IR 05000344/1987041
| ML20151G022 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/30/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20151G015 | List: |
| References | |
| 50-344-87-41, TAC-66590, NUDOCS 8804190149 | |
| Download: ML20151G022 (44) | |
Text
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t U. S. NUCLEAR REGULATORY COMMISSION
REGION V
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE FOR PORTLAND GENERAL ELECTRIC COMPANY TROJAN NUCLEAR PLANT REPORT NO. 50-344/87-41 EVALUATION PERIOD:
11/1/86 - 11/30/87 SALP BOARD ASSESSMENT CONDUCTED:
JANUARY 5, 1988
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8804190149 880330 PDR ADOCK 05000344 Q
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SUMMARY (11/1/86 - 11/30/87)
TROJAN NUCLEAR PLANT Inspections Conducted Enforcement Items Inspection *
Percent Severity Level **
Functional Area Hours of Effort I
II III IV V Dev.
1.
Plant Operations 1337 25.51 1 1 2.
Radiological Controls 386 7.36
1 3.
Maintenance 442 8.43
4.
Surveillance 165 3.15
5.
Fire Protection
.76
6.
Emergency Preparedness 654 12.48 7.
Security 576 10.99
8.
Outages 137 2.61 9.
Quality Programs and 1303 24.86 3 1
Administrative Controls Affecting Quality 10.
Licensing Activities N/A N/A 11.
Training and Qualification
1.47 Effectiveness 12.
Engineering 125 2.38
TOTAL 5242 100.00
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- Allocations of inspection hours to each functional area are approximations based upon NRC Form 766 data.
- Severity levels are in accordance with NRC Enforcement Policy (10 CFR Part 2, Appendix C).
Data reflects Reports 86-40 through 87-4.
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TABLE 2 TROJAN NUCLEAR PLANT ENFORCEMENT ITEMS Inspection Severity Functional Report No.
Subject Level Area 86-42 Physical Security Barriers failure IV
to adequately secure openings in vital area barriers.
Failure to annunciate changes in IV
status of security computer system.
86-45 Chemistry technician was observed V
working in hot sample sink without wearing a laboratory coat.
87-09 Nuclear Quality Assurance Department IV
was not enforcing the requirements of NQAP-114 and issuing the Trend Analysis Cata Form at completion of each audit or surveillance.
87-13 Qualification File No. 15 for IV
Rosemount Type 176KF and 176 KS RTOs did not demonstrate that the plant functional performance requirements for their application were met.
Limitorque valve actuators in V
containment were not maintained in a condition similar to that in which they were tested, in that many of their gear case grease relief valves had dust caps installed, and qualification files covering these Limitorque valve actuators did not contain any justification for the deviation.
87-15 Failure to establish and implement III
radiation protection procedures, train workers, perform radiation surveys and maintain records of radiation survey results.
87-18 No deviation, as required by Pending
Administrative Order (AO) 4-4, was obtained prior to attempting transfer between the SI accumulators using the fill line on May 12 or May 23, 1987.
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TABLE 2 (cont.)
TROJAN NUCLEAR PLANT ENFORCEMENT ITEMS
, Licensee failed to establish hold Pending
tags so that the fill line could not be utilized prior to resolution of the problem.
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87-24 Failure to report automatic actuation V
of Reactor Protection System of June 29, 1987 at 9:02 p.m.
87-31 The 1983 ASME Boiler and Pressure IV
Vessel Code,Section XI specifies
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that "values with fail-safe actuators shall be tested by observing operation of the valves upon-loss of actuator power.
Contrary to this, as of October 2, 1987, the AFW turbine driven pump had not been verified to be capable of starting by operation of the steam admission valves coincident with loss of actuator power (using only accumulator air).
Contrary to the licensee's program IV
for inservice testing (IST) of pumps and valves, as of October 2, 1987, valves MS 226 and MS-222 had not been included in the licensee's IST
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program.
As of October 2, 1987, the eight IV
Emergency Diesel Generator (EDG)
Air Start System pressure regulators downstream pressure setpoints were 180 to 190 psig.
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The setpoint had been changed without documenting the
performance of a safety evaluation.
As of October 2, 1987; (a) all IV
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eight lubricators of the EDG Air Start System were downstream of relay air valves, (b) one of
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eight relay air valves was equipped
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with a pressure gage, and (c) one of eight pressure reducing valve i
downstream pressure gages was a
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0-200 psig gage.
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TABLE 2 (cont.)
TROJAN NUCLEAR PLANT ENFORCEMENT ITEMS Eight EDG Air Start System air IV
receiver relief valves had not been tested, inspected or set since original construction.
As of September 22, J.987, support V
H 834 was not attached to the air supply line.
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Deviation At the time of the inspection, the
Trojan instrument air system utilized a rotary compressor with.the screw lubricated by an air / oil mixture.
Additionally, air lines to the main steam isolation valves and the steam isolation valves for the auxiliary
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feedwater steam turbine did not have in-line filters.
This is a deviation.
87-34 Contrary to the licensee's Nuclear IV
Quality Assurance Program, on September 25, 1987, adequate measures had not yet been established to ensure appropriate review of fire protection program activities by a fire protection engineer As of September 25, 1987, adequate IV
corrective action to NCAR No. P86-123 was not accomplished to assure that the cause of significant conditions adverse to quality were corrected to preclude repetition:
All supervisors
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issuing welding and cutting permits had not been trained to perform this activity in accordance with the corrective action to NCAR P86-123.
As of September 25, 1987, the IV
licensee's training program for fire protection had not been maintained so that the brigade's ability to perform the operations they are expected to carry out is maintained.
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TABLE 2-(cont.)
TROJAN NUCLEAR PLANT ENFORCEMENT ITEMS 87-40 Three instances of required Technical IV
specifications surveillance testing performed on September 12~,19, and 26, 1987, detector current calculations were not performed after detector voltage calculations indicated Quadrant Power Tilt Ratio exceeded 1.02.
Contrary to Technical Specification IV
4.10.1.2; during low power physics testing conducted in July 1985, September 1984, and July 1983, rod drop time measurements were performed for only one full length control rod (at location K-06) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the shutdown margin to less than the limits of Specification 3.1.1.1.
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TABLE 3
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TROJAN NUCLEAR PLANT-SYNOPSIS OF LICENSEE EVENT REPORTS **
Functional SALP Cause Code *
Area A.
B C
D E
X-Totals.
1.
Plant Operations
0
3
0
2.
Radiation Controls
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0
1
1 3.
Maintenance
1
1
0
4.
-Surveillance
1
3
0
5.
Fire Protection
0
0
0
6.
0
0
0
7.
Security
0
0
0
8.
Outages
1
0
0
9.
Quality Programs and
0
0
0
Administrative
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Controls Affecting Quality
,10.
Licensing Activities
0
0
0
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11.
Training and
0
0
0
Qualification Effectiveness l
12.
Engineering
1
0
0
l-l TOTALS
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7
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- Cause Codes:
A-Personnel Error B-Design, Manufacturing or Installation Error
C-External cause D-Defective Procedures E-Component Failure X-Other
- Synopsis includes LER Nos. 86-10 through 87-34
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TABLE 4 TROJAN NUCLEAR PLANT LICENSEE EVENT REPORTS (11/1/86 - 11/30/87)
LER Title SALP Area /Cause Code *
86-10 Deficiencies Identified in the Analysis 12/A of High Energy Line Breaks in the Turbine Building 86-11 Reactor Trip from Spurious High Vibration 1/E Signal on Main Turbine 86-12 Control Room Boundary Degradation Resulting 4/E in Inability to Maintain Positive Pressure in Control Room 87-01 Technician Inadvertently Shorted Feedwater 3/A Pump Control Power-Feedwater Pump Trip / Reactor Trip 87-02 Control Room Boundary Door Stuck Open 1/E Insufficient Control Room Positive Pressure Maintained (Voluntary)
87-03 Deficient Procedure Resulted in Inadequate 4/0 Response Time Testing 87-04 Technician Error Resulted in Reactor Trip 4/A Breaker Opening 87-05 Waste Gas Compressor Oxygen Alarm 12/A Inadvertently Disconnected from Control Room 87-06 Deficiencies in Flood Protection Design 12/8 Provisions 87-07 Pressurizer Safety Valve Lifted Out-of-3/D Tolerance During Surveillance Testing 87-08 Fuel Particles Contaminated Containment 2/E Technician Exposed to Radiation 87-09 Raychem Splices Improperly Installed 8/B 87-10 Inadvertent Actuation of 230 KV Bus 3/A Differential Relays - Partial Loss of Offsite Power
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TABLE 4 (cont.)
TROJAN NUCLEAR PLANT (LICENSEE EVENT REPORTS)
87-11 Electrical Penetration Leaked 4/E Excessively due to Degraded Seals 87-12 Control Room Boundary Compromised Due 4/A
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to Removed Duct Panel 87-13 Accumulator Fill Line Ruptures Due to 1/A
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Backflow Induced Vibration
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87-14 Charging Pump Cladding Corrosion Due to 3/B Apparent Manufacturing Deficiency 87-15 Steam Generator Level Transmitters 4/A Improperly Calibrated t
87-16 Reactor Trip Breakers Inadvertently 4/D
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Opened Due to Procedure Deficiency i
87-17 Leakage Through Control Room Floor Cable 4/D Penetrations - Insufficient Control Room Positive Pressure
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87-18 Valve Packing Leakage Exceeded FSAR 4/E
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Assumed Leakage
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87-19 Movement of Irradiated Filter Near 8/A l
Radiation Monitor Caused Containment
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Ventilation Isolation i
87-20 Seismic Monitoring Instrumentation 4/A
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Surveillance Missed Due to Inadvertent
Deletion from Schedule I
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87-21 Opening of Incorrect Fuse Drawer Caused 1/A i
12.47 Kv Bus Undervoltage - EDG Started 87-22 Accumulator Water Level Inadvertently 4/A f
Allowed to Decrease Below Technical Specification Limit 87-23 Feedwater Regulating Valve Failed to 1/E
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Close - Turbine Trip on Hi-Hi Steam
Generator Level
87-24 Turbine Trip / Reactor Trip Due to "C" 1/A Steam Generator High-High Level 87-25 Containment Ventilation Isolation Sue 1/E
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to Spurious Actuation of PRM-1C l
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TABLE 4 (cont.)
TROJAN NUCLEAR PLANT (LICENSEE EVENT REPORTS)
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LER Title SALP Area /Cause Code *
87-26 Missed Surveillance of Post-Accident 4/A
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Leakage Outside Containment i
87-27 Boron Injection Tank Relief Valve Leaked 1/E Greater than FSAR Assumed Limits 87-28 Containment Ventilation Isolation Due to 4/B Spurious Actuation of PRM-1A 87-29 Fire Watch Not Established Due to 3/A Personnel Error i
87-30 Low Component Cooling Water Flow to RHR 1/D
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Heat Exchange-Procedure Inadequacy 87-31 Steam Flow Channel Bistable Not Tripped 4/A l
Per Technical Specifications Due to Personnel Error 87-32 Reactor Coolant System Wide Range 1/D Pressure Transmitters Out-of-Calibration
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Due to Instrument Drift.
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87-33 Main Steam Pressure Transmitters Out-of-1/D
Calibration-Apparent Procedure Inadequacy
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87-34 Emergency Diesel Generator Not Demonstrated 1/A Operable Per Technical Specifications -
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- Cause Codes:
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B-Design, Manufacturing or Installation Error l
C-External Cause
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D-Defective Procedures E-Component Failure X-Other i
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