IR 05000344/1986043

SALP Rept 50-344/86-43 for Nov 1985 - Oct 1986

ML20212E077
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/19/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20212E069	List: IR 05000344/1986043 ML20212E065
References
50-344-86-43, NUDOCS 8701050239
Download: ML20212E077 (48)

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, < U.. S; NUCLEAR REGULATORY COMISSION j REGION V

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i SYSTEMATIC AS5ESSMENT OF LICENSEE PERFORMANCE FOR PORTLAND GENERAL ELECTRIC COMPANY TROJAN NUCLEAR PLANT REPORT NO. 50-344/86-43 EVALUATION PERIOD: 11/1/85 - 10/31/86 ASSESSMENT CONDUCTED: DECEMBER 4, 1986 D$$$$$h{f344 PDR

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TABLES OF SUMMARY (11/1/85 - 10/31/86)

TROJAN NUCLEAR PLANT Inspections Conducted Enforcement Items Inspection" . Percent Severity Level ""

Functional Area Hours of Effort I II III IV V De ~ Plant Operations 1958 40.99 1 Radiological Controls 251 . Maintenance 356 7.45 1 Surveillance 607 1 . Fire Protection 36 .75 Emergency Preparedness 40 .84 Security and Safeguards 139 2.91 5

' Outages 443 . Quality Programs and 500 10.46 2 1 Administrative Controls

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1 Licensing 122 2.52 1 Engineering & Construction 236 4.94 1 1 Training ' 88 1.84 TOTAL 4776 100.00 1 3 12 4 1

• Allocations of inspection hours to each functional area are approximations based upon NRC Form 766 dat ** Severity levels are in accordance with NRC Enforcement Policy (10 CFR Part 2, Appendix C).

Data reflects Reports 85-33 through 86-39 l

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TABLE 2 TROJAN NUCLEAR PLANT ENFORCEMENT ITEMS Inspection Severity Functional Report N Subject' Level Area 85-33 Abser.ce of independent quality control III 9 1 over maintenance activity Failure to properly identify AFW flow IV 3 indicating switches 86-3 Security violation IV 7 Lack of proper control of keys and IV 7 key cards Reporting losses of physical security IV 7 86-6 Failure to maintain the Control Room II 11 Emergency Ventilation Systems in an operable status Deviation: Control Room Emergency 4 Ventilation System (CB-1) humidistat was set at 85 percent during normal lineup rather than at the 70 percent value indicated in the FSA Licensee failed to report the status V 2 and identify the cause of an inoperable radioactive gaseous effluent monitoring channel (FR-3100)

86-18' Workers issued a respirator for use IV 2 whose medical reevaluations had expirea Licensee did not maintain records of V 2 surveys performed on May 12 and April 19 and 25, 1986 86-20 Corr (ctive action was not assigned and IV 9 implemented for NCR86-024, which documented NCR's associated with electrical conduit support for the

"A" train of the hydrogen recombiner system

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TABLE 2 (Continued)

TROJAN NUCLEAR PLANT ENFORCEMENT ITEMS j Inspection Severity Functional Report N Subject Level Area 86-23 Battery service test, MP-1-14, performed IV 4 in May 1985 and May 1986, to verify the battery capacity utilized a constant current load of 300 amps and were performed at a battery temperature of approximately 90 F, without correcting the results accordingly for the elevated temperatur The inservice test program implemented by IV 4 the licensee did not include some ASME Code Class 3 valves and the valves had not been

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periodically teste Licensee surveillance procedure MP-1-14, IV 4 and operating instructions 01-4-2 and ONI-14 had not been properly maintained, in that they were not consistent with the plant design basis, as defined in the Updated Safety Analysis Report (USAR).

During the May 1985 performance of V 4 procedure MP-1-14, the final battery voltage following the 30 minute discharge was not recorded for battery D-1 While in Mode 1 for one hour and ten III 1 minutes, portions of the RHR system were inoperable when valve M0-8809A was close Quality Control inspector failed to III 9 properly follow procedures MP-5-1 and QCP 3 for the installation of the inlet flange of valve PSV-8010A 86-28 On the four-day period from 0001 IV 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> May 12 to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> May 15, 1986, approximately 100 entries were made to vital areas without use of the individually-assigned card key and thus without the entry being properly noted by the computer The licensee failed to report the IV 7 undetected access to vital areas as described in the item above to the NRC l

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I TABLE 2 (Continued)

TROJAN NUCLEAR PLANT ENFORCEMENT ITEMS Inspection Severity Functional Report N Subject Level Area 86-30 Licensee delivered for transport a IV 2 Model No.10-142 shipping package which contained approximately 30

. gallons of free standing radioactive water

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Licensee failed to maintain records V 2 of surveys made of the spent resin storage tank pump room and adjacent areas on July 24, 1986 i

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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 . Totals Plant Operations 2 0 1 1 2 0 6 Radiation Protection 0 0 0 0 0 0 0 Maintenance 0 0 0 0 0 0 0 Surveillance 0 3 0 0' 2 0 5 Fire Protection 0 0 0 0 0 0 .0 . Emergency Preparedness 0 0 0 0- 0 0 0 Safeguards 0 0 0 0 0 0 0 Outages 0 0 0 0 0 0 0 Quality Program and 0 0 0 0 0 0 0 Administrative - 4 Controls Affecting

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Safety 1 Licensing -0 0 0 0 0 0 'O 1 Engineering and 0 0 0 0- 0 0 0 Construction-

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12i.. Training , 0 0' 0 0 0 0 0 TOTALS 2 3 1 1 4 0 11

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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. 85-13 through 86-09 NOTE: Several LERs categorized in multiple areas of cause codes follow-up LERs which do not identify additional areas or causes were not double accounted along with the original LER during this perio __

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TABLE 4 e

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TROJAN NUCLEAR PLANT Licensee Event Reports

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(11/1/85 - 10/31/86)

LER Title SALP Area /Cause Code *

85-13 High Failure Rates during Snubber 4/E Inservice Testing 85-14 Automatic Actuation of "B" Emergency 1/E Diesel Generator 86-1 Circulating Water Pu.np Trip Resulting 1/D in High Negative Flux Rate Reactor Trip

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86-2 Control. Room Emergency Ventilation 4/B System Degradation Due to Equipment Failure and Design Deficiency 86-3 Residual Heat Removal System Inoperable 1/A Due to lncorrect Technical Specification Interpretation 86-4 Ship Grounding Outside. Intake Structure 1/C-Damaging Plant Outfall Pipe 86-5 Containneent Isolation Valves Fail Local 4/B Leak Rate Testing 86-6 Na0H Additive Flowrate Test Failed Due 4/B to Misapplication of Kerotest Globe Valves 86-7 Reactor Trip Due to Personnel Error 1/A Resulting in Exceeding Low Power Range Trip Setpoint 86-8 Safety Injection and Reactor Trip Due 4/E to Failed Steam Pressure Transmitter 86-09 Source Range Neutron Detector Spike 1/E Causes Reactor Trip Breakers to Open

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A-Personnel Error-

,B-Design, Manufacturing or Installation Error

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C-External Cause v

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D-Defective Procedures -

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E-Component Failure X-Other n ,

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