IR 05000312/1986029
| 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
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. S. NUCLEAR REGULATORY C0fetISSION-i;
REGION V
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J SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE FOR SACRACMENTO MUNICIPAL UTILITY DISTRICT RANCHO SEC0 NUCLEAR GENERATING STATION
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l REPORT NO. 50-312/86-29 EVALUATION PERIOD:
06/01/85- 06/30/86 ASSESSMENT CONOUCTED:
AUGUST 12, 1986
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8612020532 861114 PDR ADOCK 05000312 o
PDR I
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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 *
1.
' Plant Operations 2468
1
1
2.
Radiological 317
2
4
Controls m.
3.
Maintenance 211
1
4.
Surveillance -
287
1 5.
' Fire Protection 184
.
6.
Emergency-Preparedness 260
5
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7..
Security and Safeguards 545
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8.
Outages
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324
9.
QualityProgr$ms/
531
1
1
Administrative 10.
Licensing Activities NA NA 11.
Training
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1 12.
Engineering and Construction 192
1
1 Totals 5352 100
0
7
6
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- Pending final escalated enforcement action.
- Severity levels are in accordance with NRC Enforcement Policy. (10 CFR Part 2, Appendix C).
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Data compiled from Inspection Report Nos. 85-16 through 86-23, excluding 85-23,
. covering inspections performed during the assessment period 06/01/85 - 06/30/86.
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TABLE 2 Rancho Seco Enforcement Items
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06/01/85 - 06/31/86 (85-19 through 86-23)
Inspection Severity Functional Report No.
Subject.
Level.
Area 85-19 Failure to establish design _and III
installation control measures to ensure integrity of nitrogen supply and vent header system.
85-20 Failure to provide: adequate lighting IV-
levels.
85-28 Failure to follow radiation procedures V
for carrying pocket dosimeter and dressing in' protective-clothing in controlled areas.
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Failure to comply with technical speci-IV-2 fication required verification of flow rates during calibration of stack radiation monitors.
Failure to provide PASS. system training D
at committed frequency.
Failure to provide committed schedule for D
design / procurement of PASS sample shields'.
Fa'ilure to provide committed PASS proce-D
dures for recovery of particulate and
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iodine media under'high sample activity conditions.
Failure to complete committed PASS remote D
adjustment capability for water / nitrogen
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i, manifold and ion chromatograph.
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85'-29
. Failure to adequately search hand-carried III
package.
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85-30 Failure to provide approved procedure for V
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calibration.of power range instrument
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(gain adjustment).
Failure to comply with Technical Specifi-IV
cation cooldown rate of 100*F/hr during October 2, 1985 transient.
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.b TABLE 2 (continued)
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' Rancho Seco Enforcement Items
.06/01/85 --06/31/86 (85-19 through 86-23)
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.. Inspection Severity Functional
- Report No.
Subject Level Area 1n 4.
'85-34 Failure to follow access control procedure (a)
86-04-Failure'to annotate computer printout (b)
regarding alarm response and assessment.
i Degraded vital: area barrier.
(b)
Security officer found asleep in' degraded
. b)'
(
vital area barrier compensatory post.
Compensatory measures failure _
(b)
Failure-to properly escort' visitors and.
(b)
tailgating into vital areas ~.
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Failure to search vehicle.
(b)
86-05 Failure to perform 10 CFR 50.59 safety IV
review.of new building constructed and
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u' sed to process radwaste.
-86-06.
Failure to fol' low procedures to make P
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in-plant announcements and provide complete. initial notification information-to localJgovernment agencies.
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' Failure to follow procedures to make P
follow-sp notifications to local govern-
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ment-agencies.
Failure to maintain emergency plan P
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implementing procedure with current radiation monitor setpoints.
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Failure to implement emergency and P
annunciator. procedure requirements
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to obtain samples, and evacuate the
. auxiliary building and wear respirators.
(a) This violation was combined with the violation in inspection report 85-29 in the aggregate as a Severity Level III problem.
(b) All 86-04 violations.were listed in the aggregate as a Severity Level III proble u
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' TABLE 2 (continued)
, Rancho'Seco Enforcement. Items 06/01/85 - 06/31/86 (85-19 through 86-23)
Inspection-Severity Functional Report No.
. Subject Level Area 86-07 Improper. termination of cable shield wire.
D
Failure to maintain plant cooldown rate P
within Technical. Specification limits.
Failure to corre.ct excessive flow. rate P
. of;the Emergency. Filtration System for th~e CR/TS,C subsequent to surveillance test.
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- Failure to establish written procedure P
for securing HPI following safety feature actuati~on.
Failure'to establish written procedure P
for loss, of power to the ICS.
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Failure to establish. written procedure P
1-for manually operated ATW system valve.
,
- failureJto follow procedur.c to stop P
ATW pumps.
Failure to establish written procedure P
for emergency manual operation of ATW control valve.
_
Failure to provide procedures for P
certain abnormal plant conditions.
Failure to properly implement emergency P
procedures.
Lack of procedure for crimping tool.
P
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-86-08 Failure to properly control calibrated V
I tools and a volt. meter.
86-13 Failure to perform 10 CFR 50.59 evalua-IV
tion on SA-516 plate material.
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86-14'
Failure to insure emergency plan P
training is provided to all appropriate-
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personnel.
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' TABLE 2 (continued).
Rancho Seco Enforcement Items 06/01/85 - 06/31/86-(85-19 through 86-23)
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- Inspection Severity Functional Report No. 8
&ubject Level-Area 86-14-Failure to maintain emergency implementing
.P
. procedures document.
Failure to follow 10 CFR 50.54(q) require-P
.6 ments.
86-15 Failure to comply with Technical Specifi-P
cations, Table 4.21-1, Footnote'(c).
Failure to establish a surveillance P
program pursuant to 10 CFR Part 50, Appendix I, Section IV B.
. Failure to limit the. quarterly loss P
commitments to-a member of the general public pursuant to Technical Specifi-cations, Section 3.1.7.2.
Failure to perform safety evaluations for.
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temporary. changes to radwaste processing systems pursuant to 10 CFR Part 50.59.
Failure to develop and maintain procedures P
2-for controlling the transfer of. radio-
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activity. contaminated water pursuant to
" Technical Specifications, Section 6.8.
- 86-18'
Failure to review modification by'PRC.
IV
Fa'ilure to: hang abnormal tag per V-
requirement.
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86-21 Failure to maintain continuous cleaning D
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86-22 iFailure'to store quality record in the IV
-vault.
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- Severity Level P -;Pending final escalated enforcement action.
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Table 3 SYNOPSIS OF LICEESEE EVENT REPORTS Functional-SALP Cause Code *
. Area A
B C
D E
X
Totals
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1.
Plant Operations
1
5
1
2.
Rad. Controls
0
0
0
3.
Maintenance 2-
0
1
5
~ 4.
Surveillance
0
2
0
5.
Fire Protection
0
1
0
6.
Energency Preparedness
0
0
0
7.
Safeguards
0
0
0
- 8.
Refueling
0
0
0 0-9.
Quality Programs
5
0
0 6 and Administrative Controls Affecting Safety 10.
Licensing
0
0
0
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11.
Training H
0
0
_0
1 Effectiveness J
' 12.
Engineering and
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5
1
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Construction
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Totals
12
10
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A - Personnel Error (
_B Design, Manufacturing or Installation Error C - External Cause
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E - Component Failure-X - Other
- - Cause not yet determined l'
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The:.above data are based upon LERs 85-06 through 86-10.
Three of these LERs reported two separate events which were assigned to separate functional areas l
and cause codes.
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TABLE 4
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SUMMARY OF LERs (LER 85-06 through LER 86-10)'
Functional Cause LER No.
l Areas Code Subject
.85-06.
B CRD Refurbished Breaker Failed to'Open on Undervoltage.During Bench Test 85-07'
D 4160 V.' Bus Undervoltage Relay'Out of Calibration 85-08
A Fire Barrier Surveillance Scheduling Error
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85-09
B Diesel Generator Control Circuitry Fails to Follow Normal Shutdown Sequence '
85-Id'
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' Reactor Coolant System Nonisolatable Leak at
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High Point' Vent; Missing Pipe Supports 85-11 i
D Reactor Trip From Unbypassed Shutdown High
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Pressure Trip Logic
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85-12 Ell.
A Imp.roperly Latched Airlock. Door Compromises Containment Integrity a
85-13
'l B
Diesel Generator Starts from Transient
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Overvoltage Condition 85-14
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
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HVAC Found 85-16
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
D Diesel Generator Output Breaker Lockout 85-19
.D Excess Cooldown Rate After Reactor Trip Due to Open Feedwater Heater Relief Valves-85-20
B Essential HVAC Flow Controller Design Error Prevents Automatic Control After Return of Power
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TABLE 4 (continued)
SUMMARY OF LERs.
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(LER 85-06 through LER 86-10)
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Functio'nal Cause LER No.
sArean Code Subject
.85-21
A.
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
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85-23
E Reactor Trip from Pressure Transient Induced by ICS Relay Resistance, Operator Error with Manual Feedwater Control with Stuck Recorder Pen
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85-24
E Reactor Shutdown Due to Packing Glarid Leak' age of Pressurizer Liquid Sample Inboard Isolaticn-l
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85-25
~1 A
Reactor Trip and Overcooling from Loss of ICS
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D Power Induced Transient'
86-01 3,9-B EDG "A" and "B" Declared Inoperable During Cold-l
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Shutdown
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86-02
B Erosion and Leaks in DHR Pump Casing Drain Line
86-03
A Containment Purge Unmonitored
86-04 ^
A Missed Fire Watch 86-05
B Seismic Spacing of Nuclear Service Batteries
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86-06
'4 D
Fire Protection System Overdue for Surveillance 86-07.
B
~ Control Room Emergency HVAC High Flow Condition
l 86 08
D-Failure to Institute Fire Watch for Breached
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86-09'
A,D
< Spurious ESFS Actuation
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86-10'
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= Redundant Cabling in Same Fire Area j
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