IR 05000324/1979023

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IE Insp Repts 50-324/79-23 & 50-325/79-24 on 790716-20.No Noncompliance Noted.Major Areas Inspected:Licensee Followup Lers,Outstanding Items Re Comments on Operating Procedures & Electric Relay Problem
ML19209C974
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 08/30/1979
From: Kellogg P, Riley B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19209C972 List:
References
50-324-79-23, 50-325-79-24, NUDOCS 7910180535
Download: ML19209C974 (6)
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f **00q'o UNITED STATES v

  • t NUCLEAR REGULATORY COMMISSION g

ae REGION 11

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101 MARIETTA ST., N.W., SUITE 3100 o

ATLANTA, GEORGIA 30303

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Report Nos. 50-325/79-24 and 50-324/79-23 Licensee: Car tina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Brunswick I and 2 License Nos. DPR-71 and DPR-62 Inspection at Southport, North Carolina Inspector:

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P. J. Kellogg, tion Chief, RONV Branch Dafe Signed SUMMARY Inspection on July 16-20, 1979 Areas Inspected This routine unannounced inspection involved 34 inspector-hours onsite in the areas of review of Ii rensee Event Reports, followup on unresolved item concerning water accu.nulation in Reactor Building lower rooms, followup on outstanding item conceraing ec.anents on operating procedures, review licensee action on vendor letter concerning electrical relay problem and plant tour.

Results Of the five areas inspected, no items of noncompliance or deviations were identified.

1177 )l0 7910180

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DETAILS 1.

Persons Contacted Licensee Employees

  • A. C. Tollison, Jr., Plant Manager
  • C. R. Gibson, Superintendent, Administrative and Technical
  • S. E. Thorndyke, Operations Supervisor W. L. Triplett, Administrative Supervisor K. E. Enzor, Maintenance Supervisor
  • G. T. Milligan, Engineering Supervisor
  • J. Davis, Mecahnical Engineer
  • R. M. Poulk, NRC Coordinator NRC Resident Inspector
  • J. E. Quzts
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on July 20, 1979 with those persons indicated in Paragraph 1 above.

3.

Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (324/325-78-25-01) The inspector reviewed the licensee's written report dated June 1, 1979 concerning w.ter accumulation in RFR and HPCI pump rooms; and the corrective actions cospleted to date.

The inspector verified completed carrective actions and reviewed status of further planned actions.

Pending completion and further review by the inspector, this item will remain open.

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Licensee Event Report Review The licenree event reports listed below were reviewed in-office for poten-tial generic problems, to detect trends, to determine if the information provided meets NRC reporting requirements and to censider whether corrective action discussed appeared appropriate. Selected reports as denoted, were further reviewed at the site to verify adequacy of information provided, corrective action taken, and compliance with Technical Specifications and other regulatory requirements. The inspector examined selected internal reports and correspondence, records and discussed events with appropriate personnel.

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LER No.

Date Event Unit 1 79-045 6/22/79 Drywell oxygen analyzer erratic reading 79-039 6/13/79 1B SBGT inoperable 79-037

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5/15/79 APRM rod block upscale alarm drift 79-036 6/2/79 Pipe snubbers inoperable 79-035 5/17/79 Failure to report inoperable coolant sampling 79-034 5/10/79 Failure of drywell equipment drain recorder 79-032 5/14/79 RCIC valve motor failure 79-031 5/12/79 Containment oxygen monitor instrument drift 79-030 5/8/79 Main steam flow instrument line plugged

  • 79-021 4/20/79 Drywell atmosphere monitor inoperable
  • 79-016 4/17/79 Portion of five protection system inoperable
  • 79-015 3/8/79 Pipe snubber failed test 79-014 5/19/79 Containment atmosphere dilution tank level low 79-013 4/6/79 Missed surveillance tests79-012 4/25/79 Control Rod 34-27 no position indication at notch 34 79-011 4/19/79 Drywell vent line isolation valve failed to close

'4 1/5/79 Containment atmosphere dilution tank level low 79-003 1/17/79 HPCI Steamline isolation instrument drift 79-002 1/23/79 SBLC relief valve setpoint low 79-001 1/4/79 HPCI system response time failure 78-096 12/11/78 Loss of normal power to bus E-1 1177 312

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-3-LER No.

Date Event 78-093 12/2/78 Control Rod 02-23 notch 18 and 28 position indication inoperable 78-092 12/19/78 Pipe supports not installed per design 78-083 10/14/78 RCIC turbine manual reset inoperable 78-082

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11/1/78 10 CFR 50 nonconformanc=

78-077 10/6/78 CSi low level switch inoperable 78-075 10/4/78 ADS logic switch did not actuate Unit 2 79-052 7/2/79 Inadequate pipe supports79-051 6/20/79 Drywell atmosphere monitor pump problem 79-049 A/19/79 Drywell oxygen level above limit 79-047 o/17/79 Drywell atmosphere monitor tripped 79-046 6/27/79 Condensate conductivity recorder inope: J 1e 79-045 6/13/79 Dryweli oxygen monitor problem 79-044 6/12/79 Drywell.tmosphere sample inoperable

  • 79-042 6/6/79 SLC tank level and concentration low 79-040 6/14/79 Condensate conductivity cell inoperable 79-039 5/19/79 Containment air lock test late 79-038 5/21/79 Diesel generator frequency problem 79-037 5/19/79 Drywell oxygen monitor out of calibration 79-036 5/7/79 Pipe snubbers failed visual inspection 79-034 5/10/79 FW valves excess leakage 79-032 4/25/79 Pipe snubbers failed visual inspection 79-031 5/10/79 MSIV excess leakage 79-030 4/25/79 Pipe snubbers failed functional test 79-029 6/2/79 Pipe snubbers inoperable
  • 79-028 5/10/79 Torus hatch open on reactor startup 79-027 6/4/79 MSIV switches out of tolerance 79-026 5/7/79 HPCI suction transfer switch inoperable 79-024 5/10/79 Drywell equipment drain tecorder inoperable 79-021 7/2/79 Pipe snubbers inoperable 79-020 4/21/79 SLC relief valve setpoint low 79-019 4/20/79 SBGl' motor lead splice failure
  • 79-017 4/4/79 RHR pumps failed to start 79-016 2/26/79 Diesel generator trip 79-015 2/23/79 RHR wiring logic error 79-012 2/19/79 Pipe snubber loose hardware 79-011 4/19/79 Pipe snubbers failed visual inspection 79-010 3/15/79 LHGR incorrect limit value 79-009 2/7/79 Pipe snubber improper seal material 79-008 3/1/79 EPCI speed governor os:illation 79-007 2/27/79 Pipe whip restraint not per design 117/

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LER No.

Date Event 79-006 1/13/79 LPCI loop inoperable 79-005 1/9/79 RHR pump logic switch failure 79-004 1/10/79 Drywell atmosphere sample pump failure 79-003 1/30/79 MSIV stem-disc separation 79-002 1/15/79 Diesel generator failed retest 79-001

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1/2/79 Reactor low level switch setpoint drift

  • Denotes reports which were further reviewed at the site.

Corrective action taken or being taken was determined to be satisfactory.

The it.speccor noted and discussed with the plant manager four of above reports (1-79-021, 1-79-017, 1-7S-015, 2-79-011) due in thirty days were submitted from one to ten days late.

The three most delinquent had been previously identified by the licensee as being late. Tae Plant Manager stated corrective actions to prevent recurrence were bEing taken. The adequacy of these actions will be judged as future reports are received and evaluated.

No items of noncompliance or devateas were ident.ified by the inspector.

6.

Licensee Action on NRC Operator Licensing Branch Comments The inspector and resident inspector conducted a areliminary review of licensee actions on changes to operating procedures.

These changes were incorporated following plant review of procedures comments from J. J. Buzy, NRC Operator Licensing Branch.

These changes will be further reviewed by J. J. Buzy.

7.

Licensee Action on Vendor Identified Problem The vendor of certain inductioL disc protection relays had identified a problem possibly caused by the migration of petroleum jelly resulting in higher than normal pick-up values.

The vendor had issued a Service Advice bulletin identifying this problem.

Initial checking by the licensee did not reveal that such information had been supplied or received on site.

The licensee stated he would pursue this matter further based upon details furnished by the inspectcr. This item will be reviewed further on subse-quent inspections.

E.

Plant Tour The inspector toured Unit I and 2 Reactor and Turbine buildings, Control Roors, Battery and Switchgear rooms and Radwaste and Diesel Generator buildings. The inspector observed and the licensee was aware of feed water line leaks in IB Feed Pump Room.

The battery rooms of Un t 1 and 2 showed evidence cf poor housekeeping practices; rags, paper, rubber gloves were found arc and equipment and floor areas.

In discussing these concerns with

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plant management it was believed tinat doors to the battery rooms were previously maintained locked and the current unlocked status of these doors may have occurred as a result of expanding boundaries of secure vital The licensee stated these rooms would be cleaned and the possi-areas.

bility or limiting access (non-security basis) would be reviewed to prevent unauthorized personal traffic and attendent housekeeping problems. The inspector also observed the loading dock area outside of the radwaste building as needing more housekeeping attention.

The licensee stated continuing efforts are being applied toward housekeeping in that area. A tour of the diesel generator building indicated housekeeping problems in piping trenchs and in some 4.reas under diesel engines regarding varying degrees of fuel oil accumulation and general foreign materials in part due to extensive recent construction activity in this building.

The licensee stated that attention and actions would be applied toward resolving these matters. No items of noncompliance or deviations were identified.

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