSE FRESRRIZED LIGHT WATER 492. SEQUOYAH I 50-327 84-060 840921/1906 ESTINGHOLCE PFISSLRIZED LICHT WATER 493. SEQUOYAH 1 50-327 84-060 840923/1115 WESTINGHOUSE PRESSURIZED LIGHT ETER 494. SEQUOYAH 1 50-327 84-060 840924/1730 WESTINGHOUSE PRES $URIZED LIGHT WATER 495. SEQUQYAH 1 50-327 84-060 840928/0039 WESTINGHOLEE PRESSLRIZED LIGHT WATER
496* SEQUOYM i 50-327 84-060 840928/0228 WESTINGHOUSE PRESSWIZEDLIGHTWATER
. 497, SEQUDYAH 1 50-327 84-060 840929/2205 WESTINGHOUSE PRESSLE! ZED LIGHT WATER 498, 50-327 SEQUOYAH 1 84-062 840929/2310 ESTINGHOUSE PRESSLRIZED LIGHT WATER 499. SEQUOYAH I 50-327 84-060 840930/0114 WESTINGHOUCE PRESSURIIED LIGHT WATER 500. SEQUOYAH 1 50-327 84-065 841009/0307 ESTINGHOUSE PRESSWIZED LIGHT ETER 501. SEQUOYAH 1 50-327 84-065 841009/0340 ESTINGHOUSE PRESSLRIZED LIGHT WATER 502. SEQUOYAH 1 50-327 84-066 841009/1600 ESTINGHOUSE PRESSLRIZED LIGHT WATER 503. SEQUOYAH 1 50-327 84-068 841104/1228 WESTINGHOUSE PRESSURIZED LIGHT WATER 504. SEQUOYAH 2 50-328 84-011 840713/0124 WESTINGHOUSE PRESSURIZED LIGHT WATER 505. SEQUOYAH 2 50-328 84-011 840714/0744 ESTINGHOUSE PRESSWIZED LIGHT WATER 506. SEQUOYAH 2 50-328 84-011 840715/0158 WESTINGHOUSE PRESSlRIIED LIGHT WATER 507. SEQUOYAH 2 50-328 84-013 840820/1203 ESTINGHOUSE PRESSW IZED LIGHT WATER 500. SEQUOYAH 2 50-328 84-020 841216/0826 ESTINGHOUSE PRESSLRIZED LIGHT WATER 509. ST. LUCIE 1 50-335 84-000 840828/ MISSING COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 610. ST. UJCIE 2 50-389 84-005 840830/ MISSING COMEUSTION ENGINEERING PRESSURIZED LIGHT WATER .
'S11. ST. LLCIE 2 50-389 84-007 841024/2255 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 512. ST. LUCIE 2 50-389 84-009 841104/0549 COMBUSTION ENGIEERING PRESSlRIZED LIGHT WATER 513. ST. LUCIE 2 50-389 84-012 841119/ MISSING COMBUSTION ENGINEERING PRESSURIZED LIGHT WATER 514. ST. LUCIE 2 50-389 84-011 841121/0927 COMBUSTION ENGIEERING PRESSURIZED LIGHT WATER 515. ST. LUCIE 2 50-389 84-014 841129/0450 COMBUSTION ENGIEERIE PRESSlRIZED LIGHT WATER 516. ST. LUCIE 2 50-389 84-016 841219/ MISSING COMBUSTION ENGIEERIE PRESSURIZED LIGHT WATER 517. SUMMER 50-395 84-046 841106/1750 WESTINGHOUSE PRESSLRIZED LIGHT WATER 518. SLRRY I 50-280 84-023 841113/1355 ESTINGHOUSE PRESSLRIZED LICMT WATER 519. SURRY 1 50-290 84-024 841116/1436 WESTINGHOUSE PRESSURIZED LIGHT WATER
$?0. SURRY 2 50-281 84-014 840321/1644 WESTINGHOUSE PRESSURIZED LIGHT WATER 521. SUSQUEHAMA 1 50-387 84-029 840703/1412 GENERAL ELECTRIC B0! LING LIGHT WATER 522. SUSQUEHANNA 1 50-387 84-033 840716/18 % GENERAL ELECTRIC BOILING LIGHT WATER 523. SUSQlEHAWA 1 50-387 84-036 840724/1541 GEERAL ELECTRIC BOILING LIGHT WATER 324. SUSQlEHANNA 1 50-387 84-037 840803/0635 GEERAL ELECTRIC BOILING LIGHT WATER 525. SUSQUEHAWA 1 50-387 84-037 840803/0639 GEERAL ELECTRIC BOILING LICHT WATER 526. SUSQEHANNA 1 50-387 84-043 841006/1654 GEERAL ELECTRIC BOILING LIGHT WATER 527. SUSQEHAMA 1 50-387 84-047 841102/1300 CEERAL ELECTRIC BOILING LIGHT WATER 328. SUSQlEHANNA 2 50-388 84-0!! 840705/2040 GEERAL ELECTRIC BOILING LIGHT WATER 529. SUSQUEHAWA 2 50-388 84-011 840706/1929 OENERAL ELECTRIC BOILING LIGHT WATER
~
530. SUSQUEHANNA 2 50-388 84-0!! 840706/2122 GENERAL ELECTRIC BOILING LIGHT WATER 531. SUSOUEHAWA 2 50-388 84-011 840706/2305 GEERAL ELECTRIC BOILING LIGHT WATER 532. SUSOEHANNA 2 50-388 84-014 840723/1759 GENERAL ELECTRIC BOILING LIGHT E TER 533. SUSQUEHANNA 2 50-388 84-014 840723/2117 GEERAL ELECTRIC BOILING LIGHT E TER-534. SUSQUEHANNA 2 50-388 84-013 840726/0137 GENERAL ELECTRIC BOILING LIGHT WATER 535. SUSQUEHANNA 2 50-338 84-015 840802/1840 CENERAL ELECTRIC BOILING LIGHT WATER 536. SUSOUEHANNA 2 50-388 84-020 840929/1400 GENERAL ELECTRIC BOILING LIGHT WATER 537. SUSQUEHANNA 2 50-388 84-025 841031/1815 CENERAL ELECTRIC BOILING LIGHT WATER 338. TROJAN 50-344 84-016 840920/CG18 WESTINCHOUSE FRESSLRIZED LICHT ETER 539 TR0JAN 50-344 84-019 841012/1232 WESTINCHOUSE PRESSLRIZED LIGHT WATER 540. TURVEY PT. 4 50-251 84-015 840716/1400 WESTINGHOUSE PRESSlRIZED LIGHT WATER 541. TURKEY PT. 4 50-251 84-025 841124/0802 EST!nrMOUSE PRESSLRIZED LIGHT WATER 542. TlRKEY PT. 4 50-251 84-026 841124/1310 WESTINGHOUSE PRESSLRIZED LIGHT ETER 543. VERMUNT YANKEE 50-271 84-015 840724/1254 GENERAL ELECTRIC B0! LIE LIGHT ETER 544. VERMONT YAEEE 50-271 84-023 841126/1255 CENERAL ELECTRIC BOILING LIGHT WATER 54L WATERFCGD 3 50-382 84-001 841225/1820 COMBU5 TION EN0!NEERING PRESSURIZED LIGHT EIER 546. WPPSS 2 50-397 84-072 840705/1700 GENERAL ELECTRIC BOILING LIGHT WATER 547. WPPSS 2 . 50-397 84-072 840706/0050 GEtERAL ELECTRIC BOILING LIGHT WATER 543. WPPSS 2 50-397 84-072 840706/0216 GENERAL ELECTRIC B0! LING LIGHT WATER 549. WPPSS 2 50-397 84-073 840708/ MISSING GENERAL ELECTRIC 10! LING LIGHT WATER 550. WPPSS 2 50-397 84-071 840716/1400 CENERAL ELECTRIC BOILING LIGHT WATER 551. WPPSS 2 50-397 84-077 840720/2323 CENERAL ELECTRIC BOILING LIGHT WATER 552. WFPSS 2 50-397 84-077 840721/1145 CENERAL ELECTRIC BOILING LIGHT WATER 533. WFPSS 2 50-397 84-072 840731/ MIS $1NG CEERAL ELECTRIC B0! LING LICHT WATER 554. WPPSS 2 50-397 84-078 840001/0045 GEERAL ELECTRIC - BOILING LIGHT WATER 555. WFPSS 2 50-397 84-078 840801/1818 GEERAL ELECTRIC 60! LING LIGHT WATER 556. *WPPSS 2 50-397 84-082 840802/0115 GEERAL ELECTRIC BOILING LIGHT WATER 557. WFPSS 2 50-397 84-078 840807/0755 GENERAL ELECTRIC BOILING LIGHT WATER 558. WPPSS 2 50-397 84-072 840808/ MISSING GENERAL ELECTRIC BOILING LIGHT WATER 60
559/ WPSS 2 50-397 84-072 840800/ MISSING GDEML ELECTRIC BOILING LIGHT WATER
, 560., WPSS 2 50-397 84-078 840800/0040 CENEML ELECTRIC BOILING LIGHT WATER 561. WPPSS 2 50-?97 84-072 840810/ MISSING GENERAL ELECTRIC BOILING LIGHT WATER 562. WPSS 2 50-397 84-033 840814/1455 GEEML ELECTRIC BOILING LIGHT WATER 563. WPSS 2 50-397 84-081 840816/1030 GEERAL ELECTRIC BOILING LIGHT WATER 564. WPPSS 2 50-397 84-081 840818/0315 GEERAL ELECTRIC BOILING LIGHT WATER 565. WPPSS 2 50-397 84-092 840821/1838 GEEML ELECTRIC B0ILING LIGHT WATER 566. WPPSS 2 50-397 84-082 840823/ MISSING OENERAL ELECTRIC BOILING LIGHT WATER 567. WPPSS 2 50-397 84-091 840823/ MIS $1NG GENERAL ELECTRIC BOILING LIGHT ETER 568. WPSS 2 50-397 84-093 840824/0200 GEEML ELECTRIC BOILING LIGHT WATER .
569. WPPSS 2 50-397 84-092 840824/1759 GEERAL ELECTRIC BOILING LIGHT WATER 570. WPSS 2 50-397 84-033 840831/MISSIE GENERAL ELECTRIC BOILING LIGHT WATER 571. WPSS 2 50-397 04-097 840904/0317 GEEML ELECTRIC BOILING LIGHT WATER 572. WPSS 2 50-397 84-098 840904/1855 GEEML ELECTRIC BOILING LIGHT WATER 573. WPSS 2 50-397 84-033 840905/1652 GEERAL ELECTRIC BOILING L10HT WATER 574. WPPSS 2 50-397 84-094 840905/2015 GENERAL ELECTRIC BOILING LIGhi WATER 575. WPPSS 2 50-397 84-098 840910/2203 GEERAL ELECTRIC BOILING LIGHT WATER 576. WPPSS 2 50-397 84-098 840917/1305 GENERAL ELECTRIC BOILING LIOh7 ETER 577. WPPSS 2 50-397 84-072 840918/ MISSING GEERAL ELECTRIC 90! LING LIGHT WATER 578. WPSS 2 50-397 84-072 840918/0200 GENERALELECTRIC BOILING LIGHT WATER 579. WPSS 2 50-397 84-101 840919/ MISSING GEEML ELECTRIC BOILING LIGHT WATER 580. WPPSS 2 50-397 84-105 840924/1001 GENERAL ELECTRIC BOILING LIGHT WATER 581. WPSS 2 50-397 84-105 840924/1010 GENERAL ELECTRIC BOILING LIGHT WATER 582. WPPSS 2 50-397 84-099 840928/ MISSING GENERAL ELECTRIC BOILING LIGHT ETER 583. WPPSS 2 50-397 84-099 840928/ MISSING GEERAL ELECTRIC BOILING LIGHT ETER 504. WPFSS 2 50-397 84-099 840928/1550 GENEPA ELECTRIC BOILING LIGHT WATER 585. WPSS 2 50-397 84-102 840930/0620 GENERAL ELECTRIC BOILING LIGHT ETER 586. WPPSS 2 50-397 84-101 841002/1638 GENERAL ELECTRIC BOILING LIGHT WATER 587. WPPSS 2 50-397 84-082 841004/2121 GEERAL ELECTRIC BOILING LIGHT WATER 588. WPSS 2 50-397 84-107 841008/1215 GENEML ELECTRIC B0! LING LIGHT WATER 589. WPSS 2 50-397 84-119 841110/1820 OEERAL ELECTRIC BOILING LICHT WATER 590. WPPSS 2 50-397 84-118 841113/0640 GEEML ELECTRIC BOILING LIGHT WATER 591. WPPSS 2 50-397 84-117 841116/0452 GENEML ELECTRIC B0! LING LIGHT WATER 592. WPPSS 2 50-397 84-120 841119/1250 GEEML ELECTRIC BOILING LIGHT WATER 593. WPPSS 2 50-397 84-127 841218/0825 CENERAL ELECTRIC - BOILING LIGHT WATER 594. WPPSS 2 50-397 84-123 841224/1300 GENERAL ELECTRIC BOILING LIGHT WATER 595. Y N EE R0WE 50-029 84-012 840712/0805 WESTINGHGJSE PRESSURIZED LIGHT WATER 596. Y N EE RO E 50-029 84-014 840814/2254 ESTINGHOUSE PRESSLRIZED LIGHT WATER 597. YANEE R0WE 50-029 84-014 840814/2310 WESTINGHOUSE PRESSURIZED LIGHT WATER 598. Y W EE R0WE 50-029 84-015 840905/0556 WESTINGHOUSE PRESSURIZED LIGHT WATER SN. YAWEE R0WE 50-029 84-016 840915/0029 WESTINGHOUSE PRESSURIZED LIGHT WATER 600. YAM IE RCME 50-029 84-017 841112/2010 WESTINGHOUSE PRESSURIZED LIGHT WATER 601. IICN 2 50-304 84-030 841210/ MISSING WESTINGHOUSE PRESSURIZED LIGHT WATER 61
Table A.3 Valid (Design Basis) ESF Actuations Docket NSSS Report Event Measured ESF System .
Unit (s) Number Vendor Number Date/ Time Parameter Function
- Reason
- 3. Haddam Neck 213 W 84-014 840824/1325 Loss of Power Power (DG) Loss of Off-Site Power g 4. Indian Point 3 286 W 84-015 841116/1242 Loss of Power Power (DG) Wind / Loss of Off-Site Powirr
- 6. Cook 2 316 W 84-o34 841223/0203 Radiation Isolation (CP) Leaking Bypass Valve
- 13. McGuire 1 369 W 84-024 840821/2148 Loss of Power Power (DG) Loss of Off-site Power Isolation (CV)
= .
Table A.3 Valid (Design Basis) ESF Actuations84-081 841123/0924 Level HPCS Suction Valve Cycling and
- 15. LaSalle 1 373 GE Minor Leakage Transfer 84-087 841222/0000 Level
i 84-011 840716/1750 Loss of Power Power (DG) Stom-Loss of Off-site Power
- 21. Catawba 413 W Bus During Test 841016/1110 Loss of Power Power (DG) Loss of Switchyard Bus
- - m 22. Callaway 483 W 84-052 Isolation (h) Voltage w
] Fluid (AFW) '-
3 a AFW = Auxiliary Feessater CP = Containment Purge CV = Containment Ventilation DG = Diesel Generator M = Multiple RWCU = Reactor Water Cleanup SI = Safety Injection HPCS = High Pressure Core Spray I
a
}
V
= ".
Table A.4
- Valid (Non-Design Basis) ESF Actuations Docket NSSS Report Event Neasured ESF System Unit (s) thaber ,
Vendor shaber Date/ Time Parameter Function
- Reason
- 1. Yankee Rowe 029 W 84-016 840915/0029 Loss of Power
- Power (OG) Loss of Nain Generator >
Field Relay
- 2. Yankee Bowe 029 W 84-017 841112/2010 Loss Of Power Power (OG) Main Generator Rotor Collector Ring Arcing
- 4. Indian Point 2 247 W 84-016 841016/2126 Pressure Fluid (SI) Preseture Opening of Safety Relief Valve
- 5. Dresden 3 249 GE 84-007 840722/ - Pressure Isolation (PCIS) Turbine Bypass Valve i Erratic Operation
- 6. Dresden 3 249 GE 84-020 M1026/0908 Pressure Isolation (PCIS) Camputer Pressure Indication Too Nigh ,
- 8. Turkey Pt 4 251 W 84-026 841124/1310 Level Fluid (AFW) Feedseter Transient g 9. Quad Cities 1 254 GE 84-012 840002/0045 -
R8 Vent System HWAC (SSGT)
Isolation
- 10. Palisades 255 CE 84-015 840004/1355 Loss of Power Power (DG) Safeguards Bus did not fast transfer; blown fuse
- 12. Monticello 263 GE 84-027 840912/0821 Loss of Power Power (DG) Susped Panel Tripped Relay Caused loss of voltage on
, Auxiliary Reserve Transformer e
4-t t
t
~
Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket NSSS Report Event Measured ESF System Unit (s) Ember Vendor Neber Date/ Time Parameter Function
- Reason
- 14. Quad Cities 2 265 GE 84-010 841025/0546 Pressure Fluid (NPCI) Procedure Deficiency in Hot Standby caused reactor pressure to increase
- 15. Diablo Canyon 1 (2) 275 W 84-020 840719/0925 Loss of Power Power (DG) Jarred Relay During Construction
- 16. Diablo Canyon 1 275 W 84-023 840730/1327 Loss of Power Power (DG) Inadvertent Isolation from Offsite Power
Close During Test
- 18. Diablo Canyon 1 275 W 84-030 841124/1616 Temperat re/ Flow Fluid (le) Failure to Reset steam Dump Controller
, 19. Diablo Canyon 1 275 W 84-034 841215/2316 Loss of Power Power (DG) Inadvertent opening of m .
Start , Feeder
- 20. Peach Botton 3 278 GE 84-011 840821/1401 Level Isolation (PCIS) Failure of Feedwater Fluid (HPCI) Control resulted in reactor low level
- 23. Prairie Island 1(2) 282 W 84-007 E400905/2300 Loss of Power Power (DG) Test Procedure Inadequacy t.
_ - _ _ __ __ .--__ -_ -- _ _ . . . - - ~ - - - - - - -
Table A.4 (Cont'd)
- Unit (s) Neber Vendor Number Date/ Time Parameter Function
- Reason
- 24. Prairie Island 1(2) 282 W 84-009 841002/1646 Loss of Power Power (DG) Misunderstanding During Switching
'9 Ft. Calhoun 285 CE 84-023 841124/2000 Radiation ' Isolation (VIAS) Iodine Accumulation on Monitor
- 30. Ft. Calhoun 285 CE 84-025*, 841207/1329 Radiation Isolation (VIAS) Leak in Waste Gas Vent
- 31. Pilgrim 1 293 E 84-011 840828/1005 Loss of Power Power (DG) Leads Separated During Relay Replacement g 32. Pilgris 1 293 E 84-012 840920/1529 Loss of Power Power (DG) Inadvertent Manual Start y During Test
! 33. Pilgria 1 293 E 84-017 841219/1358 Loss of Power Power (DG) Personnel Error After Test - loss of offsite power
- 35. Browns Ferry 3 296 E 84-015 841209/- Loss of Power I Power (DG) Overcurrent Relay Trip After Failure of Breaker 4
}
I J
i
- Table A.4 (Cont'd) ~
Valid (Non-Design Basis) ESF Actuations Docket NSSS Report Event Measured ESF System Unit (s) Number V*ndor Number Date/ Time Parameter Function
- Reason
Summer Heat
- 37. Pt. Beach 2 301 W 84-005 841022/1547 Loss of Power Power (DG) Inadvertent Loss of Off-site Power
- 38. Pt. Beach 2 301 W 84-006 841023/1057 Loss of Power Power (DG) Inadvertent Open Breaker During Relay Replacement
- 39. Pt. Beach 2 301 W 84-007 841108/0130 Loss of P0wer Power (DG) Personnel Error During Inspection -
, of RCP's and reactor trip of 2 RCPs
- 42. Cook 2 316 W 84-020 840005/1414 Reactor Trip Fluid (AFW) Bus Failure due to Blown Fuse E 43. Cook 2 316 W 84-024 8400911/1517 Reactor Trip Multiple (ND) All ESF Systems Operated Satisfactorily in Response to Trip
- 44. Cook 2 316 W 84-025 840912/0733 Reactor Trip Fluid (AFW) SG Level Control Problems
- 45. Cook 2 316 W 84-029 841111/0737 Pressure Partially Stuck Open
, Fluid (CH)
Pressurizer Spray Valve
Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Doctet NSSS Report Event Measured ESF System Unit (s) haber Vendor Number Date/ Time Parameter Function
- Reason
- 47. Calvert Cliffs 2 318 CE 84-008 841003/1948 Level Fluid (AFW) Loss of Feed Pump 48 Hatch 1 321 GE 84-015 840003/2151 Level Isolation (PCSS) Low Level After HVAC (58GT) Reactor Scram g 49. Hatch 1 321 GE 84-010 840820/0907 Temperature Isolation (RWCU) High Ambient Temp.
Due to Hot Weather
- 52. Brunswick 2 324 GE 84-014 841128/0100 Level Isolation (PCIS) Failure of RHR Heat Exchanger Level Control
- 53. 8hanswick 1 325 GE 84-014 840001/1417 Pressure Isolation (PCIS) Manual Operation of Safety Relier Valve
- 54. Brunswick 1(2) 325 GE 84-016 840007/0134 Loss of Power Power (DG); Isola- Faulty Degraded Voltage tion (PCIS); HVAC Relay Devices (C8,SSGT) .
Isolation (PCIS) Controller Inputs
- 56. Brunswick 1 325 . GE 84-027 840930/0920 Temperature Isolation (RCIC, Deflected Steam from PCIS) Steam Leak
- 57. Brunswick 1 325 GE 84-027' 840930/0926 Temperature Isolation (RCIS, Deflec'ted Steam from PCIS) Steam Leak
F l
l Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket N555 Report Event Measured ESF Systee Unit (s) Number Vendor Number Date/ Time Parameter Function
- Reason
- 59. Brunswick 1(2) 325 E 84-031 841107/0816 Fire Detection WAC (CB) Cigarette Smoke
- 60. Brunswick 1(2) 325 GE 84-031 841113/1955 Fire Detection WAC (C8) Cigarette Seoke E 61. Brunswick 1(2) 325 GE 84-030 841207/1100 Fire Detection WAC (CB) Cosiing Funes
- 63. Brunswick 1(2) 325 GE 84-036 841212/1014 haual HVAC (CS) Minute Chlorine Gas Leaks (4. Brunswick 1(2) 325 CE 84-036 841212/1458 Manual HVAC (CB) Minute Chlorine Gas Leaks
- 66. Brunswick 1(2) 325 GE 84-036 841218/2040 Manual HVAC (CS) Minute Chlorine Gas Leaks 67 Brunswick 1(2) 325 GE 84-018 841226/2205 Fire Detection HVAC (C8) Tobacco Smoke
~
G9. Sequoyah 1 327 W 84-060 840929/2205 Radiation High Activity in Isolation (A8)
Spent Fuel Pool
- 70. Sequoyah 1 327 W E4-060 840030/0114 Radiation Isolation (AB) High Activity in Spent Fuel Pool
Table A.4 (Cent'd)
Valid (Non-Design Basis) ESF Actuations Event Neasured ESF System Docket stS55 Report Aeason Vender ur Date/ Time Parameter Function
- unit (s) Ihamber M1009/0307 Badiation Iselation (AB) Centaminated Material
- 71. Segasyan 1 (2) 327 W M-865 .
Next to Monitor Radiation Iselation (AB) Contaminated Noterial
- 72. Segssyah 1 (2) 327 W M-865 M 1009/0340
. Next to Monitor Less of Power Power (BG) Inadvertent opening of
- 73. Segesyah 1 327 W M-066 M1009/1600 of treaker During Surveillance M1216/0826 Pressure Fluid (CN) Operation of SI-Block
- 74. Segasyah 2 328 W M-820 Hand Switches
~
840713/0902 Level Iselation (PCIS) Lew Level After Reacter
- 75. Buane Arnold 331 E M-027 Scram
- WAC (SAGT) 841123/0640 Level Fluid (WCI), Lew Level After Reacter
- 76. Duane Arnold 331 E M-042 Scram (ACIC) Isel. *
(PC15); WAC 3 (SAGT)
Teeperature WAC (SFU) - - Law Iniet Air Tegperature 331 E M-843 M1206/0730
- 77. Suane Arnold .. .
Fluid (NPCI) Less of Feed Pimp en
- 78. Fitzpatrick 333 E M-023 M11M/- Level Lou Section Pressure .
Anstematic Bus Transfer
- M-012 M1018/1435 Less of Power Power (SG)
- 79. Seaver Valley I(2) 334 W Did not aperate Fluid (AFW) SG Feed Pump Lou 336 CE M-012 M1128/- ' Level St. Mi11stene 2 Discharge Pressure 9
9 e
9 i e
. 7 Table A.4 (Cont'd)
Valid (Non-Design Basis) E5F Actuations Docket N555 Report Event Measered ESF System Unit (s) Iksuber Vendor Number . Date/ Time Parameter Function
- Reason
- 82. Trojar. 344 W 84-019 841012/1232 Loss of Power Power (DG) Inadvertent Deener-gization y 83. Davis-Besse 346 84W 84-013 840911/1235 Press 2re Isolation (SFRCS) Difficulty in Balancing Pressure
- 84. Limerick 1 352 GE 84-024 841205/0800 Condenser Isolation (PCIS) Failure to Reset Partial Vacuum Signal During Test
, Radiographic Testing
- 86. San Onofre 2 (3) 361 CE 84-037 840703/0522 Toxic Gas WAC (CR) Overly Conservative Alara Setpoints
Alaris Setpoints 68_ San Onofre 2 (3) 361 CE 84-037 840705/1637 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints
- 89. San Onofre 2 (3) 361 CE 84-037 849705/1740 Toxic Cas WAC (CR) Overly Conservative Alarm Setpoints
- 90. San Onofre 2 (3) 361 CE 84-037 840707/1320 Toxic Gas WAC (CR) Overly Conservative Alarm Setpoints 91 San Onofre 2 (3) 361 CE 84-037 840707/1332 Toxic Gas WAC (CR) Overly Conservative Alarm Setpoints
- 92. San Onofre 2 (3) 361 CE 84-037 840707/1606 Toxic Gas WAC (CR) Overly Conservative Alarm Setpoints
. . _ _ _ _ - . . . - . _ . _ _ _ - _ . . _ _ _ .. - ___ . _ _ _ ~ - - _ = - . _ - . . __ .
i Table A.4 (Cont'd)
Valid (Non-Design 8asts) ESF Actuations s
1 Docket N555 Report Event Neasured ESF System
- Unit (s) Em6er Vendor Number Date/ Time Parameter Function
Alara Setpoints i 94. San Onofre 2 (3) 361 CE 84-037 840708/1236 Toxic Gas WAC (CR) Overly Conservative l Alarm Setpoints l M N
- 95. San Onofre 2 (3) 361 CE 84-037 840709/1122 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints
%. San Onofre 2 (3) 361 CE 84-037 840709/1250 Toxic Gas WAC (CR) Overly Conservative
'{
Alaru Setpoints
1
- Alara Setpoints a
! 13. San Onofre 2 (3) 361 CE 84-042 840002/0736 Toxic Cas WAC (CR) Overly Conservative
! Alare Setpoints i
Alarm Setpoints 100. San Onofre 2 (3) 361 CE 84-042 840003/0120 Toxic Gas WAC (CR) Overly Conservative j Alare Setpoints 101. San Onofre 2 (3) 361 CE 84-042 840803/2125 Toxic Gas WAC (CR) Overly Conservative Alara Setpoints 102. San Onofre 2 (3) 361 . CE 84-G12 840803/- Toxic Gas WAC (CR) Overly Conservative Alara Setpoints 103. San Onofre 2 (3) 361 CE 84-042 840804/- Toxic Gas WAC (CR) Overly Conservative a
Alare Setpoints f
4 f
Table A.4 (Cont'd)
Valid (Mon-Design Basis) ESF Actuations Docket N555 Report Event Measured ESF System Unit (s) humber Vendor Number Date/ Time Parameter Function *
- Reason 104. San Cnofre 2 (3) 361 CE 84-042 8408-/- Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 105. San Onofre 2 (3) 361 CL 84-042 840008/0916 Toxic Gas WAC (CR) Overly Conservative Alars Setpoints U 106. San Onofre 2 (3) 361 CE 84-042 840823/2121 Toxic u s WAC (CR) Overly Conservative Ala m Setpoints 107. San Onofre 2 (3) 361 CE 84-042 840823/2211 Toxic Gas WAC (CR) Overly Conservative Alarm Setpoints 108. San Onofre 2 (3) 361 CE 84-044 840803/1010 Toxic Gas WAC (CR) Funes from Cleaning Solvent ,
109. San Onofre 2 361 CE 84-043 840006/1710 Level Fluid (EFW) Low SG Level Due to Shrink After Reactor Trip '
110. San Onofre 2 (3) 361 CE 84-052 840903/0142 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 111. San Onofre 2 (3) 361 CE 84-052 840906/0920 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 112. 54n Onofre 2 (3) 361 CE 84-052 840906/1100 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 113. San Onofre 2 (3) 361 CE 84-052 840906/1130 Toxic Gas' WAC (CR) Overly Conservative Alare Setpoints 114. San Onofre 2 (3) 361 CE 84-052 840911/0718 Toxic Gas WAC (CR) Overly Conservative .
Alarm $*tpoints O
. -t Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket N555 Report Event Measured ESF System Unit (s) Number Vendor Number Date/ Time Parameter Function
- Reason 115. San Onofre 2 (3) 361 CE 84-055 840928/1905 Toxic Gas W AC (CR) Overly Conservative Alare Setpoints 116. San Onofre 2 (3) 361 CE 84-055 841024/0456 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 5 117. San Onofre 2 (3) 361 CE 84-055 841025/0505 Toxic Gas WAC (CR) Overly Conservative Alaru Setpoints 118. San Onofre 2 (3) 361 CE 84-065 841101/0657 Toxic Gas WAC (CR) Overly Conservative Alarm Setpoints 119. San Onofre 2 (3) 361 CE 84-065 841103/1853 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 120. San Onofre 2 (3) 361 CE 84-065 841108/1102 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 121. San Onofre 2 (3) 361 CE 84-065 841110/1557 Toxic Gas WAC (CR) Overly Conservative Alare Setpoints 122. San Onofre 2 (3) 361 CE 84-065 841113/1440 Toxic Gas WAC (CR) Qverly Conservative Alara Setpoints 123, San Cnofre 2 361 84-069 CE 841109/1536 Radiation Isolation (CP) Radioactive Waste Near Monitor
~
124. San Onofre 2 361 CE 84-069 841113/1712 Radiation Isolation (CP) Radioactive Itees Near Monitor 125. San enofre 2 361 CE 84-069 841113/- Radiation Isolation (CP) .
Radioactive Items Near Monitor
a l
I 4
e i
~a bic A.4 (Cent'd)
Valid (Non-Cesign Basis) ESF Actuations
! Docket NSSS Report Fvent Measured ESF Systee y Unit (s) Number Vendor ' Number Date/ Time Parameter Function
Completely Full i
127. Hatch 2 366 GE 84-021 840921/1701 Level Fluid (HPCI) Low Level After 1 y j (n Isolation (PCIS, Reactor Scraa MSIV) 128. A-iansas 2 368 CE 84-026 841026/1137 Level Fluid (EFW) Low SG Level After l;
i Reactor Trip 129. Ansash ? 368 CE 84-028 84110'/1104 Level Fluid (EFW) Low SG Level Due to Shrink After Reactor Trip 130. McGuire.2 3D W 84-028 84113/0012 Pressure Pressure Surge in Isolation (UNI)
Crossover Line i 131. LaSalle 1 91 Gli 84-045 840715/0511 Flow Filter Not Completely i Isolation (RWCU)
I Filled / Improper Valve .
Position
- 132. LaSalle 1 L'l GE 84-046 840727/2140 Flow Open Filter Drain Valves Isolation (RWCU) 133. LaSalle 1 173 GE 84-046 840727/2150 Flow Open Filter Drain Valves Isolation (RWCU)
A34. LaSalle 1 373 GE 84-046 840727/2000 Flow Open Filter Drain Valves Isolation (RWCU) 135. LaSalle 1 373 GE 84-046 840728/0441 Flow
' Isolation (RWCU) Unknown Reason While 8eing Placed in Service f
b
- _ -_ __ _ _ m . ._ _ . _ . _ . . _ _ _ _ _ .. __
._--_.-.m_ _ _ _ - _ - _ - _ _ _ _ . _ _
. t
=
i 4
Table A.4'(Cont'd)
Valid (Non-Destgr. Basis) ESF Actuations I
Docket NSSS Report Event Measured ESF Systee j Unit (s) Number Vendor Number .
Date/ Time Parameter Function
- Reason 136. LaSalie 1 373 GE 84-047 840807/2137 Flow Isolation (IndCU) Valves Found Out of Position 137. LaSalle 1 373 GE 84-050 840828/0105 Flow .
Isolation (RWCU) Valves Out of Position-
139, taSalle 1 373 04-055 840921/1647 Flow j
GE Isolation (RWCU) Calibration /Setpoints
' Off at less than Design Conditions i 140. LaSalle 1 (2) 373 GE 84-076 841111/1019 Loss of Power HVAC (58GT) Recirc Pump Start l Isolation (PCIS, Caused Voltage Drop j R8V) i 141. L45a11e 1 373 84-082 GE 841124/1044 Flow Isolation (RWCU) Fluid Conditions Differ
, Between Startup/ Rated 142. LaSalle 2 374 GE 84-036 840706/0120 Flow Isolation (RWCU) Leakage Past Valve Seat 143. LaSalle 2 374 2 84-C37 840718/2108 Flore Isolation (RWCU) Damaged Operator;
. Leakage Past Valve 114. LaSalle 2 374 GE 84-041 840728/2206 Flow Isolation (RWCU) Density Olfferences At 3
Other than Rated Conditions i 145. LaSalle 2 314 . GE 84-042 840728/2355 Condenser Vacuum Isolaton (PCIS) Bypass Switches A
, , in " Bypass" j 140. LaSaile 2 374 GE 84-044 840801/1451 Flow Isolation (RWCU) Lifted Relief Valve j , Startup Conditions
- e
,_--,,w- ,-w --
4 Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket NSSS Report Event Measured ESF System Unit (s) Number Vendor Number Date/ Time Parameter Function
- Reason 147. LaSalle 2 374 GE 84-054 840818/2101 Flow Isolation (RWCU) Valve Manipulations 148. LaSalle 2 374 GE 84-054 840818/2151 Flow Isolation (IIWCU) Valve Manipulations 149. LaSalle 2 374 GE 84-054 840818/2241 Fics Isolation (RWCU) Valve Manipulations U 150. LaSalle 2 374 GE 84-058 840826/0830 Temperature Isolation (RWCU) Ventilation Shut Down 151. LaSalle 2 374 GE 84-061 840830/0030 Flow Isolation (RWCU) Density Differences in Start-up 152. LaSalle 2 374 GC 84-061 840830/0515 Flow Isolation (RWCU) Density Differences in Start up 153. LaSalle 2 374 GE 84-061 840830/1100 Flow Isolation (RWCU) Density Differences in Start-up 154. LaSalle 2 374 GE 84-061 840830/1110 Flow Isolation (RWCU) Open Relief Valve 155. LaSalle 2 374 GE 84-061 840830/1410 Flow Isolation (RWCU) Placing Filter on Line 156. LaSalle 2 374 GE 84-061 840830/1415 Flow Open Relief Valve Isolation (RWCU) 157. LaSalle 2 374 GE 84-066 840902/1022 Flow Isolation (RWCU) Inadequate fill and went 158. LaSalle 2 374 . GE 84-057 840906/1800 Flow Isolation (RWCU) Density Differences at Other than Rated Conditions 159. LaSalle 2 374 CE 84-064 840907/0325 Flow Density Transients at Isolation (RWCU)
Shutdown
Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket MSSS Report Event Measured ESF System Unit (s) Number Vendor humber Date/ Time Parameter Function
- Reason 160. LaSalle 2 374 GE 84-069 840912/- Condenser Vaccum Isolation (PCIS) Spurious Opening of Main Steam Stop Valves 161. LaSalle 2 374 GE 84-067 840918/1132 Temperature Isolation (RWCU) Cool Outside Air / Heat Given Off by Pump M 162. LaSalle 2 374 GE 84-073 841112/1340 Temperature Isolation (RWCU) Ventilation Shut Down 16L LaSalle 2 374 GE 84-073 841112/1501 Flow Isolation (RWCU) Shutdown Conditions Different from Rated .
164. LaSalle 2 374 GE 84-073 841112/2355 Flow Isolation (RWCU) Shutdown Conditions Different from Rated 165. LaSalle 2 374 GE 84-077 841115/1419 Pressure HVAC (MI) Primary Containment Chiller Trip and Restart 166. LaSalle 2 374 GE 84-077 841116/0844 Pressure HVAC (MI) Primary Containment Chiller Cycling On and Off 167. LaSalle 2 374 GE,84-077 841116/1128 Pressure HVAC (MI) Primary Containment
. Chiller Cycling On and Off 168. LaSalle 2 374 GE 84-079 841121/0158 Flow Isolation (RWCU) Perturbations from Placing Filter on Line 169. LaSalle 2 374 GE 84-08C 841121/0443 Pressure HVAC (MI) Primary Containment Chiller Trip and Restart 170. LaSalle 2 374 CE 84-081 841127/1506 Pressure HVAC (MI) Ventin2 of Primary Containment
Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket NSSS Re,, ort Event Measured ESF System Unit (s) Number Vendor Number Date/ Time Parameter Function " Reason 171. LaSalle 2 374 GE 84-083 841208/1423 Pressure HVAC (MI) Pressure Differential from Starting Second P.C. Chiller 172. LaSalle 2 374 GE 84-089 841215/0216 Flow Isolation (RWCU) Difference in Conditions Between Rated and Shutdown 173. LaSalle 2 374 GE 84-090 841216/1014 Pressure HVAC (MI) Start of P.C. Vent and Purge and/or PC Chiller 174. LaSalle 2 374 GE $4-091 841219/1430 Pressure HVAC (MI) Increasing Suppression Pool Level 175. LaSalle 2 374 GE 84-092 841220/0839 Pressur'e HVAC (MI) Primary Containment Chiller Trip and Restart 176. LaSalle 2 374 GE 84-093 841220/0325 Flow Isolation (RWCU) Flow Perturbations During Start-up 177. LaSalle 2 374 GE 84 088 841228/1746 Pressure HVAC (MI) Operation of
, Hyarogen Recombiner 178. Susquehanna 1 (2) 387 GE 84-029 840703/1412 Level Fluid (HPCI), HVAC Low Reactor Level (58GTS); After Reactor Scram 179. Susquehanna 1 Isolation (MS) 387 . GE 84-033 840716/180 Condenser Vacuum Isolati m (MS) Inadvertent Opening of Vacuum Breaker Valve 180. Susquehanna 1 387 GE 84-047 841102/1300 Flow Surge in Flow Due to Isolation (RWCU)
Excessive Air in Filter
Table A.4 (Cont'd) ~
Valid (Non-Design Basis) ESF Actuations Docket " NSSS Report Event Measured ESF System Unit (s) Number Vendor Number Date/ Time Parameter function
- Reason 181. Susquehanna 2 388 GE 84-014 i 840723/1759 Temperature Isolation (RWCU) Problems with Reactor Building Chillar
- 182. Susquehanna 2 388 GE 84-014 840723/2117 Temperature Isolation (RWCU) Problems with Reactor Building Chiller 183. Susquehanna 2 388 GE 84-013 840726/0137 Loss of Power Isolation (PCIS, Loss of Off site MS) Power Startup Test 184. St. Lucie 2 389 CE 84-012 ' 841119/- Loss of Power Power (DG) Reduced Voltage when Condensate Pump Seized 185. St. Lucie 2 389 CE 84-011 841121/0927 Reactor Trip
- Fluid (AFW) Loss of Load Generator Exciter Field Failure 186. St. Lucie 2 389 CE 84-016 841219/- Loss of Power Power (DG) Aux. Transformer Feeder Breaker Did Not Open 187. Summer 1 395 W 84-046 841106/1750 g Loss of Power Power (DG) Undervoltage Due to Personnel Error 188. WPPSS 2 397 GE 84-072 840731/- Flow Isolation (RWCU) Actual Delta Flow 189. WPPSS 2 397 GE 84-072 840808/- Flow Isolation (RWCU) Actual During Flow to Main Condenser 190. WPPSS 2 397 GE 84-072 840808/- , Flow Isolation (RWCU) Actual During Flow to Main Condenser l
8 Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket NSSS Report Event Unit (s) Measured ESF System Neber Vendor Number Date/Tlee Parameter Function
- Reason 191. WPPSS 2 397 GE 84-072 840810/- Flow Isolation (RWCU) Actual During Flow to Main Condenser 192. WPPSS 2 397 GE 84-072 840918/0200 Flow Actual During Flow to Isolation (WRCU)
Main Condenser 193. WPPSS 2 397 GE 84-072 '
840918/- Flow Isolation (RWCU) Shifting Flow from Condenser to Recir-culation 194. WPPSS 2 397 GE 84-033 840814/1455 Temperature Setpoint too Conservative Isolation (RWCU) 155. WPPSS 2 397 GE 84-033 840831/- Temperature
- Isolation (RWCU) Setpoint too Conservative 1%. WPPSS 2 397 GE 84-033 840905/1652 Temperature Setpoint too Conservative Isolation (RWCU) q 197. WPPSS 2 397 GE 84-081 840816/1030 Temperature l Isolation (RWCU) Logic Switch in Wrong Position 198. WPPSS 2 397 GE '84-081 840818/0315 Temperature Isalation (RWCU, m Switch in Wrong'*
RCIC) Position N 199. WPPSS 2 397 GE 84-091 840823/- Flow Isolation (RNR) High Shut Down Cooling Suction Flow
} 200. WPPSS 2 397 GE 84-097 840904/0317 Flow i Isolation (RWCU) Shift of Flow from i
j 201. Lacrosse 409 AC 84-015 840829/0945' Pressure Isolation (MS) Failure to 8ypass q
During Shutdown 202. Lacrosse 409 AC 84-021 841124/1340 Loss Of Power Power (OG) Incorrect Responsive to Alarms ,
i.
l i
1 1
l l
J 4
l
+ t Table A.4 (Cont'd)
- Valid (Non-Design Basis) ESF Actuations Docket MSSS Report Event Measured ESF System Unit (s) Number Vendor Number Date/ Time Parameter Function
- Reason 203. Catad a 413 W 84-017 841021/0635 Manual / Flow Fluid (AFW) Trip of Both Main Feedwater Pumps 204. Catada 413 W 84-023 841119/0645 Manual Trip of Both Main Fluid (AFW) l-Feedwater Pumps 205. Catad a 413 W 84-024 841124/1339 Level Fluid (AFW) Checkout Without Written Instructions 206. Catada 413 W 84-025 841127/0934 Reactor Trfp Fluid (AFW) Personnel Error Caused Loss of Main Feed Pumps 207. Catada 413 W 84-028 841205/0111 Loss of Power Power (DG) Supply Breaker Opened Following DG Test 208. Grand Gulf 1 416 GE 84-045 841014/1700 Loss of Power fluid (HPCS D.G.) Weather Caused Isolation (RWCU) Voltage Transients 209. Crand Gulf 1 416 GE S4-051 841102/1921 Flow Isolation (RCIC) Manual Turbine Trip i m Caused High Steam Flow
! 210. Grand Gulf 1 416 GE 84-051 841103/0650 Flow Isolation (RCIC) Opening Valves Caused High Steam Flow 211. Grand Gulf 1 416 CE 84-053 841129/0055 Level Fluid (HPCS); HVAC Defective Special Test (58GT); Isolation Equipment (AB,RWCU) 212. Grand Gulf 1 416 CE 84-058 841224/1232/ Reactor Scram Isolation (MS) Spike of IRM Caused By Increase in Feedwater 1..
FIOW I
1 ey e
. ?
b v
Table A.4 (Cont'd)
Valid (Hon-Design Basis) ESF Actuaticas Docket NSSS Report Event Measured ESF System Unit (s) Number Vendor Number Date/ Time Parameter Function
- Reason 213. Byron 1 454 W 84-017 841123/2145 Pressure Fluid (CH); Inadequate Removal of Power (DG) SI Block 214. Callaway 1 483 W -
840808/- Pressure Fluid (M) Undetected Trip Condition
, Coincident With Test to 215. Callaway 1 483 W 84-034 840822/2317 Loss of Main Fluid (AFW) Block Switch Moved to Feed Pump Permit 216. Callaway 1 483 W 84-042 840923/0805 Reactor Trip Isolation (FW) Spike Generated by Cable Removal 217. Callaway 1 483 W 84-045 840930/1029 Reactor Trip / Isolation (FW) Deficient Procedure Temperature 218. Ca11away 1 483 W 84-047 841006/1437 RX Trip Isolation (FW) Technician Removed Control Power Fuses 219. Callaway 1 483 W 84-048 841006/2120 Reactor Trip Isolation (FW) Reactor Trip Breakers Reopened When Closed 220. Callaway 1 483 W 84-048 841011/0334 Reactor Trip Isolation (FW) Seactor Trip Breakers Reopened When Closed 221. Callaway 1 483 W 84-048 841022/1652 Reactor Trip Isolation (FW) Reactor Trip Breakers Reopened When Closed
~
222. Callaway 1 483 W 84-051 841014/1848 Level Isolation (FW) Swell from Steam Dump Va11ves Suddenly Opening
4 Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Docket NSSS Report Event Measured ESF System Unit (s) Number Vendor Number Date/ Time Parameter Function
Isolation (MI) Instrumentation 224. Callaway 1 483 W 84-054 841021/1208 Level Fluid (AFW) Adjustment of Power Range Isolation (MI) Instrumentation -
$ 225. Callaway 1 483 W 84-055 841021/0508 Level FIuld (AFW) Calibration of Feedwater Isolation (MI) Control System 226. Callaway 1 483 W 84-056 841022/0513 Level Turbine Trip on High Fluid (AFW)
Isolation (MI) Hood Temperature 227. Callaway 1 483 W 84-056 841023/1527 Level Fluid (AFW) Steam Dump Cycling Isolation (MI).
228. Callaway 1 483 W 84-057 841027/0350 Reactor Trip Fluid (AFW) Blown Fuse in MFW Control Isolation (MI) Caused Low SG Level 229. Callaway 1 483 W 84-058 841030/1152 Level Steam Dumps Failed to Fluid (AFW)
Isolation (MI) Operate Properly 230. Callaway 1 483 W 84-059 841105/1156 Reactor Trip Fluid (AFW) FW Oscillations Caused Isolation (MI)* by Ruptured Air Line 231. Callaway 1 483 W 84-059 841106/0450 Level Fluid (AFW) FW Oscillations Caused Isolation (MI) by Ruptured Air Line 232. Callaway 1 483 W 84-060 841114/1451 Level Fluid (AFW) SG Level Oscillations Caused Isolation (MI) While Attempting Turbine Run Back
= 9 Table A.4 (Cont'd)
Valid (Non-Design Basis) ESF Actuations Report Event Measured ESF System Docket NSSS Number Vendor Number Date/ Time Parameter Function
- Reason Unit (s)
W 84-061 841129/0305 Reactor Trip Fluid (AFW) Power Loss to EHC Caused 233. Callaway 1 483 Isolation (MI) Turbine Trip W 84-065 841217/1208 Level Fluid (AFW) Failed Control Circuit in 234. Callaway 1 483 Isolation (MI) Main Feed Reg Valve -
84-065 841218/0036 Level Fluid (AFW) Main Feed Reg Valve
~
235~. Callaway 1 483 W Isolation (MI) Did Not Operate Correctly i
e I
.i Table A.4 (Cont'd)
- AB = Auxiliary Building RBV = Reactor Building Ventilation -
RCIC = Reactor Core Isolation Cooling RHR = Residual or Decay Heat Removal SBGT = Standby Gas Treatment SFU = Standby Filtration Units CB = Control Building CH = Charging CP = Containment Purge CR = Control Room DG = Diesel Generator EFW = Emergency or Auxiliary Feedwater HPCI = High Pressure Coolant Injection M = Multiple MI = Miscellaneous MS = Main Steam ND = Not Defined PCIS = Primary Containment Isolation System .
CS = Containment Spray CT = Containment FW = Feedwater HPCS = High Pressure Core Spray MSIV = Main Steam Isolation Yalve RWCU = Reactor Water Cleanup SFRCS = Steam and Feedwater Rupture Control System VIAS = Ventilation Isolation Actuation System i
1 86
-- -y ..- , - - .-- ,. ,.- .. . -,.
Table A.5 ESF Actuations - Heating and Ventilation Systems System Names Auxiliary Building Gas Treatment Auxiliary Building Special Vent Auxiliary Building Ventilation -
Control Building Emergency Air Filtration Control Building Ventilation - Standby Filtration Unit Control Room Emergency Air Cleanup Control Room Emergency Air Treatment Control Room Emergency Filtration Control Room Emergency Outside Air Supply Control Room Fresh Air Control Room Heating, Ventilation and Air Conditioning Control Room Ventilation Emergency Filtration Train (Control Room Heating, VentilationandAirConditioning)
Shield Building Vent Standby Gas Treatment C
l l
l 87
TAB.E A.6 FAu!E E5: ACTUATIOV?
E C ET N535 REPO:- EVIV MEA $50 BAi!C (AINit NUMIER VE C R rcMI F CATEf tit 1E FAFPITE: FL?CTIO. CKIE A:TICt BP0 m 3 reg y 1 50 25; GE g4 03; g40st4j05;; y;;;tg3 pc;E COMiltaTIO.. ~E!!:1 BR0 4 5 F R*Y ! 50-2'I DE 24-0!! 840921/102T PAJF. Fu):~ FEXENEE TEi~:'O E40Wrn FERRY 3 50-276 CE 84-005 640727/2217 MAra)AL P0,ER PROCEDiFE TE5TIf4 BCOWN3 FEF8Y 3 50-296 GE 84-009 840913/1443 LEVEL FLUID +POWE; FERSONNEL TE3TIta E*0WPG FE50Y 3 50-296 OE 84-009 840915/1523 LEVEL FLUID 4 5 5 COMBINATION TEiTI!C BROWN 5 FERRY 3 50-256 GE 64-010 841010/1039 LOSS Or POWER F0 WEE FERSONNEL TESTIte EDUNiUICK 1 50-325 CE 64-011 840711/1215 FIRE DETECTION HVAC LENOW 0FERATICN BRUNSWICV ! 50- 5 E 64-012 540725/0&f2 LOSS OF FC4 R HVAC EQUIPMENT OFERATIS BRUNSWIO'1 50-r5 GE 84-013 840317/1301 FIRE 0 TECTION WAC SPURIOJ5 (fERATICA BR'J6WICr 1 50-r5 OE 64-020 840902/1625 FIRE DETECTION HVA: itFNCO; CIERATICV BRJ 64!CK 1 50-725 GE 84-020 840902/1845 FIRE DETECTION WAC LWNM 0;EGTIO%
BRUNSWICY.1 M-325 GE 64-022 840906/1240 TEMPERATEE ISOLATION ECUIPMENT OFEcATIO BRUN5WICV ! 50-!! GE 84-025 840110/0909 RADIATICri 150 N LUID N4TURt5 OPI%T:0 BoVN540 1 50-r! OE 34-00i 841022/1624 FIRE DETECTION WAC ACTUA. CO*.!TC':T; BRLTEJICV 1 50-325 GE 84-02? 841029/1410 RADIATION WAC COMEIt3TIGi 0:EA~:J.
B2MLIO 1 50-r5 GE 64-0?1 841107/2145 FIFE DETECTION HV4 SPURICJ5 CFEUT:9.
BRf64C' 1 .
50-325 GE 64-031 841109/1119 FIRE CETECTIO's HE 55GI005 0:E:C:C-BWJ54CP : 50- 5 E S4-031 E41109/1523 FIRE DETECTICt. HVC SNR:0UI 0?I~ 'T:C'.
BRUGCO: 1 50-K5 GE 64-031 841109/1903 FIRE DETECTION WAC SFU;IO : CONiT4;TD.
BRUN5W!O'1 50-325 GE G4-031 841113/ MIS 5ING FIRE DETECTION WAC P5!ING 0:E:ATICA BRUN3WIO:1 50-325 GE 84-031 841113/2336 FIRE DETECTION WE $5%!0;.t2 0:EU':?:
BRUN? WICK 1 50-325 OE 64-O r 841114/0150 T0XIC GA3 ISOLATION UNNNGC! 0:E:ATIG:
E@UNSWIC" 1 50-r5 GE 84-032 841116/0202 T0XIC OAS ISOLATION LNKNOWN OPE;ATIO.
BRUPGWICr 1 50-325 CE 84-032 641116/0400 T0XIC 0A5 ISCLATION LENOW C:ERATION BRtJ6WIO' 1 50-325 GE 84-0?2 841116/0505 T0XIC OA5 ISOLATION lt G WN CfEAT:0N BRUN?WICf 1 50-325 OE 84-032 84111e/0605 T0XIC CA5 !$0LAT!0N t m 0WN CFERATIC' BRUNSWICK 1 50-325 GE 84-030 841208/0859 FIRE DETECTION HVAC SPURIOU1 0 UATION BDUNSWICr ! 50-325 GE 34-030 84120?/1424 FIRE DETECTION HVAC SPURIOU5 0FEMT!O'.
BR16 WICK 1 50-325 GE 84-030 841208/1751 FIRE DETECTICt; HVAC 55910J3 0?EG IC .
BRUN5WIO 1 50-325 GE 64-030 641213/0912 FIRE ICTECTION Wi.C SP9I005 0FEMTIC; E4UN5WIO' 2 50-324 GE 84-012 841024/1140 FLOW ISOLATION SPU;ICUS OFERMIC%
BtCN! WICK 2 50-324 CE 64-017 S41130/1456 TEMcERATURE ISOLATION EQUIFMENT C;EFAi!0N BYRON 50-4 9 WEST 84-011 841109/1000 RADIAi10N HVAC PERSONNEL CONITRUCTICrc BWON 50-4 9 WE5T 84-010 841112/0830 RADIATION MISCELLANEOUS COMEINATItN 0:EMTION BYRON 50-4% WEST 84-010 841119/ MISSING RADIATIOP. MISCELLANE045 COMB!fATION TE5 TIN}
BYRON 50-454 WEST 64-01** 841127/0746 RADIATION MISCELLANEOUS SPURIOU5 TESTING BYRON 50-454 WEST 84-021 841127/1114 RADIATION HVAC SPURIOUS OPERATION BYRON 50-454 WEST 84-019 841127/1540 RADIATION MISCELLANEOUS SPURIOUS TESTING BYRON 50-454 WEST 84-018 841128/0837 LOSS OF POWER WAC PROCEDURE MAINTAINANCE BYRON 50-454 WEST 84-021 841128/1130 RADIATION HVAC SPURIOUS OPER4 TION BYRON 50-454 WEST 84-019 841128/1135 RADIATION MISCELLANEOUS SPURIOU$ TESTIf?0 BYRON 50-454 WEST 84-022 841129/2312 RADIATION MISCELLANEC8J5 COMBINATION TESTIf6 BYRON 50-454 LEST 84-021 841130/0311 RADIATION HVAC SFm'JU5 0FERATION BYRON 50-454 WEST 84-021 841130/1210 FADIATION HVAC SFURIOUS OPEFATION BYRON 50-454 WEST S4-022 841130/2116 RADIATION MISCELLANE0US C0FBINATION TESTIN3 BYRON 50-454 WE5T 64-021 641201/1115 RADI4 TION WAC SPURIOJS OPEMTION BYRON 50-4% WEST 84-019 841202/1458 FADIATION MISCELLANE005 SPURI0ih ic:.TINO BTSON 50-4 9 WEST 84-022 641202/2059 RADIATI'ON MISCELLANEOUS COMBINATICii TE!TIfG BYRON 50-454 WEST 54-021 641203/0313 PADIATION HVAC 55URIOU5 CfEFATION BYRON 50-454 WEST 64-022 841203/1555 RADIATION MI5CELLANEC8J5 COMBINATICN TE3TitG BYRON 50-454 WEST 84-029 ' 841205/0541 RADIATION HVAC FROCEDJRE TE5 TIN)
BYRON 50-454 WEST 84-029 641207/0G41 RADIATION HVAC COM5IraTION OFERATICN BYRON 50-454 WEST 84-029 341212/010e RADIATION WAC COMBINATION OFER:.T!0N BYR0ri 50-454 WEST 64-027 841212/0750 RADIATION HVAC PROCEDURE MAINTAINANCE BYRC4 50-4 9 WEST 84-031 841215/2005 RADIATION MISCELLANEGU5 SPURIOU5 0FERATION BWON 50-454 WEST 84-031 641217/1704 MISCELLANEOUS 5FEICUS OFERATION RgIATION
BYFON 50-454 WEli 84-0?O 84121G/0334 LOSS OF PCWE MISCELLAr;E005 E0'JIFTENT OFEFAT:0N
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EYC 50-4!4 WEST ?4-053 641216/22 % REIATION HVC CO*2:GTICN C EWI?
BWG; 50-4'I WE57 M-031 64:219/0?!? RADIATION MISCELLANEO)S 59DJ3 0:E;C::
EiFGi 50-454 WEST H-r7 E41221/002S FADIATION WC FROCEDU:I I! NTMfE:2 EVFF; 50-4*4 WEST 84-027 641222/1522 MLIATION H/R FROCE}/E MAD. tai *22:E EYRON 50-454 WEi!84-03s 541225/0755 RA*4ATION HW.C FEE 50E MA7TMNZ:2 BW3N 0-454 WE?T 54-03? 341226/1034 PADIATI0r; WA' COM51MTION 0;EC:C.
EY:0'. 50-454 WEli F-035 24;*26/12:4 MAG. HVAC PERSONNEL GFE%iiX EYVJ; 50-454 WEIT 5*-023 641226/1000 RACIATION WA: CCv51N TIO'; 0:E%TIO*.
BfRON 50-454 WEST 84-037 841226/23;5 RADIATION WAC lemN OFERATW; BYRON 50-454 WEST 84-033 641230/0557 FADIATION WAC COMEINAi!0N OFERATION BYRON 50-454 WEST 84-038 841231/0937 FADIATIGN WAC SOURICUS MAINTAINATE CALLAWAY 50-423 WEST 84-018 640718/1455 LOSSQFPOWER ISOLATION COMBIMTION TESTIf4 CALL M Y 50-433 WEST 64-019 840719/0712 LOSS OF PO=ER ISCLATION NISSING CONSTRUCTION CALLAWAY 50-453 WEST 84-025 840310/1412 RADIATION ISOLATION SPURIOUS ffEMTION CALLAWAY 50-4S2 WEST 64-025 640613/1225 PRESSURE FLUID COMBINATION TESTits CALLAWAY 50-483 WEST 84-027 840813/1640 LOSS OF POWER ISOLATION PERSONE. TESTI'd CALLAWAY 50-433 WEST 84-027 640817/1525 LOSS OF POWER ISOLATION PERS0tJE MAINTAir#;:E CALLAWAY 50-483 WEST 84-032 640820/0246 LOSS OF POWER ISOLATICH COMBINATION 0:E%TRN CALLAWAY 50-413 WE57 M-03t 840?24/0551 PADIATIGN ISOLAT!0N SoVRIOUS OFEFATICL CALLAWF 50-43 WEST M-036 640325/1323 RADIATICA ISOLATION SPURIOJi 0?E47:0 C/sLTA 50-433 WE5i 9-05 840226/1431 RADIATION IS0JTION 5FWIOU5 0FEFJ.'!n CALLA 6'4 50-482 WEST 8-016 640527/1?25 RADIATION ISOLATION spi)RICUi 0FE% G (ALLAWh 50-453 WEi~ G-Oh 640323/0040 RCIATION ISCLAi!ON FER!ONNEL 0:ECATIG; CtLL E Y 50-4?? WES' 84-03! SC?07/10?0 LEVEL I5OLATION C0rEIOTION TESTIN-CA LAW 4 50-432 WEii U-036 64902/19: RO ATION ISOLATION SPWIOUi CFER'O; CALLAWAY 50-42; WEET M-Oh 90M4/0U7 REIATION ISOLATW4 SDURIOJi 0:EFAT:Oi CALLAWAY 50-43? WEST 64-04 909;*/102! LEVEL ISCLATION COMEIMTION M G 'AITA *E CALLAWAY 50-453 WEli U-044 641005/1720 LEVEL ISOL+ FLUID ACT@. PAIWAlt%CE CALL /WAY 50-453 WEST 54-040 H10:0/1424 LEGL ISOLAT W: COSIMTD; MAP.~4WE
- CALLAWAY 50-453 WEST 84-Os 64207/2 03 L055 0 P04r; ISOLATION EOUIPMIC 0:EUTIG.
CALLAW4 50-423 WEli N-06! S:20ii144 RCIATION ISOLATION CO3 P;ATD OFEPTD; C4LLNM 50-453 WE5i 64-063 91214/1229 RADIAT!C4 ISCLATION CCc31GTW. 0;E;C:3 CALLAWAY 50-452 WEIT H-0J 8:230/CI 3 LO55 0 POW 5. Ii1ATW. E.W. OFI~CD CAT &EA 50-4:3 WEIT 9-003 840322/ 40; UWOWN MISSPd inNN. 7:E:R:C CATAWM 50-412 6 37 64-02; 8 ;;14/10 5 LEVE. IS?.ATION Uma TEi .
COF 50-3:5 WE!? M-01? 340514!5F CO*21%TICN MIS:ELLANE005 EGJIFMET T C:E:C:
C00r 2 50-316 WEi! E4-02; 641120!1e10 TEVE%iNE ISO.AT:0N COME:NCICN TEST: J CRYSTAL RIVER 3 50-302 EW 9-0:5 S40713/;752 MI5 SIN 3 F0W5 E7) ipr. INT 0:EG D.
DUANE ARNOLD 50-32; GE H-C32 540934/024 RC:ATIGN HiR Cif31NATICN 0:E A* C; DUANE ARtOLD 50-3?! GE 84-0*2 90916/0225 PAUICI0'. WK COMBIMTION 0:EUTBN DUANE ARNOLD 50-?31 GE 64-032 840916/0500 RMIATION HVC COMBIN4TRN OFE% TION DUAE ARNOLD 50-331 CE 84-036 640 C /0331 FLOW ISOLATION SPURICU3 OPERATION DUAE #2NOLD 50-331 GE 84-036 840930/0256 TEMFERATURE ISOLATION SPURIOUS OFERATION DUAE ARNOLD 50-331 GE 84-036 641020/1515 LN NOWN ISOLATION SPJRIOUS OPERAi!0%
DUANE ARNOLD 50-331 GE 84-037 64101/1331 UNKNOWN ISOLATION SPURICd5 OPE %TW:
DIABLO CANYON 1 50-275 WEST 84-018 84 706/0340 RADIATION 'WAC EQUIPMENT OPERAT:0N DIABLO CANYON 1 50-275 WEST 84-019 840714/1417 NISSINO WAC OTHER TEiTIN3 DIABLO CANYON 1 50-275 WEST 84-022 840728/0709 COMBINATION MISCELLANE005 PERS0WEL TESTItG DIABLO CANYON 1 50-275 WEST 84-029 841104/2328 LOSS OF POWER ISOLATION trtNOWN OFEATION FT. CALHOLN 50-235 CE 84-014 640703/1100 PADIATION ISOLATION ACTUA. MAINTAINAN:I FT. CALHOUN 50-235 CE 84-017 M0803/1645 RADIATW4 ISOLATION ACTUAL OFEATIGi FT. CALWJUN 50-285 CE 84-018 S40607/1105 RADIATICN ISOLATW4 COMBINATION OPERATIGN FT. CALHOLN 50-255 CE 64-019 640102/042 RADIAT W4 100!ATION PER50t0& OPEMTW FT. CALHOUN 50-255 CE E4-010 840?21/1245 RADIATW: ISOLATICt; ACTUAL ODE %TI%
F7. CALHOUN 50-255 CE 34-024 341126/0644 PADIATD; ISOLATION ACTUAL 0:EST:CN GINM 50-244 WEST 84-000 640817/1445 LOSS OF POWER POWER EQUIFMENT TE5iINO GRAND OULF 1 50-416 GE 84-037 640815/1345 TENFERATME ISOLATION UNKNOWN OFEMTION CMD CU 1 50-416 CE 84-043 841002/0945 MANUAL FLUID PERSONNEL TESTPiG GRAND CJLF 1 50-416 GE 84-044 841006/0440 LOSS OF PCEER ISOLATION EQUIP"ENT OFEGAi!0N C E D GULF 1 50-416 GE 64-046 641017/1450 TEMPEPATURE ISOLATION LMEWN TESTING ORAND OULF 1- 50-41e GE 64-056 641219/2035 FLOW ISOLATION SFURIO'Ji 0:EATION C M D CULF 1 50-816 GE 84-057 841221/0443 !!OLATION PROCEDURE OPE %iiON g%'
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GIAND OULF 1 50-416 CE 64-059 841221/1000 TEVEFAil:E ISCOTION E0V!5ec T2?T!G
. HATCH 1 50-321 GE 84-013 840727/MI5iIK LEVEL FLUID EQU:Fr.Di' TEST N CTCH I 50-321 GE 84-02? 641104/211! L0i? CF F0WER WAC+!iCMTIO?. PEIO?J.EL MAINTA:NNE HATCH 1 50-321 O!84-023 -541107/1911 LOSS 0: POWS F/AC+IS0i.ATION PER5G6E_ MAINT;ItA C HA7CH ! 50-32: GE 64-020 6412:t/1700 LOS5 0F FCLE~ IS0;+:LUIC LN.KW 0FFATIC -
HATCH 1 -
50-321 GE S4-020 84121c/09M LOS3 0F POWEi !$0LtFLUit SFSI0d CfERATIC'.
MTCW ! h 321 GE 64-02; 341224/12 3 FLO,i ISC.ATI0t. C0ri! NATION CfEFATICS HATCH I 50-?:1 CE 84-02 641224/1345 FLOW 150LATIGi C0rilt.Ai!ON 0:EATIO; HATCH ! 50-321 GE 84-0 3 6412'5/0:05 FuGJ IS1ATI0t. C0Filt;ATI0to GPEUTI?.
HATCH 1 50-321 GE E.4-029 841225/1801 FLOW HVAC+I N TION EQUIP e ; 0?E ATIGi NATCH 1 50-?21 GE 84-020 841228/12?! LOSS OF P0.iER 150L+ FLUID SPURIOU? OPEFAT:01 HATCH 2 50-366 OE 64-009 840711/0745 LEVEL FLUID + POWER PROCEDURE TESTIC HATCH 2 50-366 GE 64-012 844508/0535 TEPFERATURE ISOLATION EQUIPMEPC 0:EMTION HATCH 2 50-366 CE 84-016 840815/1830 LEVEL POWER + FLUID PERSONNEL TESTIU MTCH 2 5)-366 GE 84-019 840924/1757 TEMFERATURE ISOLATION EQUIPMENT OFERATIO'.
HATCH 2 50-366 CE 84-019 840924/1823 TEPPERATURE ISOLATION E0JIFST CSEMTION HATCH 2 50-366 GE 84-019 840924/1948 TEMPERATURE ISOLATION E9JIPPENT OFERATICe; M TCH 2 50-366 OE 34-019 840924/2220 TEPPERATtRE ISCOTION EQUIP S T OFEMi!0N HATCH 2 ,
50-366 GE 64-024 841011/1715 LOSS OF POWER ISOLATION EQUIPME?C OFERATI0f!
. HATCH 2 50-366 CE S4-035 841213/2109 TEPPERATURE ISOLATION EQUIPMENT OPERATIO'.
HUMBOLDT E4 Str133 GE 64-002 641206/1500 MDIATION MISCELLAPE0US FER50cEL GFEMT:7.
INDIAN FT. 2 50-247 WEST 84-008 640713/1445 mat 4AL POWER + MISC COMBIN TION C0%T4;CT:?.
INDIAN FT. 2 50-247 WEST E4-026 841226/2220 FLOW MISCELLANEOUS C0FIINAT!0N CfERATIOS:
KEA'JNEE 50-305 WEST 64-013 840702/0105 MISSING WAC EQVI: S T Cfi4TI7.
W JNEE 50 305 WE3T 64-015 840914/1026 LOS5 0F POWER HVAC PER3ONNEL OFEMTICN N JNEE 50-305 WEST 84-019 841114/0822 LOSS OF POWER HVAC EERSOf E TESTIG VEWAUNEE 50-305 WEST 84-020 841216/0405 LOSS OF POWER HVAC EQUIPPE*C C'E'ATIC9 LACROSSE 50-409 OTHE 84-017 841016/0915 RADIATION ISOLATION EQUIF E C 0FERATION LACROS5E 50-409 OTHE 84-020 841!13/0809 RADIATION ISRATION EQUIPMENT OFEMTION LAS E E 1 50-373 CE 84-049 840824/1550 LOSS CF POWER ISOLATION PROCED$E TE5 TIM LAS E E 1 50-373 GE '84-04? 840524/1725 LOSS OF POWER ISOLATION PROCEDU;E TESTIt C LASALLE 1 50-373 CE 84-056 840921/ MIS $1NCr PRESSURE ISOLATIm PERS0 feel TEI~ N LAi E E 1 50-373 CE 84-C54 640921/2005 FLOW ISOLATION EQUIFFOr C3E%TIO.
LA3ALLE 1 50-373 CE 84-060 S40920/1000 FLOW ISOLATIGi Ut&K0I. TEIT:0 LASCE 1 50-373 CE 64-055 841001/125e RADIATION WAC PER$0t#A TEiilU L4SALLE 1 50-373 GE 84-057 841001/2211 COND VACLOM ISOLATION PROCED3E TEETIM LA3EE 1 50-373 CE 64-06: 841015/024i T0XIC GA5 HVA0 EPJIFMENT CfE4 TION LASALLE 1 50-373 GE 64-071 841024/1330 LOSS OF POWER ISOLATION FER30f?E TESTIG LASEE 1 50-373 CE 64-066 641101/0344 T0XIC GAS HVAC SF%ICUI C:EMT:0N LAS E E 1 50-373 CE 84-073 641106/1130 COND VAF0JM ISOLATION EQUIPSC 0:EFITI:A LASALLE 1 50-373 GE 84-074 841107/1'55 FLC4 ISCGTION PERSONTE TE5 TIE LASALLE 1 50-373 CE 84-077 841115/0915 LOSS CF POWER WAC COMBINATION TE5TIG L45ALLE 1 50-373 CE 84-078 841117/1331 T0XIC GA5 HVAC C0".BINATION OPEPATIGi LASALLE 1 50-373 GE 84-084 841130/2040 T0XIC CAS HVAC SPLRIOUS OPERATION LAEALLE 1 50-373 GE 84-091 841220/1930 T0XIC GAS WAC E0 VIP S T OFERATICN LASALLE 1 50-373 GE 84-089 841225/1716 TOIIC GAS HVA0 SPUR:0U3 0*ERATICt.
LASALLE 2 50-374 GE 84-046 840805/0640 TEMFERATUFE ISOLATION SFGIOUS OPERATION LASALLE 2 50-374 CE 84-051 840823/0944 TEMFERATLRE ISCLATION SPLRIOLt3 OPERATION LAS E E 2 50-374 GE 84-056 540327/1145 TEMPERATURE ISOLATION SFWIOUS OPERATION LASALLE 2 50-374 GE 84-062 840827/2212 FLOW ISOLATION ACTUA. OPERATION LAS E E 2 50-374 CE 84-063 840901/1158 MANUAL ISOLATION OTHE TESTI%
LASALLE 2 50-374 CE 84-069 840912/ MISSING COND VACUUM ISRATION EQUIPMDJ OFEETICN LASALLE 2 50-374 CE 64-065 640913/1557 TEMPEPATURE ISOLATION SPURIOUi TESTIf5 LASALLE 2 50-374 GE 84-072 841029/1752 MANUAL ISOLATION PER$0V E TESTI%
LA5ALLE 2 50-374 GE 84-075 S41112/1010 L0is GF PC4EF HVAC+ ISOLATION COPEIGTIQ*. TE57 N LASALLE 2 50-374 CE 84-074 841116/0$59 TEMPERATURE ISOLATICri SPLRIOU5 TEST N LA5ALLE 2 50-374 CE 64-064 641214/1045 F E AL ISOLATI0ti EQUIP C C MAINTAINANCE LIMERICK 1 50-3': CE 84-005 841113/1300 T011C GAS HVAC PER50 VEL O'EUTIO?.
LIMERICK 1 50-35' GE 84-007 841114/1251 LEVEL ISOL+FL+ POWER PERSONNEL MA NTAINANCE LIMERICr 1 50-352 GE 84-008 641115/0300 T0XIC GAS HVAC EQUIPNENT GPERAT:0N Li s ICr 1 50-352 CE G4-021 841115/2157 LOS5 0F POWER ISCLATION EQUIPMEt3 TESTIO LIMERICK 1 50-352 GE S4-011 841118/0e40 RADIATION ISCOTION CO*!BINATION TESTING LINERICK 1 50-352 GE 84-010 641118/045 HVAC EQUltrENT 05EMTION TggC C45
LIMERICK 1 50-352 E 84-014 841121/2225 MISSING ISOLAT!0N PER30:Ja TE5T N LIO:M 1 50-M2 GE 64-020 S?1123/1035 T0XIC 0A5 HVA2 PEPi0tsE Malt.i4D3TE LI S E ! 50-3'2 GE 84-019 841126/0222 PCE595E 150GTION C07.EINAT:1 TEii N LI G IO 1 50-252 GE S4-015 841126/M50 FRE??5E ISCtATION PF00ME TEi N LIGW I 50-352 GE G4-015 641126/0752 FRE55URE ISOLATION COMEPEIX TE5 N LIGIC*1 50-352 GE 84-02! 841209/0710 T0XIC GA5 W4C ECUPMENT 0:EMTID LIFEE W 1 50-3'2 OE 84-030 541210/2120 LO55 0F POWER HVA> ISOLATION FER10?t.:. .c: IC LIGIU 1 50-152 GE $4-03. E4!211/0?M FLOW ISO.ATI0h FER50NNE. M4:G "E .i.
LI G ICV 1 50-3'2 GE G4-022 841211/1540 TEMFERA'URE ISOUTIT. FER50tI'. TEITJ LIMERICV.1 50-252 GE 64-023 841211/2115 T0YIC GA5 HVAC EQUIPMENT 0 EMT 0N LIMERICK 1 50-352 E 84-034 841212/0520 TEMFERATURE ISOLATION E0JIPMENT OPEMi!0N LIERICK 1 50-352 CE 84-012 841215/1405 TEMPERATLEE ISOLATION E9)IPrBJ TE5 TIE LIMERICK 1 50-352 GE 84-026 841216/0135 TEMFSATURE ISOLATION EQUIPPINT OPERATI?i LINERICK 1 50-352 E 84-035 841216/1113 TEMPERATURE ISOLATION EQUIPMENT TESTING LIMERICK 1 50-352 GE 84-036 841217/0515 TEMPERATURE ISOLATION EQUIPMEtJ CFEMTION LIMERICr 1 50-552 GE 84-039 641221/0252 LOSS OF POWER ISOLATION EQUIPME!J TEST;NS LIMERICV 1 50-352 GE 84-040 641221/0442 LOSS OF P WER ISOLATION PROCEUJRE 0:ERATION LIMERICK 1 50-352 GE 84-041 841222/1242 MISSING HVAC+ISOLATICN NATUM LP OPERATICN LIMERICK 1 50-?'2 GE S4-045 841230/0627 MISSING WAC NATURALP OFERATION LIFERICr 1 50-352 GE 64-04o 841230!!014 70XIC GA5 WAC EQUIPMENT OPEF4 TION MCOUIEE 2 50-570 WEST 84-015 840703/1545 LO55 0F POWER ISGLATION PER50cEL TEST N MC M RE 2 50-370 WE5T 84-018 640819/1626 L0i5 0F POWER POWER PROCEDURE TE5T N MONTICELLO 50-26? GE 84-026 840?10/1530 ROIATION HVAC+ ISOLATION FER50NNEL TESTPJ r$NTICELLO 50-263 GE 84-025 84M14/1515 LOS5 0F POWER HVAC+ISOUTION E91PPSJ CPEMT!0:
MONTICELLO 50-263 E 64-029 640915/1835 LOS5 0F POWER POWER COMBINATION OFERATIO; MONTICELLC 50-263 GE 2 H 29 840915/1953 LOSS OF P0mER POWER COMBINATION GFERATIGN MONTICELLO 50-253 GE 84-030 541009/1800 T0XIC GAS HVAC PERSONNEL 0;E MT 0N MONTICELLO 50-263 GE 54-031 841016/0001 T0XIC GA5 HVAC UNG OFEMTION MONTICELLO 50-263 CE 84-033 641127/2137 LOSS OF FCWER HVAC+ ISOLATION EQUIPMEN' OPEMTICL NO. ANNA 2 50-339 WEST 84-00i 841025/NISSIE MANUAL MIS $1NG PROCEDUSE TESTI@
NO. ANNA 2 50-339 WEST 84-010 641101/1128 LOSS OF POWER FLUID COMBINATION OFE:ATION NINE MILE PT. 50-220 GE 64-016 841001/1759 LOS5 Or POWER WAC E@)IPMENT OPE:'i!CN OYSTER CPEEV 50-219 GE 54-020 540910/MI55IG LO!5 0F POWER ISOLATION EQU:PrPJ TESTD42 OYSTER CFIEK 50-219 GE 64-025 641029/0203 LEVEL FLUID + POWER PERSO%Ei TEIT!rd PALISADE 5 50-2Y5 CE 84-00? $40704/0940 FRESSURE MISCELLANEOUS PROCEDSI MAINTAIN 4'CE FALIEADE5 50-255 CE 84-011 840719/2242 PRESSURE ISOL+FL+MI5C PERiON?F mTIG PEACH POTT 0" 3 50-279 GE 64-010 840816/0341 LOS$ Oc POWER ISOLATION PERS0t;EL MAINTAI E E PILORIM 1 50-293 GE S4-015 640929/MISSIG MANUAL FLUID PEP 50tel MAINTA:NA'4E PILORIM 1 50-293 E 84-016 841207/MISSIC LOSS OF POWER ISOLATION PERSONNEL MAINTA: E E PILORIM 1 50-293 GE B H 19 841225/1905 MISSING ISOLATION CC"5! NATION CFEMTION OSAD CITIE5 1 50-2*4 GE 84-013 640808/2206 LEVEL ISOL+FL+ POWER PERSONNEL TEST N OVAD CITIE5 1 50-254 GE 84-016 840223/1252 FLOW ISCLATION PERSGNNEL TESTIN}
@JAD CITIES 1 50-254 GE 84-018 840922/2350 RADIATION WAC UNKNOWN OPERATION 0)AD CITIES 1 50-254 GE 64-018 840924/1030 RADIATION HVAC SPURIOJ5 0FERATION 00AD CITIES 2 50-265 GE 84-009 840805/1044 LOSS OF POWER ISOLATICN E0)IPMENT OPEMTION OVAD CITIES 2 50-265 CE 84-011 841130/1250 RADIATION HVAC+ ISOLATION COMBINAi!0N OPERATION OVAD CITIES 2 50-265 GE 84-012 84!20!/0925 RADIATION HVAC+ISOLAi!ON COMBINATION OFERATION ROBINSON 2 50-261 WEST 84-010 841107/MISSIE PRESSURE MISCELLANEOUS MISSINO CCK3TRUCTION SALEM 1 50-272 WEST 84-018 640713/1557 MISSING MISCELLANE003 PERSONNEL TESTING SALEM 1 50-272 EST 84-024 841020/2300 MISSING ISCLATION SPURIOUS OPERATION SAN ONOFRE 1 50-206 WEST 84-015 841116/1134 MISSIG ISOLATION + MISC UNKNOWN OPERATION SAN ONOFRE 2 50-361 CE 84-032 840703/103? RADIATION HVAC SPURIOUS OFERATION SAN ONCFRE 2 50-361 CE 84-038 840708/1043 RADIATION HVAC SPJRIOUS OPEMTION SAN ONOFRE 2 50-361 CE 64-040 640723/15;5 PRESSURE ISOUTION COMSINATI0N TE5TUC SAN ONOFFE 2 50-361 CE 64-035 640723/1507 RADIATION HVAC SNR!O"5 GPERA*!C.
SAN ONOFRE 2 50-361 CE 84-03G $40726/00'3 RADIAi!0N WAC SPURIOUS OFECF:04 SAN ONOFRE 2 50-361 CE 84-047 540811/1141 RADIATION WAC SPURIOU5 OPEFATION SAN ONCFRE 2 50-361 CE 84-047 640311/1144 MDIATION HVA.: SFtRIOU5 0FEMTICN SAN ONOFRE 2 50-361 CE 64-047 840811/1302 RADIATION WAC SPUR:005 -
0FE~ATION SAN ONOFRE 2 50-361 CE 84-047 840311/2242 RADIATION WAC SPURICL'i CPEMTION SAN OWFRE 2 50-361 CE 84-049 840?24/1445 RADIAi!0N ISOLATION SPURI0di 0FERATION SAN ON0FFE 2 50-361 CE 64-051 640919/2218 LOSS OF F0WER ISOLATION FRCCEDURE CONSTRUCTION SAN ONGFRE 2 50-3e1 CE 84-056 841002/1312 L 5 0F POWER 15CLATION EQUIPE GFERATION
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SM ON0c5E 2 50-361 CE 84-057 641003/00~5 ROIATION Wti PERS M IL TEITIG SAN 08& RE 2 50-361 CE 84-061 841022/0517 MDIATI0r. ISOLATICA SFU; 0'.L5 CJU4Tpy.
!# ONOFFE ~ 50-361 CE 24-06: S:0~2/055! RACIATICN 150GT!0N SPAICU? C#EFAT 6.
SAN ON0cRE 2 50-361 CE 64-06; 641023/06I0 RADIATION IS*LAT'% E0]IFMIC 0 ENT!0.
54N OC G E 2 50-541 CE H-043 841024/1255 RRIATICN ! SOLATION FRC-:ED'5I 0:E:AT:CN SAN f/rf5E 2 50-361 CE 84-064 641050/;505 FAOIAiiGN II&ATION PER50m PA NTA!W.;E SAN f/;0GE 2 50-361 CE 8-C:i E41:02/15'7 FRIC:0:: ISOLATION Sc'.S! OUI 0:EFr!0%
S2: 0*W FE 2 50-16: CE 84-041 641107/1120 MDIATIO'. ISCLATION S M IGU5 0;FATION SAN ONOFRE 2 50 41 CE 84-06. 54110!/04:4 MDIATICN ISOLATION 550RIObi 0FFCICN SAN ON0FRE 2 50-36: CE 84-071 841120/0:33 RADIAT:0N ISCLATION S M IOUI 0 ERAT!0N SAN Otr5RE 2 50-361 CE 84-071 841121/0320 RADIAT!0N ISOLATIO*. SF'JRICUS CPEMI:0N SAN ONOFRE 2 50-361 CE 84-075 841130/1045 RADIATION WA0 SPURIOUS 0:FATI0'.
SAN ONOFRE 2 50-361 CE 84-074 641203/0947 RADIATION ISO /JTION SPURIOU5 0FERATIG-:
SAN ONOFFE 2 50-561 CE 64-077 641210/1115 MDIAi!0N WA0 COMBINATION TE5TIfd SAN CN0FRE 2 50-361 CE 84-0$'., 841219/0745 LOS$ CF POWER ISOLATION PROCEDfE TE5'ItG SAN ONOFPE 2 50-361 CE 84-076 841222/202S RADIATION IS0Ji:0N SFURIOUS OFEMTION SAN ONOFRE 2 50-361 CE E4-0!! S4:223/1245 LOSS OF POWER ISOL+cLU:D FERSON* EL CCNiTRUCION
$4J ONOF#I 2 50-361 CE 84-076 34!227/1444 RADIAT:Cu ISOLATION SPURIOUi 0FEDAi!0'.
54N Otr/RE 3 50-362 CE 54-03" N0727/:755 LOSS OF POWER IS & TION SCto!0U? FFAi!?
Std 00FRE 3 50-362 CE 84-041 H:125/0854 RAMATION IiOJT:0N FER50NNEL 0:E*
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SE000YM 1 V-327 AEi' F->:: F W ii0730 70aIC 045 ~50 ATION FE 50'.E. C:E U ':
520'J0YP 1 50-327 WEli 64-01^ 640!!3 4 :5 MDIATION 15CLATIS P?::. : . ::Pr :
SE7J0W 1 50-327 KE!T S4-6:.0 54MI4/173; RAM 47!0. ISCLA7:0N FLE:0.1 0FE A7:.
SE000YM I 50-327 WE!* 64-060 $40923/00U RGIATION IS0JTION S M 0CI F FATI:
SE0AW 1 SC-327 *E!- 84-060 8409N/0225 MLIATION ISCtATION 200RIO;' CFFA*:: .
SE000 W ! 50-327 WEIT E4-Oa2 S4]929/2t0 FAMATIO'; ISCLAT:. ECU: :'E7 ;~ETC:2.
SE7f W 1 50-?27 WEST $4->di N!194/122I RAMATION ISOL4'Z . CCD*.*:: P '-~;'" R SE03G 2 !L-2:! WE!' 9-011 24;7!!!0:24 M Maii0c !$0.4T:C' 9Pf!" - ::E:r' SE0'.M- 2 50-226 WE!' 9-0:1 9 0 14r0744 MMATIG4 IS]JTI0n UGUA UFr!.
SE000 W 2 50-325 WE!' 54-0;; 807:U0:5I SA!IATIOP. IS0dTI: . UM?ik: FERP .
- 57. LUCIE 1 50-315 OE 9-005 840525/ MISSING MISSINO ISOLATION SFELI 0:57" ST. LUCIE 2 50-35? CE 54-00! E40630iMI55:N3 LOSi 0F FCGER !50LATICs E0v!5MEC TE!" .
ST. LUCIE 2 50-3F CE 64-007 641024/2255 RADIATION WA:vISOLAi!ON FER50V.E. 5:WIWE ST. LUCIE 2 50-359 CE 54-005 041104/0549 RADIATION WAC+ISOL+F0w SP5 IOU 5 TE57 N ST. LUCIE 2 50-3D CE 84-014 64:129/0450 LOSS OF POWER ISCL+FLUIE EEI~~IC O' FAT!?N SLERY 1 50-290 LEST 64-023 641113/13!5 UNWOWN MISCELLANEOUI UFNOWN TEiT:':
SLRRY 1 50-280 WEST 64-024 641116/1436 MISSING POWER +MI3; PROCEDJRE MAICAINAN2 SURRY 2 - 50-281 WEST 84-014 840321/1644 LOSS OF POWER FLUID + MISC COMP! W ION OPERATIOT SUSQUEHANNA 1 50-337 GE 64-036 840724/1541 LOSS OF POWER WAC EQUIFMENT OPERATICG SUSQUEHAft4A 1 50-357 GE 84-037 840803/0635 LOSS OF POWER WAC+1SQLATION SPURICUS MAINTAINANCE SU5GJEHAWA 1 50-387 CE 84-037 840803/0639 LOSS OF POWER WAC+ ISOLATION SPURIOUS MAINTAINANCE SUS @.EHANM ! 50-337 CE 84-043 841006/1654 LOSS OF PCWER ISOLATION EQUIPMENT OPERATION SUSQUEHANNA 2 50-388 CE 84-0!! 840705/2040 RADIATION WAC EQUIPMENT OPERATION SUSQUEHAWA 2 50-3S5 GE 84-011 840706/1929 RADIATION WAC EQUIPMENT OPERATICri SUSQUEHAWA 2 50-388 GE 84-011 840706/2122 RADIATICN WAC EQUIPMIPC 0FEFATION SUSOUEHANNA 2 50-388 CE 64-011 840706/2205 RADIATION WAC E@J!FMENT 03ERATI9:
SUSOVEHANhA 2 50-388 GE 64-015 840802/1940 FLOW ISOLATION EQUIFMENT OFE:".! ION SUSQlEHANNA 2 50-333 CE 64-020 840929/1400 LOSS OF POWER ISOL4 TION COMBIN4 TION TE5 TING SU30VE MNNA 2 50-38? CE S4-025 641031/1815 FRESSURE WAC Eg;IPMEC M4INTA:N'*;;E TUR G i PT. 4 50-151 LEIT 84-0:5 84071e/1400 MAP.'JAL FLUID FERSCM.E. C N T;. ?!Ci TO.m 50-344 WEST 64-016 640920/0815 COMBINATION MISCELLANEOU3 COSINATICN OFEMT:'.N VERKAi YAVEE 50-271 GE H-0:5 640724/1254 MANUAL POWER COME:?ATION 0FERAT:0N VERM00 VAWEE 50-271 OE S4-023 541124/1255 MANVA. ISOLATION PER$0N h it:. N WATFFORD 3 50-392 CE 64-001 84!225/1820 T0XIC GAS WAC SFtri!OUS 0*ERATION LPPS3 2 50-F7 OE 84-072 840705/1700 FLOW ISOLATION SPGIOUI 0FFM:7 WCF55 2 50-397 GE $4-072 M0706/00'0 FLOW ISOLATION SFURIOU3 0FERATION WPPSS 2 50-397 GE 84-072 640706/0216 FLOW ISOLATION SFURINS OfEMTIOi WCFSS 2 50-397 CE S4-073 640703tM!$3tNO TOI!C GA3 WAC EQUIPMIC CFF;TZN 92
~
W PSS 2 50-F7 C{ $4-071 640716/1400 LOIS OF F(.44ER ISOLcTIGN FER50.?;E;. P4*NTAIG7i WPP55 2 50-3?7 E 64-077 6'4720/222? RMIAT!rf HVg cF!5IK: CcFA'!C; W55 2 S0 'M7 GE 64-07 640721/1145 PCIATION U; SPJ;;;.'! 0:EFAT:
WFPS3 2 50-3:7 OE 54-071 E40FI/0045 MD:AT:0'; W40 S:Lc !C .'. 0:F;'!:
WPPS5 2 %-F7 E 54-07?: 80501/11:5 RADIATIO. Wa: 5FU.!0;: 0 EGT:.-
WFFSi 2 50-3c7 GE S-02: N0502,0:15 FLOW 150)?!0N 5*uRI:Li CFEFA" '
WCPS$ 2 50-M7 E 54-07? S40507/0755 RADIATI0i. WC SFJ:0.. OFEr%i:0 WEP55 2 50-507 GE 5;-075 340533/05;.: RA:IATIO'. HVA: 5?Lf:2ai CFEG':'
50-577 E 64-0C 6408;1/1835 T011C CAS HVA: EQU;F E T NE:ATI~N W P55 2 W5F55 2 50-577 GE 64-06; S406:3/M:?5II.3 FLOW ISOLATION SFEIOUi CFE%i:3 WPPSS 2 50-3?7 GE 64-093 640624/0200 T0XIC C43 HVAC EQUIPPENT OPERATICG WPPSS 2 50-397 GE 84-092 840824/1759 T0XIC GA5 HVAC EQUIPt1ENT OPEMTIC :
WPPSS 2 50-397 OE 84-098 840904/1855 RADJATION HVAC SFURIOU5 0FFATION ECJIFFEh? OCERA71Ci; WFFSS 2 50-597 GE E4-094 640905/2015 T0XIC GAS HVAC WPPSS 2 50-39'l GE 84-098 840910/2203 GDIATION HVAC SPUR 0'.S OFEFATION WPPSS 2 50-397 CE 84-098 640?17/1305 RADIATION HVAC SPURIOUS OPERATICN WPPSS 2 50-377 E 84-101 64($19/ MISSING LNKNOWN ISOLATION UNNNOWN OPEMTIC'.
WPPSS 2 50-397 GE 84-105 840724/1001 RADIATION HVAC SP'JRIOU$ CPEFATIO*:
SFWIOUS OPERATIO!,
WPPSS 2 50-397 GE 84-105 8409:4/1010 PADIATION HVAC OFFATIG; WPPSS 2 50-397 E 64-009 $40928/ MISSING TEMFERATURi ISOLATION PROCEDURE WPPSS 2 50- 3 7 GE 84-099 640923/M!5 SING TEMFERATJE ISOLATION PROCEDGE OPEG ION PROCEIGE CJERA!!d; WPP53 2 50-577 GE 84-05) S40925/15!0 TEMFERATURE ISOLATION WPFSS 2 50-317 GE 84-102 64';920/0620 T0XIC GA3 HVAC EQUIP S T OFEMil?.
WFPSS 2 50-397 E 64-101 641002/165: UNKNC4'N ISOLATION IN NCWN OFE?ATI?.
WPPS3 2 50-397 GE 84-082 641004/2121 FLOW ISOLATION SPURICUS OFERAi!ON WPPSS 2 50-397 GE 64-107 641002/1215 T0XIC GAS HVAC EQUIFFENT CfEFJ.7 ION OFET67:0';
WPPSS 2 50-397 GE 84-119 641110/1820 FLOW ISOLATION EQUIPMENT WPPS$ 2 50-397 .0E 84-118 641113/0640 LOSS OF PCWER ISOLATION EQUIPMENT FAINIAINANCE WPPSS 2 50-397 CE 84-117 641116/0452 TEPPERATURE ISOLATION PERSONNEL MAINTAINALE WPPSS 2 50-397 GE 84-120 841119/1250 MANUAL HVAC PERSONNEL TESTING 50-397 GE 84-127 841218/0825 LOSS OF POWER ISOLATION PERSONNEL CON 3TRUCTION WPPSS 2 WPPSS 2 50-397 CE 84-128 841224/1300 T0XIC GA5 HVAC COMBINATION OFE%TICN 50-02? WEST 84-012 640712/0805 REAFTOR TRIP POWER UNKNOWN OPERATION YANVEE R0WE OPERA 7 ION YArJEE R0WE 50-02) WEST 64-014 840314/2254 FRESSME MISCELLANE04E EQUIPMENT YAWEE R0WE 50-029 WEST 84-014 640S14/2310 FRESSWE MISCELLANEOUS EQUIFFENT OFERAT:0N ZION 2 50-304 WEST 84-030 641210/MI551NG MISSING ISOLATION COMBINATION TESTING 93
. r s -
g-Table A.7 ESF Actuations - Safety Injection Events (Actual Injection) 2nd Half 1984 NSSS Report Event ECCS Reactor Injection Power Actuation Description of Event Unit Vendor Number Date/ Time Equipment Level iype A 1. Oyster Creek GE 84-025 841029/0203 Core Spray 0% False During calibration of reactor level instrumentation, step in procedure was omitted, causing core spray injection for about 0.5 minutes on low reactor level.
- 2. Quad Cities 1 GE 84-013 840808/2206 Low Pressure 0% False Operator error during surveillance ECCS testing. Vessel level instrument line was improperly backfilled, causing low level, core spray and LPCI* actuation, and containment isolation.
- 3. Palisades CE 84-009 840704/0940 SI Signal; 0% False Inadequate procedure caused Charging Pumps maintenance technician to remove lead, causing loss of safety injection block signal. Charging pumps injected 95% of boron tank contents.
I ,
I 3
. r a
Table A.7 (Cont'd)
ESF Actuations - Safety Injection Events (Actual Injection) 2nd Half of 1984 NSSS Report Event ECCS Reactor Injection Power Actuation Description of Event U$ Unit Vendor Number Date/ Time Equipment Level Type
- 4. Diablo Canyon 1 W 84-022 840728/0709 High Pressure 0% False High steam flow channels were Injection in test; water addition to steam generators caused low RCS temperature, resulting in high pressure injection of about 2000 gallons. ,
- 5. Diablo Canyon 1 W 84-030 841124/1616 Boron Injection 21% Valid Operator failed to reset steam Tank Non-Design dump valve pressure controller Basis .
when starting turbine, causing safety injection signal and boron injection tank injection on low Tave and high steam flow signal.
- 6. Peach Bottom 3 GE 84-011 840821/1401 High Pressure 100% Valid, Feedwater " control system failure Coolant Injection Non-Design caused low reactor level, resulting Basis in high pressure coolant injection system injection to restore level.
l
_ A
E Table A.7 (Cont'd)
ESF Actuations - Safety Injection Events (Actual Injection) 2nd Half of 1984 Report Event ECCS ' Reactor NSSS Actuation Description of Event Injection Power Equipment Level Type Unit Vendor Number Date/ Time High Head 66% Valid, During test, depressurization
- 7. Salen 2 W 84-018 840725/1320 resulted from in advertent Safefy Injection Design Basis opening and failure to reseat of relief valve. Decrease in RCS pressure resulted in high head injection.
840814/1529 Charging Pumps 100K False Failure of inverter caused
- 8. Cook 1 W 84-018 false signals, resulting in safety injection through boron injection tank by charging Pumps.
Charging Pumps 73% Valid, Partially stuck open pressurizer
- 9. Cook 2 W 84-029 841111/0737 Non-Design pressure decrease, resulting in e Basis safety injection (centrifugal
- charging pumps).
False HPCI nuto started and injected 84-013 840729/- High Pressure 96%
because half of logic had
- 10. Hatch 1 GE Coolant Injection short circuit and other half was being tested.
Valid, Low reactor water level following 84-026 840918/1039 High Pressore 89%
reactor scram from 89% power. Scram
- 11. Brunswick 1 GE Coolant Injection Non-Design Basis caused by procedure deficiency during .
maintenance which allowed Iffting of leads, causing feedwater transient.
9 O
5
. Table A.7 (Cont'd)
ESF Actuations - Safety Injection Events (Actual Injection)
Report Event ECCS Reactor MSSS Actuation Description of Event Injection Power Equipment Level Type Unit Vendor Neber Date/ Time Valid Operation SI-block handswitches
- 12. Sequoyah 2 W 84-020 841216/0826 Safety Injection GK resulted in unblock and injection via Boron Injec- Non-Design Basis on low pressurizer pressure.
tion Tank Valid Low reactor water level following 84-042 841123/0640 High Pressure 81%
reactor scram from 81% power.
- 13. Duane Arnold GE Coolant Injection Non-Design J
Basis scram caused by Icss of non-vital bus. Spurious fire protection system actuation caused spray onto transformer. ,
Valid, Low reactor water level following
Coolant Injection Non-Design e Basis Scram caused by condensate bypass
" flow controller malfunctioning causing loss of feedwater flow.
Gi False Relay that should have been energized W 84-010 841101/1128 Safety Injection was in de-energized state, resulting
- 15. North Anna 2 Accumulators in accumulator isolation valves opening and partial accumulator injection.
False Personnel error resulted in improper 84-016 840815/1a30 Core Spray GE valve alignment during test.
- 16. Hatch 2 GE High Pressure This resulted in a pressure differential Cociant Injection that the reactor water level pressure transmitter sensed as a LOCA signal. This signal caused initiation of core spray pumps and high pressure coolantinjection.
l .D
, e ,
e s
i Table A.7 (Cont'd)
ESF Actuations - Safety injection Events (Actual Injection) 2nd Half 1984 NSSS Report Event ECCS Reactor l Injection . Power Actuation Description of Event Unit Vendor Number Date/ Time Equipment Level Type
- 17. Susquehanna 1 GE 84-029 o, 840703/1412 High Pressure 100% Valid Low reactor water level following Coolant Injection Non-Design reactor scram from 100% power.
Basis Scram caused by lightning strike which caused loss of offsite power.
- 18. Grand Gulf 1 GE 84-053 841129/0055 *High Pressure 53% Valid, Defective test equipment and an Core Spray Non-Design incorrect connection caused reactor Basis level transient, causing high pressure core spray initiation.
- 19. Byron 1 W 84-017 841123/2145 Charging 05 Valid, Operator placed SI Block switch in Pump Non-Design wrong position, causing charging
, Basis pump injection on steamline low pressure.
- 20. Callaway 1 W 84-028 840813/1225 Boron False 50-483 OX During survelliance test, safety Injection injection jnitiated due to Tank pressurizer low pressure signal.
i One loop of logic was in undetected trip mode and other loop was placed in test, resulting in a pressurizer low pressure SI signal, actuating ECCS and causing a boron injection tank discharge.
1 J
o -
Table A.8 ESF Actuations -
Associated Failures 2nd Half 1984 Report Event Unit Docket Number Date Problem Reason
- 1) Yankee Rowe 029 014 8/14/84 Water sprayed into SI accumulator room Cap blew off unused line on Accumulator Safety l Valve Header l 2) 015 9/5/84 Diesel Generator output breaker tripped Response time of governor was too slow l l
l 3) 017 11/12/84 Poiler feed pump failed to trip automati- Steam pressure sensing line deterioration and l l cally pressure switch failure ;
i 1
l 4) San Onofre 1 206 015 11/16/84 R. C. pumps did not trip; annunciator Deposit on contact surfaces of switch; unknown l failed. l l
- 5) Haddam Neck 213 014 8/24/84 One DG breaker did not close automatically Not identified
- 6) Oyster Creek 219 021 9/25/84 Diesel Generator fast start locked out Not stated 1
Control rod not inserted; RCIC overspeed Not determined (scram discharge riser valve
- 7) Quad Cities 2 265 010 10/25/84 trip was closed); Not determined
- 8) Indian Point 3 286 015 11/16/84 Several DG output breakers failed to operate Control power fuses failed
- 9) - Pilgrim 1 293 020 12/25/84 LPCI injection valves would not close Faultycontactsincontroiswitch; stiff grease in motor operator
- 10) Browns Ferry 3 296 009 9/15/84 Instrument line excess flow check valves Valves required dissassembly and cleaning leaked
- 11) Cooper 298 010 8/8/84 Startup transformer breakers did not auto Unknown operate
- 12) Cook 1 315 018 8/14/84 Control rod indication out Unknown i e _ .- - .
o
- e .
! Table A.8 (Cont'd)
ESF Actuations Associated Failures 2nd Half 1984 Report Event Unit Docket Number Date Problee Reason
- 13) Cook 2 316 020 8/5/84 AFW flow control valves did not operate Not stated properly Hatch 1 ff14) 321 015 8/3/84 Safety relief valve did not operate Low setpoint
- 15) 029 12/24/84 Inboard isolation valve did not isolate Not stated e
- 16) 029 12/24/84 Inboard isolation valve did not isolate " +"
- 17) 029 12/25/84 Inboard isolation valve did not operate " "
- 18) Brunswick 2 324 012 10/24/84 Safety / Relief valve indication did not Chip connections in logic module required isolate cleaning
- 19) Brun: wick 1 325 014 8/1/84 Inboard MSIV did not cicse Failure of solenoid pilot valve
- 20) 016 8/7/84 Interrupted power to RHR, Service Water, Inappropriate / degraded voltage relay CR0 components protective devices
- 21) 025 9/10/84 Safety / relief valve sonic position Setpoint ,
indication did not function .
- 22) Sequoyah 1 327 065 10/9/84 Aux. building isolation fans restarted Radiation monitor spike after trip
- 23) Duane Arnold 331 028 ' 7/14/84 HPCI inboard steam supply valve closed Unknown
- 24) 042 11/23/84 Emergency notification system lost Loss of nonvital power
)
~_ _ _ _ _ _ __
D e
- a Table A.8 (Cont'd)
ESF Actuations Associated Failures 2nd Half 1984 Report Event Unit Docket Number Date Problem Reason
- 25) Fitzpatrick 333 023 11/4/84 RCIC failed to operate Shorted out steam supply valve motor e-=
0
" 26) Beaver Valley 334 012 10/18/84 Automatic bus transfer breakers Unknown did not open on undervoltage
- 27) Millstone 2 336 012 11/28/84 Main feedwater check valve failed Unknown to seat
- 28) No. Anna 1 338 019 11/14/84 AFW pump did not auto start; Loss of vital bus Containment isolation valve did not close; source range excore detectors had to be manually reinstated.
- 29) Davis-Besse 1 345 013 9/11/84 Atmospheric vent valve did not Air control solenoids need replacement or refur-fully reseat bishment
- 30) Limerick 1 352 030 12/10/84 RWCU suction valve was blocked Blocked in open position (allowable in the operating open condition existing at the time of the event)
- 31) San Onofre 2 361 081 12/23/84 Boric acid makeup pump trip Overcurrent/ Unknown
- 32) Hatch 2 366 021 9/21/84 RCIC tripped three times Unknown
- 34) McGuire 2 370 028 11/13/84 UHI isolation valve failed fully Check valve did not operate properly closed
- 35) LaSalle 1 373 047 8/7/a.4 Precoat tank overflow; personnel Unknown contamination ,
Y
7, ,
. . . . . , -m . ._ .
,I ,
Table A.8 (Cont'd)
.
- ESF Actuations Associated Failures 1
2nd Half 1984 Report Event Unit Docket Number Date 1
Problem Reason
- 36) LaSalle 1 373 076 11/11/84 RWCU isolated on high differential Abnormel fan Ifneup air temperature.
g 37) Susquehanna 1 387 029 7/3/84 Loss of feedwater turbines Unknown
- 38) St. Lucie 2 389 011 11/21/84 Auxiliary feed pump trip Overspeed
- 39) 016 12/19/84 Reactor coolant pump seals damaged Loss of power (breaker did not open}
- 40) WPPSS - 2 397 081 8/18/84 CR emergency flitration unit auto Spike on radiation monitor started
- 41) Lacrosse 409 011 7/16/84 'B' DG output breaker did not close; SI pump would not start Blown fuse; bus undervoltage auxiliary relay
- 42) Grand Gulf 1 416 045 10/14/84 Multiple equipment trips Adverse weather caused voltage transients
- 43) "
053 11/29/84~ RCIC turbine trip Undetermined
- 44) Callaway 483 046 10/5/84 Main feedwater isolation valve did not Loss of hydraulic fluid -Q rigg failure close
- 45) 052 10/16/84 Unexpected rod movement loss of power to control data cabinets
_ _____ _ _ __ __ _ - - - - ~