IR 05000400/1999005

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Insp Rept 50-400/99-05 on 990718-0828.No Violations Noted. Major Areas Inspected:Performance Indicators Verification
ML18017A906
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 09/23/1999
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18017A905 List:
References
50-400-99-05, NUDOCS 9910120078
Download: ML18017A906 (15)


Text

U. S. NUCLEAR REGULATORYCOMMISSION

REGION II

Docket No:

License No:

50-400 NPF-63 Report No:

50-400/99-05 Licensee:

Carolina Power 8 Light (CP8L)

Facility:

Shearon Harris Nuclear Power Plant, Unit 1 Location:

5413 Shearon Harris Road New Hill, NC 27562 Dates:

July 18 - August 28, 1999 Inspectors:

J. Brady, Senior Resident Inspector R. Hagar, Resident Inspector E. Testa, Senior Radiation Specialist (Sections 2PS1 and 2PS3)

Approved by:

B. Bonser, Chief, Projects Branch 4 Division of Reactor Projects 99'iOi20078 990923 PDR ADOCK 05000400 PDR

SUMMARYOF FINDINGS Shearon Harris Nuclear Power Plant, Unit 1 NRC Inspection Report 50<00/99-05 The report covers a six-week period of resident inspection.

In addition, it includes the results of announced inspections by a regional senior radiation specialist.

Performance Indicators Verification The initiating events cornerstone performance indicators were reviewed and verified. These included Unplanned Scrams Per 7,000 Critical Hours, Scrams With A Loss Of Normal Heat Removal, and Unplanned Power Changes Per 7,000 Critical Hours. Two years of data was reviewed.

No findings were identified.

No findings were identified during this inspection perio Re ort Details The unit was at essentially 100% power for the entire period.

1.

REACTOR SAFETY Cornerstones:

Initiating Events, Mitigating Systems, Barrier Integrity I Rtl The inspectors reviewed the emergent items described in the following Work Requests/Job Orders (WRJOs):

WR/JO 98-AGUQ1 99-AFYL1 99-AGDL1 Title Replace the leaking gasket(s) for 1CS-E016 (excess letdown heat exchanger)

Emergency Service Water Pump main reservoir traveling screen will not rotate due to broken coupling

"A"vacuum pump would not stay running b.

Observations and Findin s No findings were identified and documerited through this inspection.

1R04 E ui ment AIi nment R

The inspectors performed a detailed review of the emergency diesel generator (EDG)

system.

This included a review of the Final Safety Analysis Report, and system descriptions; a review of the status of work orders and condition reports (CR) with the system engineer; and a walkdown of the EDG system.

b.

Observations and Findin s No findings were identified and documented through this inspection.

1R05 Fire Protection The inspectors reviewed the high fire risk areas which included four fire zones that did not screen out using the Fire Induced Vulnerability Evaluation methodology in the Individual Plant Examination for External Events (IPEEE). Two zones contained the

control room envelope and the other two contained the two switchgear rooms. The inspectors also discussed the fire drill schedule with the licensee to determine when drills would be conducted in the high fire risk areas.

b.

Observations and Findin s No findings were identified and documented in relation to inspection of the high fire risk areas.

The inspectors observed that no drills were scheduled in the switchgear areas.

In discussing this with the licensee, the inspectors learned that no fire drill in these areas had been scheduled in at least the past seven years.

The licensee had decided that since full scale fire drills in the switchgear rooms could inadvertently initiate plant events, drills would not be conducted in those areas.

The IPEEE indicated that the core damage frequency contribution from the two switchgear rooms was 3.1E-6/year and 4.0E-6/year (highest of any room in the plant). The licensee initiated CR 99-01973 to review the fire brigade training for the switchgear areas and to reassess the decision not to conduct drills there.

1R09 Inservice Testin IST ofPum sand Valves S

The inspectors reviewed the performance of the following IST tests:

OST-1085

Number Rev.

OST-1041 Title A Train Heating Ventilation and AirConditioning (HVAC) Safety Related Essential Service Chilled Water (ESCW) Temperature Control Valves (TCVs) Inservice Inspection (ISI) Operability Test 1A-SA Diesel Generator Operability Test Semiannual Interval MST-I0116

Hydrogen Monitor Operability Test b.

Observations and Findin s No findings were identified and documented through this inspection.

1R12 Maintenance Rule Im lementation a.

Ins ection Sco e

The inspectors reviewed the licensee's implementation of the Maintenance Rule (10 CFR 50.65) with respect to the equipment issues described in the following CRs:

CR 99-01450 Emergency Safeguards Sequencer relay 2-30/1161 was found out of tolerance CR 99-01808 Turbine Driven AuxiliaryFeedwater Manual/Automatic station failed CR 99-02087-1

"A"Waste Gas Compressor Breaker tripped b.

Observations and Findin s No findings were identified and documented through this inspection.

1R13 Maintenance Work Prioritization 8 Control The inspectors reviewed the licensee's assessments of the risk impacts of removing from service the components associated with the Emergent Work items listed in section 1R03.

I b.

Observations and Findin s No findings were identified and documented through this inspection.

1R14 Nonroutine Evolutions The inspectors observed the operating crew's performance during the following non-routine evolutions:

~

Placing excess letdown in service and removing normal letdown from service, August 4, 1999, and August 12-13, 1999, and

~

Response to unidentified reactor coolant system leakage greater than Technical Specification limits, August 4, 1999.

b.

Observations and Findin s No findings were identified and documented through this inspection.

1R15 0 erabilit Evaluations a.

Ins ection Sco e

The inspectors reviewed the operability evaluations described in the following Engineering Service Requests (ESRs):

ESR No.

Rev.

Title 99-00254 99-00323

Operability Determination for Preaction and Multicycle System

Excess Letdown Heat Exchanger Piping Operability Determination 99-00331

Operability Determination for Response Spectrum Analyzer b.

Observations and'Findin s

No findings were identified and documented through this inspection.

1R16 0 erator Workarounds The inspectors reviewed the operator work-around associated with operating the letdown pressure control valve in manual rather than automatic control. The inspectors reviewed plant conditions to assess whether operator work-around items were being identified in the operator work-around program.

b.

Observations and Findin s The inspectors observed a fire alarm in the EDG building and the licensee's investigation of that alarm. The investigation revealed that the alarm was spurious and was caused by the starting of the motor driven fire pump (MDFP). Licensee operations personnel, revealed that these spurious alarms occur frequently when the MDFP is started.

The inspectors determined that spurious alarms would direct operator attention and fire brigade response from a real fire. As a result, the'licensee initiated CR 99-02369 to document this condition and added the work-around to the program.

No findings were identified and documented through this inspection.

1R19 Post Maintenance Testin The inspectors reviewed the following post-maintenance tests:

Number EPT-33 Rev.

Title

Emergency Safeguards Sequencer System Test Related maintenance task 99-AEZK1, Replace 2 relays in "A"emergency sequencer OST-1085

1A-SA Diesel Generator Operability Test Semiannual Interval Various preventive-maintenance tasks

OST-1 032

Reactor AuxiliaryBuilding Emergency Exhaust System Train A Operability Monthly Interval Modes 1-4 99-ADUF1, Replace E-6 fan outboard bearing b.

Observations and Findin s No findings were identified and documented through this inspection.

1R22 Surveillance Testin The inspectors reviewed the following surveillance tests:

OST-1026, Reactor Coolant System Leakage Evaluation, Computer Calculation, Daily Interval, Modes 1-2-3-4, Revision 12 MST-!0145, Steam Generator A Narrow Range Level Loop (L-0476) Operational Test, Revision 4 MST l0146, Steam Generator B Narrow Range Level Loop (L-0484) Operational Test, Revision 4 b.

Observations and Findin s No findings were identified and documented through this inspection.

t Cornerstone: Emergency Preparedness 1EP1 Drill Exercise and Actual Events The inspectors reviewed licensee participation in the August 26, 1999, emergency drill.

b.

Observations and Findin s No findings were identified and documented through this inspectio.

RADIATIONSAFETY Cornerstone: Public Radiation Safety 2PS1 Gaseous and Li uid Effluent Treatment S stems The inspectors reviewed the licensee's performance to ensure that the gaseous and liquid effluent processing systems are maintained so that radiological releases are properly mitigated, monitored, and evaluated to limit public exposure.

b.

Observations and Findin s No findings were identified and documented through this inspection.

2PS3 Radiolo ical EnvironmentalMonitorin Pro ram The inspectors reviewed the licensee's performance in implementing the Radiological Environmental Monitoring Program (REMP) as required by Technical Specifications and the Offsite Dose Calculation Manual (OCDM).

b.

Observations and Findin s No findings were identified and documented through this Inspection.

4.

OTHER ACTIVITIES 4OA2 Performance Indicator Verification The inspectors reviewed and verified the July 1999 performance indicator data for all of the initiating events cornerstone performance indicators. The inspectors reviewed two years of data that included inspection reports, monthly operating reports and operator logs.

b.

Observations and Findin s No findings were identified and documented through this inspectio OA5 Mana ement Meetin s

.1 Exit Meetin Summa The inspectors presented the inspection results to members of licensee management on September 2, 1999. The licensee acknowledged the findings presented.

'I The inspectors asked the licensee whether any of the material examined during the inspection should be considered proprietary.

No proprietary information was identifie PARTIALLIST OF PERSONS CONTACTED Licensee D. Alexander, Manager, Regulatory Affairs C. Burton, Director, Site Operations B. Clark, General Manager, Harris Plant R. Field, Manager, Nuclear Assessment T. Hobbs, Acting Manager, Operations J. Holt, Manager, Outage and Scheduling G. Kline', Manager, Harris Engineering Support Services J. Scarola, Vice President, Harris Plant B. Waldrep, Manager, Maintenance E. Wills, Manager, Environmental 8 Radiation Control NRC B. Bonser, Chief, Reactor Projects Branch 4 R. Laufer, Harris Project Manager, NRR

~Oened None ITEMS OPENED, CLOSED, AND DISCUSSED Closed None Discussed None