IR 05000397/1990023
| ML17286A426 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/08/1990 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17286A424 | List: |
| References | |
| 50-397-90-23, NUDOCS 9011150197 | |
| Download: ML17286A426 (32) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE REPORT NQ - 50-397l90; 23 WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP-2 JUNE 1, 1989 THROUGH AUGUST 31, 1990
SUMMARY ENFORCEMENT ITEMS INSPECTION PERCENT.
SEVERITY LEVELS"~
HOURS OF EFFORT I
II III IV V
DEV A.
Plant Operations B.
Radiological Controls C.
Maintenance/
Surveillance D.
Security F.
Engineering/
Tech.
Support 1214 535'505 207 156
37%
16%
'6%
6%
5%
3%
1
1
G.
Safety Assessment/
569 equality Verif.
17%
TOTALS:
32r11 11Fo 1~
T* X* H
- One violation in each of these Severity Levels was cited during this SALP period, but covered activities which were assessed during previous SALP periods.
e
~*
Severity levels are discussed in 10 CFR 2, Appendix C.
¹ A Severity Level III violation involving commercial grade procurement was cited in Inspection Report No. 89-21 and a civil penalty was proposed.
However, this enforcement action was subsequently canceled pursuant to a Commission policy decision.
SALP FUNCTIONAL AREAS A - Plant Operations B - Radiological Controls C - Maintenance/Surveillance 0 - Emergency Preparedness'
-,
Security F - Engineering/Technical Support G - Safety Assessment/equality Verification
TABLE 2 ENFORCEMENT ACTIVITY INSPECTION REPORT No; DESCRIPTION SEVERITY FUNCTIONAL LEVEL
.
AREA 86-05 86-12 88-16
"89-13 Inadequate fire protection to ensure opera-tion of one train of safe shutdown equipment Environmental gual ificati on of fan motors and Limitorque motor operators Failure to ensure integrity of vital power supplies in the event of an electrical fault Radiation area barrier not installed, allow-ing non-authorized worker free access II~
"
F IV
" Leak between primary containment and reactor building not reported within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LER not submitted within 30 days of HPCS suction valve being found inoperable IV IV F
89-17
.
I 8 C technician performing operations within IV controlled area without protective clothing 89-20 89-21 89-23 89-24 Shutdown cooling inadvertently isolated at 122 Psig on two occasions Performance, training, and qualification audits not performed for 21 months Loose drain plugs in shipping containers
Improper dedication of commercial grade equipment for safety-related use Valve instrumentation connection improperly tightened Inadequate notification to plant personnel during emergency exercise IV IV IV
¹ IV IV
~ These violations were cited during this SALP period, but covered activities which were assessed during previous SALP periods.
¹ A Severity'evel III violation was cited in Inspection Report No.
89-21 and a civil penalty was proposed.
However, this enforcement action was subsequently canceled pursuant to a Commission policy decisio Table 2 -- Enforcement Actions (Cont'd)
INSPECTION REPORT No.
DESCRIPTION SEVERITY FUNCTIONAL LEVEL AREA 89-30 89-31 Fire Protection Prog'ram procedures not properly established and maintained Burned out light bulbs in ECCS pump rooms IV
.
A C
89-38 Improper torquing of fasteners on safety-related valves-IV Failure to initiate nonconformance report for loose capscrews on a safety-related valve Effective actions not taken to prevent recurr-IV ence of loose capscrews on MOVs 89-40 Failure to check battery levels, close 25VDC lighting breakers after maintenance, and properly torque safety related valves IV 90-01 90-09 90-10 Improper handling of contaminated filters IV Improper/mi ssing emer gency operating procedures IV High radiation area not properly controlled IV
'B 90-12 Failure to comply with physical security plan IV Failure to test hand-held metal detectors 90-16 90-22 Failure to specify oil change frequency for standby service water pump motors Failure to make timely assessment of internal exposure IV IV SALP FUNCTIONAL AREAS A - Plant Operations B - Radiological Controls C - Maintenance/Surveillance D - Emergency Preparedness E
Security F - Engineering/Technical Support 6 - Safety Assessment/equality Verification
TABLE 3 SYNOPSIS OF LICENSEE EVENT REPORTS FUNCTIONAL AREA A.
Plant Operations B.
Radiological Controls A
SALP CAUSE CODE I
X
'1
-
3
TOTALS
0 C.
Maintenance/
Surveillance D.
Security F.
Engineering/
Technical Support G.
Safety Assessment/
equality Verification
2
6-
2
-
2
2 TOTALS:
T6
TG Data based upon LERs 89-11 through 90-16 CAUSE CODES A - Personnel Error
Design, Manufacturing, or Installation-C - External Cause 0 - Defective Procedures E - Component Failure X - Other or Unknown FUNCTIONAL AREAS A - Plant Operations B - Radiological Controls C -'aintenance/Surveillance 0 - Emergency Preparedness E - Security F - Engineering/Technical Support G - Safety Assessment/equality Verification
ATTACHNENT A AEOD INPUT TO SALP REVIEW FOR WNP-2 During the assessment period -from June 1,
1989 to July 31, 1990, the licensee submitted 36 LERs, LERs89-024 through 90-014:
1.
Im ortant 0 eratin Events Our LER screening process identified the following nine LER
'
t events:
s as impor an LER 89-026:
On June 19, 1989 a licensee inspection indicated that penetrations greater than 3/4-inch in the Steam Tunnel area have never been pressure tested.
Sample tests of the sealant established that eleven of these penetrations were not adequate for the design basis pressures.
This event is also reportable per
CFR Part
as a deficiency in the seal design of the Steam Tunnel Penetrations by the Plant Architect/Engineer, Burns 8 Roe, Inc..
LER 89-030'
On February 10, 1989 a High Pressure Core Spray suction valve of the Suppression Pool failed to fully open during surveillance test because of the failure of the associated Limitorque motor operator.
The event was Notice of Violation changed from nonreportable to reportable on July 28 1989 to
ion of Inspection Report 89-13.
Root Cause
- Motor operator o comp y with not made per manufacturer's design.
g 6,
1989 during surveillance testing a Reactor Feedwater LER 89-031:
On Au ust ump tripped causing a reactor scram on low Reactor pressure Vessel t
occurred when a solenoid operated drain valve was actuated wa er to depressurize the auto start pressure switch for the auxiliary lube oil pump.
The root cause of the event is under investigation.
LER 89-032:
On Au ust g
10 and 11, 1989 the licensee identified three circuits that violated the WNP-2 Electrical System separation criteria.
Root cause-Design deficiency.
LER 89-034:
Due to desi o design deficiency in protection coordination, on August 11, 1989, six Class 1E 480 volt AC motor control centers were declared LCO 3.0.3.
An Unusual Event inoperable as a result of which the plant entered into T chn'
S 'f
ec nica peci ication performed.
a Event was declared, and a normal reactor shutdown was
l LER 89-043:
On November 21, 1989 during performance of the High Pressure Core Spray (HPCS) surveillance, test, the HPCS minimum flow valve, HPCS-V-12 failed to'open on demand because of failure of= the test'eturn valve, HPCS-V-23 to close completely.
The root cause of this event is under investigation.
LER 89-044:.
On November 26, 1989 the licensee identified six incorrectly sized thermal overload heaters'in High Pressure Core Spray System.
Root cause,
- Design Deficiency.
LER 90-006:
On March 8, 1990 the licensee identified 12 power cables that'.
were not adequately protected to meet 10CFR 50, Appendix R requirements.
Root cause
- Design Deficiency.
l LER 90-012:
On May 27, 1990 an emergency diesel 'generator failed in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> full load run test because of failure of a diesel generator bearing.
Root cause
- Defective-bearing with an. extra-0='ring groove.
2.
Preliminar Notifications Four preliminary notifications (PNs) were issued during this assessment period.
On three of these events, PNO-Y-90-027, PNO-V-,89-049, and PNO-V-89-LER.
046 the necessary LERs have been issued.
The fourth PNO does not warrant s no warran an
'
3.
LER Overview The quality of the LERs were good.
The reports were well written and provided adequate information to describe the major aspects of the events-and they generally identified. the root causes of the events.
4.
Abnormal Occurrences and Other Events of Interest No Abnormal event occurred during this evaluation period.
5.
ALOD Re orts period; No AEOD report was issued on events occurring at WNP2 during th's valu t'
e a ion