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{{Adams | {{Adams | ||
| number = | | number = ML20214K973 | ||
| issue date = 08/ | | issue date = 08/12/1986 | ||
| title = | | title = SALP Rept 50-312/86-29 for June 1985 - June 1986 | ||
| author name = | | author name = | ||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) | ||
| addressee name = | | addressee name = | ||
| addressee affiliation = | | addressee affiliation = | ||
| docket = | | docket = 05000312 | ||
| license number = | | license number = | ||
| contact person = | | contact person = | ||
| | | document report number = 50-312-86-29, NUDOCS 8612020532 | ||
| package number = ML20214K964 | |||
| package number = | | document type = SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | ||
| document type = | | page count = 55 | ||
| page count = | |||
}} | }} | ||
Line 20: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:' | ||
--' y, ' ', | |||
~ | |||
- | |||
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f., ,- . | |||
.,. | |||
> | |||
' ' | |||
* | |||
w , 1, 5 | |||
^- | |||
. _ | |||
. S. NUCLEAR REGULATORY C0fetISSION-i; REGION V | |||
. J SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE FOR SACRACMENTO MUNICIPAL UTILITY DISTRICT RANCHO SEC0 NUCLEAR GENERATING STATION | |||
! | |||
l REPORT NO. 50-312/86-29 EVALUATION PERIOD: 06/01/85- 06/30/86 | |||
;. ASSESSMENT CONOUCTED: AUGUST 12, 1986 | |||
, | |||
. | |||
8612020532 861114 PDR ADOCK 05000312 o PDR I | |||
[. ' | |||
~ | |||
- . . - _ - - - . - _ -__ - | |||
f -r | |||
- . | |||
' | |||
& | |||
P | |||
. | |||
SUMMARY (06/01/85-06/30/86) | |||
Inspections' Conducted Enforcement Items Insp.** Percent Severity Level ***- | |||
Function Area Hours of Effort I II III IV V Dev. Pend * ' Plant Operations 2468 46 1 1 1 8 Radiological 317 6 2 1 4 7 Controls . Maintenance 211 4 1 1 Surveillance - 287 5 1 ' Fire Protection . 184 3 Emergency-Preparedness 260 5 5 | |||
' Security and | |||
> Safeguards 545 10 2 1 | |||
' Outages -' | |||
324 6 QualityProgr$ms/ 531 10 1 2 1 1 Administrative 1 Licensing Activities NA NA 1 Training - | |||
33 1 1 Engineering and Construction 192 4 1 1 1 Totals 5352 100 0 0 3 7 5 6 23 | |||
! | |||
* Pending final escalated enforcement actio ** Allocations of inspection hours vs. functional areas are approximations based upon inspection report data, and include onsite and in-office inspection effort. Does not include PAT /IE inspection hours or SALP preparation hours. | |||
' | |||
*** Severity levels are in accordance with NRC Enforcement Policy. (10 CFR Part 2, Appendix C). | |||
. | |||
Data compiled from Inspection Report Nos. 85-16 through 86-23, excluding 85-23, | |||
. covering inspections performed during the assessment period 06/01/85 - 06/30/8 . | |||
, , _ - _ _ | |||
.-. . .- | |||
y- -r | |||
.. | |||
.. | |||
-47 | |||
, | |||
. | |||
TABLE 2 | |||
' | |||
Rancho Seco Enforcement Items 06/01/85 - 06/31/86 (85-19 through 86-23) | |||
Inspection Severity Functional Report N Subjec Leve Area 85-19 Failure to establish design _and III 9 installation control measures to ensure integrity of nitrogen supply and vent header syste Failure to provide: adequate lighting IV- 7 level Failure to follow radiation procedures V 2 for carrying pocket dosimeter and dressing in' protective-clothing in controlled area > | |||
Failure to comply with technical speci- IV -2 fication required verification of flow rates during calibration of stack radiation monitor Failure to provide PASS. system training D 2 at committed frequenc Failure to provide committed schedule for D 2 design / procurement of PASS sample shields'. | |||
Fa'ilure to provide committed PASS proce- D 2 | |||
.., dures for recovery of particulate and iodine media under'high sample activity condition Failure to complete committed PASS remote D 2 adjustment capability for water / nitrogen | |||
~ | |||
i, manifold and ion chromatograp ., | |||
85'-29 . Failure to adequately search hand-carried III 7 | |||
+ | |||
package. | |||
. | |||
85-30 Failure to provide approved procedure for V 4 | |||
, calibration.of power range instrument (gain adjustment). | |||
Failure to comply with Technical Specifi- IV 1 cation cooldown rate of 100*F/hr during October 2, 1985 transien h y? ~ ~ ~ | |||
_ | |||
"~ | |||
;*[a . 48 | |||
.b TABLE 2 (continued) | |||
. ' Rancho Seco Enforcement Items | |||
.06/01/85 --06/31/86 (85-19 through 86-23) | |||
' | |||
.. Inspection Severity Functional | |||
- Report N Subject Level Area 1n '85-34 Failure to follow access control procedure (a) 7 86-04- Failure'to annotate computer printout (b) 7 regarding alarm response and assessmen i Degraded vital: area barrie (b) 7 Security officer found asleep in' degraded .( b)' 7 vital area barrier compensatory pos Compensatory measures failure _ (b) 7 Failure-to properly escort' visitors an (b) 7 tailgating into vital areas ~. | |||
[- _ Failure to search vehicl (b) 7 86-05 Failure to perform 10 CFR 50.59 safety IV 2 review.of new building constructed and | |||
'' | |||
% - u' sed to process radwast Failure to fol' low procedures to make | |||
' | |||
-86-0 P 6 | |||
^ | |||
- in-plant announcements and provide complete. initial notification information-to localJgovernment agencies. | |||
,. | |||
- | |||
' Failure to follow procedures to make P 6 | |||
. | |||
, , | |||
follow-sp notifications to local govern-ment-agencie Failure to maintain emergency plan P 2 | |||
- | |||
implementing procedure with current radiation monitor setpoint ' | |||
Failure to implement emergency and P 2 | |||
' | |||
annunciator. procedure requirements to obtain samples, and evacuate the | |||
. auxiliary building and wear respirator (a) This violation was combined with the violation in inspection report 85-29 in the aggregate as a Severity Level III proble (b) All 86-04 violations.were listed in the aggregate as a Severity Level III proble u | |||
., , | |||
" | |||
> > | |||
~ 4 _ | |||
- | |||
' TABLE 2 (continued) | |||
, Rancho'Seco Enforcement. Items 06/01/85 - 06/31/86 (85-19 through 86-23) | |||
Inspection- Severity Functional Report N . Subject Level Area 86-07 Improper. termination of cable shield wir D 12 Failure to maintain plant cooldown rate P 1 within Technical. Specification limit Failure to corre.ct excessive flow. rate P 9 | |||
. of;the Emergency. Filtration System for | |||
- | |||
th~e CR/TS,C subsequent to surveillance tes > | |||
, | |||
_ | |||
.. | |||
- Failure to establish written procedure P 1 for securing HPI following safety feature actuati~o Failure'to establish written procedure P 1 | |||
, | |||
for loss, of power to the IC Failure to establish. written procedure P 1- | |||
, for manually operated ATW system valv failureJto follow procedur.c to stop P 1 ATW pump Failure to establish written procedure P 1 for emergency manual operation of ATW control valv _ | |||
Failure to provide procedures for P 1 certain abnormal plant condition Failure to properly implement emergency P 1 procedure Lack of procedure for crimping too P 3 | |||
. | |||
-86-08 Failure to properly control calibrated V 3 I | |||
tools and a volt. mete Failure to perform 10 CFR 50.59 evalua- IV 9 tion on SA-516 plate material. | |||
' | |||
86-14' Failure to insure emergency plan P 6 | |||
. training is provided to all appropriate-personnel. | |||
! | |||
l | |||
! | |||
} | |||
, | |||
,r, c- +v-w,- | |||
_ | |||
y , | |||
< | |||
. | |||
- > | |||
., - | |||
-- .. .. . . . . | |||
,.. | |||
.. - | |||
, , | |||
- | |||
, | |||
' TABLE 2 (continued). | |||
Rancho Seco Enforcement Items 06/01/85 - 06/31/86- | |||
, | |||
(85-19 through 86-23) | |||
; Inspection Severity Functional Report No. 8 | |||
&ubject Level- Area 86-14- Failure to maintain emergency implementing .P 6 | |||
. procedures documen Failure to follow 10 CFR 50.54(q) require- P .6 ment Failure to comply with Technical Specifi- P 2 cations, Table 4.21-1, Footnote'(c). | |||
Failure to establish a surveillance P 2 program pursuant to 10 CFR Part 50, Appendix I, Section IV . Failure to limit the. quarterly loss P 2 commitments to-a member of the general public pursuant to Technical Specifi-cations, Section 3.1. Failure to perform safety evaluations fo P 2 temporary . changes to radwaste processing systems pursuant to 10 CFR Part 50.5 Failure to develop and maintain procedures P 2-for controlling the transfer of . radio- | |||
~ | |||
activity . contaminated water pursuant to | |||
" Technical Specifications, Section ;86-18' Failure to review modification by'PR IV 9 Fa'ilure to: hang abnormal tag per V- 9 | |||
, | |||
- | |||
requiremen ' | |||
* | |||
86-21 Failure to maintain continuous cleaning D | |||
- | |||
,' , ' of nuclear service raw wate iFailure'to store quality record in the IV 9 g -vaul . | |||
. | |||
!' * Severity Level P -;Pending final escalated enforcement actio ' | |||
I s | |||
, | |||
[ | |||
; | |||
' | |||
l l | |||
. | |||
F ,;p>' , | |||
4, | |||
' | |||
- | |||
' | |||
. | |||
Table 3 SYNOPSIS OF LICEESEE EVENT REPORTS Functional- SALP Cause Code * | |||
. Area A _ | |||
B C D E X * | |||
_ | |||
Totals Plant Operations 3 1 0 5 0 1 10 Rad. Controls 1 0 0 0 0 0 1 Maintenance 2- 1 0 1 1 0 5 | |||
~ Surveillance 1 0 0 2 0 0 3 Fire Protection 1 0 0 1 0 0 2 Energency Preparedness 0 0 0 0 0 0 0 Safeguards 0 0 0 0 0 0 0 | |||
- Refueling 0 0 0 0 0 0 0- Quality Programs 1 5 0 0 0 0 6 and Administrative Controls Affecting Safety 1 Licensing 0 0 0 0 0 0 0 , | |||
1 Training H 1 0 0 0 _0 0 1 Effectiveness J | |||
s | |||
. ' 1 Engineering and - | |||
2 5 0 1 0 0 8 | |||
- | |||
, | |||
Construction | |||
, , | |||
. Totals 12 12 0 10 1 1 36 e , , | |||
' | |||
m | |||
+- | |||
A - Personnel Error ( ' | |||
_B Design, Manufacturing or Installation Error C - External Cause l D - Defective Procedures | |||
'- | |||
E - Component Failure-X - Other | |||
* - Cause not yet determined l' | |||
' | |||
The:.above data are based upon LERs 85-06 through 86-1 Three of these LERs reported two separate events which were assigned to separate functional areas l | |||
and cause codes. | |||
i. - | |||
L | |||
FJ;.:-51:r . | |||
i-o ? ' ' | |||
52~ | |||
_ | |||
TABLE 4 | |||
. | |||
SUMMARY OF LERs (LER 85-06 through LER 86-10)' | |||
Functional Cause LER N l Areas Code Subject | |||
.85-0 B CRD Refurbished Breaker Failed to'Open on Undervoltage.During Bench Test 85-07' 4 D 4160 V.' Bus Undervoltage Relay'Out of Calibration 85-08 4 A Fire Barrier Surveillance Scheduling Error | |||
: < | |||
. | |||
. . | |||
85-09 12 B Diesel Generator Control Circuitry Fails to Follow Normal Shutdown Sequence ' | |||
85-Id' 12 ~ A ' Reactor Coolant System Nonisolatable Leak at | |||
, | |||
, 0TSG . | |||
. | |||
High Point' Vent; Missing Pipe Supports | |||
' | |||
85-11 i D Reactor Trip From Unbypassed Shutdown High | |||
. | |||
, | |||
Pressure Trip Logic 85-12 El A Imp.roperly Latched Airlock. Door Compromises a Containment Integrity 85-13 'l B Diesel Generator Starts from Transient | |||
- | |||
Overvoltage Condition 85-14 9 B Non-Class IE Breaker Installed in Class IE System 85-15 3,9 A D/G Started Inadvertently and Loose Connections Prevent Circuit Breaker Closure for Essential | |||
' ~ HVAC Found 85-16 1 X Spurious Closure of DHR Suction Isolation Valve 85-17 9,12 B Seal Plate Omission Results in HEPA Filter Bank Leak f 85-18 1 D Diesel Generator Output Breaker Lockout 85-19 1 .D Excess Cooldown Rate After Reactor Trip Due to Open Feedwater Heater Relief Valves-85-20 12 B Essential HVAC Flow Controller Design Error Prevents Automatic Control After Return of Power | |||
, | |||
. -. - - - - . | |||
, | |||
, | |||
;o: | |||
- | |||
, | |||
- | |||
TABLE 4 (continued) | |||
SUMMARY OF LER ' | |||
(LER 85-06 through LER 86-10) _ | |||
Functio'nal Cause LER N sArean Code Subject | |||
.85-21 3 Diesel-Generator Auto-Start Due to Lifted LeadL Error:by Maintenance Personnel 85-22- l' 'A Pressurizer. Liquid Sample Valve;Found Open in ) | |||
Violation of Tag-Out' Controls j l | |||
l | |||
' | |||
85-23 1 E Reactor Trip from Pressure Transient Induced by ICS Relay Resistance, Operator Error with Manual | |||
. | |||
. | |||
Feedwater Control with Stuck Recorder Pen f | |||
P> ' | |||
85-24 3 E Reactor Shutdown Due to Packing Glarid Leak' age | |||
, of Pressurizer Liquid Sample Inboard Isolaticn -l l Valve | |||
1 | |||
' | |||
85-25 ~1 A Reactor Trip and Overcooling from Loss of ICS 3 D Power Induced Transient' | |||
, | |||
86-01 3,9- B EDG "A" and "B" Declared Inoperable During Cold -l | |||
, Shutdown ' | |||
86-02 12 B Erosion and Leaks in DHR Pump Casing Drain Line | |||
: 86-03 2 A Containment Purge Unmonitored 1 86-04 ^ 5 A Missed Fire Watch | |||
< | |||
86-05 9 | |||
, | |||
B Seismic Spacing of Nuclear Service Batteries i | |||
' | |||
' | |||
86-06 '4 D Fire Protection System Overdue for Surveillance 86-0 B ~ Control Room Emergency HVAC High Flow Condition l 86108 5 D -Failure to Institute Fire Watch for Breached | |||
- | |||
Penetration 1 | |||
: . | |||
: | |||
' - | |||
86-09' 1 A,D < Spurious ESFS Actuation a, ; | |||
86-10' 12 . A,D = Redundant Cabling in Same Fire Area j i | |||
I | |||
! | |||
' | |||
. | |||
. | |||
. | |||
i ; | |||
. | |||
. | |||
}} | }} |
Latest revision as of 16:03, 18 December 2021
ML20214K973 | |
Person / Time | |
---|---|
Site: | Rancho Seco |
Issue date: | 08/12/1986 |
From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
To: | |
Shared Package | |
ML20214K964 | List: |
References | |
50-312-86-29, NUDOCS 8612020532 | |
Download: ML20214K973 (55) | |
Text
'
--' y, ' ',
~
-
'
f., ,- .
.,.
>
' '
w , 1, 5
^-
. _
. S. NUCLEAR REGULATORY C0fetISSION-i; REGION V
. J SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE FOR SACRACMENTO MUNICIPAL UTILITY DISTRICT RANCHO SEC0 NUCLEAR GENERATING STATION
!
l REPORT NO. 50-312/86-29 EVALUATION PERIOD: 06/01/85- 06/30/86
- . ASSESSMENT CONOUCTED
- AUGUST 12, 1986
,
.
8612020532 861114 PDR ADOCK 05000312 o PDR I
[. '
~
- . . - _ - - - . - _ -__ -
f -r
- .
'
&
P
.
SUMMARY (06/01/85-06/30/86)
Inspections' Conducted Enforcement Items Insp.** Percent Severity Level ***-
Function Area Hours of Effort I II III IV V Dev. Pend * ' Plant Operations 2468 46 1 1 1 8 Radiological 317 6 2 1 4 7 Controls . Maintenance 211 4 1 1 Surveillance - 287 5 1 ' Fire Protection . 184 3 Emergency-Preparedness 260 5 5
' Security and
> Safeguards 545 10 2 1
' Outages -'
324 6 QualityProgr$ms/ 531 10 1 2 1 1 Administrative 1 Licensing Activities NA NA 1 Training -
33 1 1 Engineering and Construction 192 4 1 1 1 Totals 5352 100 0 0 3 7 5 6 23
!
- Pending final escalated enforcement actio ** Allocations of inspection hours vs. functional areas are approximations based upon inspection report data, and include onsite and in-office inspection effort. Does not include PAT /IE inspection hours or SALP preparation hours.
'
- Severity levels are in accordance with NRC Enforcement Policy. (10 CFR Part 2, Appendix C).
.
Data compiled from Inspection Report Nos. 85-16 through 86-23, excluding 85-23,
. covering inspections performed during the assessment period 06/01/85 - 06/30/8 .
, , _ - _ _
.-. . .-
y- -r
..
..
-47
,
.
TABLE 2
'
Rancho Seco Enforcement Items 06/01/85 - 06/31/86 (85-19 through 86-23)
Inspection Severity Functional Report N Subjec Leve Area 85-19 Failure to establish design _and III 9 installation control measures to ensure integrity of nitrogen supply and vent header syste Failure to provide: adequate lighting IV- 7 level Failure to follow radiation procedures V 2 for carrying pocket dosimeter and dressing in' protective-clothing in controlled area >
Failure to comply with technical speci- IV -2 fication required verification of flow rates during calibration of stack radiation monitor Failure to provide PASS. system training D 2 at committed frequenc Failure to provide committed schedule for D 2 design / procurement of PASS sample shields'.
Fa'ilure to provide committed PASS proce- D 2
.., dures for recovery of particulate and iodine media under'high sample activity condition Failure to complete committed PASS remote D 2 adjustment capability for water / nitrogen
~
i, manifold and ion chromatograp .,
85'-29 . Failure to adequately search hand-carried III 7
+
package.
.
85-30 Failure to provide approved procedure for V 4
, calibration.of power range instrument (gain adjustment).
Failure to comply with Technical Specifi- IV 1 cation cooldown rate of 100*F/hr during October 2, 1985 transien h y? ~ ~ ~
_
"~
- [a . 48
.b TABLE 2 (continued)
. ' Rancho Seco Enforcement Items
.06/01/85 --06/31/86 (85-19 through 86-23)
'
.. Inspection Severity Functional
- Report N Subject Level Area 1n '85-34 Failure to follow access control procedure (a) 7 86-04- Failure'to annotate computer printout (b) 7 regarding alarm response and assessmen i Degraded vital: area barrie (b) 7 Security officer found asleep in' degraded .( b)' 7 vital area barrier compensatory pos Compensatory measures failure _ (b) 7 Failure-to properly escort' visitors an (b) 7 tailgating into vital areas ~.
[- _ Failure to search vehicl (b) 7 86-05 Failure to perform 10 CFR 50.59 safety IV 2 review.of new building constructed and
% - u' sed to process radwast Failure to fol' low procedures to make
'
-86-0 P 6
^
- in-plant announcements and provide complete. initial notification information-to localJgovernment agencies.
,.
-
' Failure to follow procedures to make P 6
.
, ,
follow-sp notifications to local govern-ment-agencie Failure to maintain emergency plan P 2
-
implementing procedure with current radiation monitor setpoint '
Failure to implement emergency and P 2
'
annunciator. procedure requirements to obtain samples, and evacuate the
. auxiliary building and wear respirator (a) This violation was combined with the violation in inspection report 85-29 in the aggregate as a Severity Level III proble (b) All 86-04 violations.were listed in the aggregate as a Severity Level III proble u
., ,
"
> >
~ 4 _
-
' TABLE 2 (continued)
, Rancho'Seco Enforcement. Items 06/01/85 - 06/31/86 (85-19 through 86-23)
Inspection- Severity Functional Report N . Subject Level Area 86-07 Improper. termination of cable shield wir D 12 Failure to maintain plant cooldown rate P 1 within Technical. Specification limit Failure to corre.ct excessive flow. rate P 9
. of;the Emergency. Filtration System for
-
th~e CR/TS,C subsequent to surveillance tes >
,
_
..
- Failure to establish written procedure P 1 for securing HPI following safety feature actuati~o Failure'to establish written procedure P 1
,
for loss, of power to the IC Failure to establish. written procedure P 1-
, for manually operated ATW system valv failureJto follow procedur.c to stop P 1 ATW pump Failure to establish written procedure P 1 for emergency manual operation of ATW control valv _
Failure to provide procedures for P 1 certain abnormal plant condition Failure to properly implement emergency P 1 procedure Lack of procedure for crimping too P 3
.
-86-08 Failure to properly control calibrated V 3 I
tools and a volt. mete Failure to perform 10 CFR 50.59 evalua- IV 9 tion on SA-516 plate material.
'
86-14' Failure to insure emergency plan P 6
. training is provided to all appropriate-personnel.
!
l
!
}
,
,r, c- +v-w,-
_
y ,
<
.
- >
., -
-- .. .. . . . .
,..
.. -
, ,
-
,
' TABLE 2 (continued).
Rancho Seco Enforcement Items 06/01/85 - 06/31/86-
,
(85-19 through 86-23)
- Inspection Severity Functional Report No. 8
&ubject Level- Area 86-14- Failure to maintain emergency implementing .P 6
. procedures documen Failure to follow 10 CFR 50.54(q) require- P .6 ment Failure to comply with Technical Specifi- P 2 cations, Table 4.21-1, Footnote'(c).
Failure to establish a surveillance P 2 program pursuant to 10 CFR Part 50, Appendix I, Section IV . Failure to limit the. quarterly loss P 2 commitments to-a member of the general public pursuant to Technical Specifi-cations, Section 3.1. Failure to perform safety evaluations fo P 2 temporary . changes to radwaste processing systems pursuant to 10 CFR Part 50.5 Failure to develop and maintain procedures P 2-for controlling the transfer of . radio-
~
activity . contaminated water pursuant to
" Technical Specifications, Section ;86-18' Failure to review modification by'PR IV 9 Fa'ilure to: hang abnormal tag per V- 9
,
-
requiremen '
86-21 Failure to maintain continuous cleaning D
-
,' , ' of nuclear service raw wate iFailure'to store quality record in the IV 9 g -vaul .
.
!' * Severity Level P -;Pending final escalated enforcement actio '
I s
,
[
'
l l
.
F ,;p>' ,
4,
'
-
'
.
Table 3 SYNOPSIS OF LICEESEE EVENT REPORTS Functional- SALP Cause Code *
. Area A _
B C D E X *
_
Totals Plant Operations 3 1 0 5 0 1 10 Rad. Controls 1 0 0 0 0 0 1 Maintenance 2- 1 0 1 1 0 5
~ Surveillance 1 0 0 2 0 0 3 Fire Protection 1 0 0 1 0 0 2 Energency Preparedness 0 0 0 0 0 0 0 Safeguards 0 0 0 0 0 0 0
- Refueling 0 0 0 0 0 0 0- Quality Programs 1 5 0 0 0 0 6 and Administrative Controls Affecting Safety 1 Licensing 0 0 0 0 0 0 0 ,
1 Training H 1 0 0 0 _0 0 1 Effectiveness J
s
. ' 1 Engineering and -
2 5 0 1 0 0 8
-
,
Construction
, ,
. Totals 12 12 0 10 1 1 36 e , ,
'
m
+-
A - Personnel Error ( '
_B Design, Manufacturing or Installation Error C - External Cause l D - Defective Procedures
'-
E - Component Failure-X - Other
- - Cause not yet determined l'
'
The:.above data are based upon LERs 85-06 through 86-1 Three of these LERs reported two separate events which were assigned to separate functional areas l
and cause codes.
i. -
L
FJ;.:-51:r .
i-o ? ' '
52~
_
TABLE 4
.
SUMMARY OF LERs (LER 85-06 through LER 86-10)'
Functional Cause LER N l Areas Code Subject
.85-0 B CRD Refurbished Breaker Failed to'Open on Undervoltage.During Bench Test 85-07' 4 D 4160 V.' Bus Undervoltage Relay'Out of Calibration 85-08 4 A Fire Barrier Surveillance Scheduling Error
- <
.
. .
85-09 12 B Diesel Generator Control Circuitry Fails to Follow Normal Shutdown Sequence '
85-Id' 12 ~ A ' Reactor Coolant System Nonisolatable Leak at
,
, 0TSG .
.
High Point' Vent; Missing Pipe Supports
'
85-11 i D Reactor Trip From Unbypassed Shutdown High
.
,
Pressure Trip Logic 85-12 El A Imp.roperly Latched Airlock. Door Compromises a Containment Integrity 85-13 'l B Diesel Generator Starts from Transient
-
Overvoltage Condition 85-14 9 B Non-Class IE Breaker Installed in Class IE System 85-15 3,9 A D/G Started Inadvertently and Loose Connections Prevent Circuit Breaker Closure for Essential
' ~ HVAC Found 85-16 1 X Spurious Closure of DHR Suction Isolation Valve 85-17 9,12 B Seal Plate Omission Results in HEPA Filter Bank Leak f 85-18 1 D Diesel Generator Output Breaker Lockout 85-19 1 .D Excess Cooldown Rate After Reactor Trip Due to Open Feedwater Heater Relief Valves-85-20 12 B Essential HVAC Flow Controller Design Error Prevents Automatic Control After Return of Power
,
. -. - - - - .
,
,
- o
-
,
-
TABLE 4 (continued)
SUMMARY OF LER '
(LER 85-06 through LER 86-10) _
Functio'nal Cause LER N sArean Code Subject
.85-21 3 Diesel-Generator Auto-Start Due to Lifted LeadL Error:by Maintenance Personnel 85-22- l' 'A Pressurizer. Liquid Sample Valve;Found Open in )
Violation of Tag-Out' Controls j l
l
'
85-23 1 E Reactor Trip from Pressure Transient Induced by ICS Relay Resistance, Operator Error with Manual
.
.
Feedwater Control with Stuck Recorder Pen f
P> '
85-24 3 E Reactor Shutdown Due to Packing Glarid Leak' age
, of Pressurizer Liquid Sample Inboard Isolaticn -l l Valve
1
'
85-25 ~1 A Reactor Trip and Overcooling from Loss of ICS 3 D Power Induced Transient'
,
86-01 3,9- B EDG "A" and "B" Declared Inoperable During Cold -l
, Shutdown '
86-02 12 B Erosion and Leaks in DHR Pump Casing Drain Line
- 86-03 2 A Containment Purge Unmonitored 1 86-04 ^ 5 A Missed Fire Watch
<
86-05 9
,
B Seismic Spacing of Nuclear Service Batteries i
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86-06 '4 D Fire Protection System Overdue for Surveillance 86-0 B ~ Control Room Emergency HVAC High Flow Condition l 86108 5 D -Failure to Institute Fire Watch for Breached
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Penetration 1
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86-09' 1 A,D < Spurious ESFS Actuation a, ;
86-10' 12 . A,D = Redundant Cabling in Same Fire Area j i
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