IR 05000324/1980014
| ML19318B899 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/20/1980 |
| From: | Kellogg P, Ouzts J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19318B895 | List: |
| References | |
| 50-324-80-14, 50-325-80-17, NUDOCS 8006300266 | |
| Download: ML19318B899 (5) | |
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NUCLEAR REGULATORY COMMISSION
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I 101 MARIETTA sT., N.W., SUITE 3100 h
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ATLANTA, GEORGIA 30303
Report Nos. 50-324/80-14 and 50-325/80-17 Licensee: Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Facility: Brunswick I and 2 Docket Nos. 50-324 and 50-325 License Nos. DPR-62 and DPR-71 Inspection at Bruns ick ite near Southport, NC 8.76 O
Inspector:
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J. E. 'Ouzts t
Date Signed
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Accompanied by:
A. K. Hardin Approved by ICl4 do d
P.J.Kellogg,Act{ngSectionChief,RONSBranch Date ' Signed SUMMARY Inspection on March 31 through May 2, 1980 Areas Inspected This routine, announced inspection involved 106 inspector-hours onsite in the areas of control room observations, review of operator logs, tagout of systems, tours of vital areas, physical security, radiation protection, housekeeping and cleanliness, l
fire protection, observation of maintenance, observation of surveillance and review and followup on licensee event reports.
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Unit 1 Areas Inspected This routine inspection involved 56 manhours of inspection time onsite in ten areas
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identified above.
Unit 1 Findings
i Of the ten areas inspected no apparent items of noncompliance or deviations were
identified.
Unit 2 Areas Inspected This routine inspection involved 50 manhours of inspection time onsite in ten areas identified above.
Unit 2 Findings Of the ten areas inspected, no apparent items of noncompliance or deviations were identified.
8006300 26 h
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v DETAILS 1.
Persons Contacted Licensee Employees A. C. Tollison, Plant General Manager J. H. Brown, Operations Manager G. T. Milligan, Maintenance Manager J. A. Padgett, QA and Safety Director W. M. Tucker, Administrative and Technical Manager Other licensee employees contacted included construction craftsmen, 3 techni-cians, 10 operators, 3 mechanics, 6 security force members, and 4 office personnel.
Other Organizations N. C. Department of Human Resources Officials Brunswick County Officials 2.
Exit Interview The inspection scope and findings were summarized on April 4,18, and May 2, 1980, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
The inspector conducted plant tours, performed surveillance of plant opera-tions and inspected plant conditions as identified below:
a.
Control Room Observations b.
Operator Log Review c.
System and Component Tagout d.
Tours of Accessible Vital Areas e.
Physical Security Protection f.
Radiation Protection g.
Fire Protection h.
Housekeeping and Cleanliness
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As a result of these inspection activities no items of noncompliance or deviations were identified.
6.
The inspector followed up on the following unit I reactor trips that occurred during this inspection period.
At 1310 on April 3, 1980, unit I reactor tripped on low water level at a.
89% power when feedwater pump tripped due to loss of 4160 volt ID bus.
b.
At 0450 on April 8, 1980, Unit I reactor tripped from 55% power due to turbine trip.
c.
At 1231 on April 16, 1980 Unit I reactor tripped from about zero power due to turbine trip.
As a result of the followup on these reactor trips, no items of noncompliance or deviations were identified.
7.
The following licensee event reports (LER's) were reviewed to determine that the information provided met NRC reporting requirements, that the description of the event and corrective action were adequate, and to eval-uate the relative safety significance of the events and any potential generic problems.
LER No.
Date Event 1-80-02 01/06/80 Chloride Intrusion Monitoring Inoperative 1-80-06 02/25/80 Containment Atmosphere Monitoring Problems 1-80-07 01/14/80 Torus Level Instrument Problem 1-80-14 02/14/80 Suppression Pool Level Switch Problem 1-80-15 03/14/80 Torus Suction Valve Switch Problem
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1-80-16 02/14/80 RHR Pump Trip 1-80-18 02/13/80 Torus Drained about 5500 gallons due to Valve Left Open 1-80-20 02/06/80 RIP Valves CAC-AQH-1260, 1261 and 1262 Closed.
1-80-21 03/04/80 RHR Service Water Pump Failed to Start Due to Suction Isolation Valve Shut 1-80-22 03/18/80 CAC-AR-263 Hose Clogged and Inoperative l
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s-3-LER No.
Date Event 1-80-25 04/05/80 CRD Core Display Inoperative 1-80-27 03/19/80 SBGT Breaker would not reset 1-80-29 03/23/80 HPCI Discharge Valve Opening Time
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Incorrect 2-80-03 01/03/80 Hi Reactor Vessel Conductivity 2-80-05 01/05/80 High Drywell Pressure Switch Isolation Valve Shut.
2-80-07 02/04/80 Battery Inverter Trip on Under Voltage 2-80-08 01/10/80 MOV Solenoid Failure 2-80-09 01/14/80 Loose Wiring Connection in CAC-A7-1259-1 2-80-10 01/14/80 MCPR Limit Exceeded 2-80-11 01/10/80 CAC-TR-1258-temperature recorder problem 2-80-13 01/16/80 CAC-AQH-1260-Lead Shorted to Ground 2-80-14 01/16/80 Operator Error During Torus Fill 2-80-15 02/01/80 Suppression Pool Level Indication Isolated 2-80-17 01/18/80 Snubber Inspection Missed 2-80-18 02/05/80 Snubber Found Inoperative 2-80-20 01/23/80 Recirculation Pump Tripped Due to Blown Fuses 2-80-22 02/06/80 RIP Containment Isolation CAC-AQH-R60, 1261 and 1262 Problem 2-80-25 03/18/80 Refueling Interlock Links Problem 2-80-28 02/12/80 RCIC Exhaust Diaphragm 2-80-32 02/16/80 CAD Tank Level Problem 2-80-38 02/29/80 Recirculation MG Set Trip
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The corrective action indicated for each of the above events were determined to be adequate. No items of noncompliance or deviations were identified.
8.
On April 16, 1980, the inspector witnessed maintenance on No. 3 diesel generator engine to replace a damaged cylinder head resulting from failure of valve seat. No items of noncompliance or deviation.s were identified.
9.
On April 22, 1980, the inspector witnessed the performance of periodic test PT 45.2.11, " Steam Line Low Pressure Time Response - B21-PS-N015B". No items of noncompliance or deviations were identified.
10.
Acceptance Criteria The inspector used one or more of the following sources of acceptance criteria for evaluating the above areas inspected:
(a)
10 CFR 50, Appendix "B" (b)
10 CFR 20 (c) Technical Specifications (d) ANSI N45.2.3 (1971)
(e). ANSI N18.7 (1972)
(f) Regulatory Guides (g) Site Security Plan (h) Quality Assurance Program (
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