IR 05000029/1985098

SALP Rept 50-029/85-98 for Feb 1985 - Oct 1986

ML20207F622
Person / Time
Site:	Yankee Rowe
Issue date:	12/30/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20207F617	List: ML20207F615 ML20207F622
References
50-029-85-98, 50-29-85-98, NUDOCS 8701060160
Download: ML20207F622 (57)

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<L ENCLOSURE SALP BOARD REPORT U.S. NUCLEAR REGULATORY COMISSION

REGION I

SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE INSPECTION REPORT 50-29/85-98 YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION ASSESSMENT PERIOD: FEBRUARY 1, 1985 - OCTOBER 6, 1986 BOARD MEETING DATE: DECEMBER 4, 1986 l

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8701060160 861230 9 PDR ADOCK 0500

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l SUMMARY DESCRIPTION 85-01 Determination of Inappropriate LOCA Methodology Assumption-85-02 CS-V-621 Not Tested in Accordance With The ISI Program 85-03 Fuel Degradation (Assemblies B-696I, B-688 and A-679 In Core Posi-tions ,,-9, H-8, and K-5)

85-04 Pressurizer Safety Valve PR-SV-181 (S/N BW 07972) Setpoint Greater Than TS

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85-05 Switchgear Room Fire Barrier Inadequacy 85-06 Condensate Pump Trip Circuit Inoperable 85-07 Nuclear Instrumentation Channels 7 & 8 Low Power Set Points In-operable 85-08 No. 4 Steam Generator Blowdown Monitor Inoperative 85-09 Reactor Scram During Startup due to Maintenance Personnel Erro Inadvertent Reactor Scram During Maintenance Activity 86-01 Technical Specification Violation Concerning the Yankee Emergency Plan 86-02 Insufficient Implementation Procedures For the Offsite Dose Calcu-lation Manual

86-03 Failure to Comply with a Technical Specification Action Statement 86-04 Reactor Scram - Loss of Heater Drain Pumps

. 86-05 Dose Equivalent I-131 >1.0 Microcuries Per Gram

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86-06 Inoperable No. 3 Steam Generator Blowdown Monitor 86-07 480 VAC Busses Cross-Tie Electrical Loading Problem 86-08 No. 1 Main Coolant Pump Suction Valve Stem Failure 86-09 Incorrect Overload Devices for Four Motor-0perated Valves

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LER NUMBER SlM4ARY DESCRIPTION 86-10 Potential Loss Of Shutdown Cooling 86-11 Containment Isolation Valves Missed Surveillance 86-12 Plant Trip on Low SG Level Due to Loss of Control Air 86-13 Reactor Scram due to Operator Error l

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TABLE 3 INSPECTION HOURS SUMMARY (2/1/85 - 10/6/86)

YANKEE NUCLEAR POWER STATION HOURS % OF TIME Plant Operations 655 22% Radiological Controls 507 14% Maintenance and Modifications 601 20% Surveillance 284 10% Fire Protection and Housekeeping 162 5% Emergency Preparedness 445 15% Security and Safeguaras 154 5% Refueling and Outage Management 142 5% Assurance of Quality NA NA Training and Qualification Effectiveness NA NA Licensing Activities * 107 4%

Total 3057 100%

• Inspection effort only.

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TABLE 4 ed ENFORCEMENT SUMMARY YANKEE NUCLEAR POWER STATION Severity Levels FUNCTIONAL AREAS I II III IV V DEV Total Plant Operations 1 1 Radiological Controls Maintenance and Modifications 1 1 Surveillance 2 2 Fire Protection and Housekeeping Emergency Preparedness Security and Safeguards Refueling and Outage Management Assurance of Quality 1 1 J .' Training and Qualification Effectiveness Licensing Activities 1 2 2 5

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TABLE 5 ENFORCEMENT DATA YANKEE NUCLEAR POWER STATION Inspection Inspection Severity Functional Report N Date Level Area Violation 85-07 3/21-4/26/85 V D Failure to establish a written procedure that pre-

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scribes the required quali-tative assessment for in-strumentation channel checks required by the Technical Specifications for meteoro-logical monitoring syste /7-2/14/86 V D Failure to establish a written procedure that prc-scribes the required quali-tative assessment for in-strumentation channel checks required by the Technical Specifications for steam generator blowdown monitor /10-10/8/86 IV A Failure to maintain at least one main coolant loop bypass valve closed while in Mode 3 and failure to conduct a required surveillance test on these valve /26-7/2/86 III C Installation of undersized trip coils in circuit breakers for motor-operated valves located in the reac-tor coolant system and emergency feedwater syste .

86-17 9/29-10/3/86 IV H Failure to follow procedures requiring quality control for maintenance activities.

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TABLE 6 INSPECTION REPORT ACTIVITIES YANKEE NUCLEAR POWER STATION Inspection Inspection Areas Report N Hours Inspected 85-04- 110 Routine Resident 85-05 160 Post-Accident Sampling System 85-06 30 Startup Physics Testing 85-07 114 Routine Resident 85-08 163 Emergency Preparedness Exercise F5-09 72 Radiation Protection Prorrr,

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85-10 40 Radiological Environmental Monitoring Program 85-11 141 Routine Resident 85-12 135 Generic Letter 83-28, Salem-ATWS Concerns 85-13 34 Safe Shutdown System Building Construction 85-14 181 Routine Resident 85-15 137 Routine Resident 85-16 Radiation Protection Program 85-17 31 Physical Security 85-18 156 Routine Resident 85-19 12 Licensing Review (on-site) of P.C. 186 85-20 37 Maintenance Program 85-21 27 Nonradiological Chemistry Program 85-22 --

Operator Examination 85-23 74 Radiation Protection Program 85-24 126 Routine Resident l

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• T-6-2 Inspection Inspection Areas Report N Hours Inspected 85-25 135 Appendix R 86-01 42 Refueling and Startup Testing 86-02 99 Routine Resident 86-03 18 Licensed Operator Training Program 86-04 37 Radioactive Waste Management 86-05 196 Routine Resident 86-06 83 Emergency Preparedness Exercise 66-07 --

Operator Examination 86-08 200 Routine Resident 86-09 49 Reactor Coolant System Vents-Special Inspection 86-10 19 Emergency Preparedness 86-11 32 Surveillance Testing and Calibration Control Program 86-12 74 Radiation Protection Program 86-13 --

Not Used 86-14 35 Physical Security 86-15 --

Not Used 86-16 58 Radiological and Chemical Confirmatory Measurements

, 86-17 124 Operational QA Effectiveness

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c TABLE 7 REACTOR TRIPS AND UNPLANNED SHUTDOWNS YANKEE NUCLEAR POWER STATION Power Proximate Root Date Level Cause Cause 12/9/85 <2% Unit Trip Personnel error maintenance. Contractor employee inadvertenly bumped an RPS relay while cleaning within the control room's main control boar /28/85 <2% Unit Trip Personnel error - maintenance and opera-tion False high startup rate trip caused when maintenance personnel performed a functional test in conjunction with troubleshooting. The root cause was per-sonnel failure to recognize performance of the test while at <15% power will resuit in a plant scra /1/86 100% Unit Trip Equipment failure - random caus Loss of both heater drain pumps resulted in a low steam generator level reactor scra The pumps were damaged in a lightning stor /18/86 100% Shutdown Equipment failure - mechanical defect (under review). Shutdown to repair a leaking weld in a coupling on the No. 2 steam gerator's blowdown lin /4/86 100% Unit Trip Equipment failure - random caus Low control air pressure condition caused by a component failure subsequently resulted in a plant scram on low steam generator levels. A contributing cause was inade-quacies in guidance in a recovery procedure involving feedwater control valve lock-u /4/86 <2%' Unit Trip Personnel error - operations. Control room operator error resulted in RPS trip

, when the non-return valve trip / reset switch

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was inadvertantly placed in the trip posi-tion during a plant startup.

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c FIGURE 1 NUMBER OF DAYS SHUT DOWN YANKEE NUCLEAR POWER STATION I

February, 85 l l

March, 85 l l

April, 85 l l

May, 85 l l

June, 85 l l

July, 85 l l

August, 85 l l

September, 85 l I

October, 85 I i 13 Days Shut Down Cycle XVII-XVIII Refueling Outage i

November, 85 1 30 Days Shut Down l Cycle XVII-XVIII Refueling Outage i

December, 85 l l 9 Days Shut Down Cycle XVII-XVIII Refueling Outage l

January, 86 l

February, 86 l l

March, 86 l l

April, 86 l l

l May, 86 l

June, 86 I i 13 Days Shut Down 1_

July, 86 l_I 1 Day Shutdown i

August, 86 l l

September, 86 l 1_

October, 86 1_l I Day Shutdown

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