IR 05000324/1990012
| ML20042E799 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/25/1990 |
| From: | Conlon T, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20042E795 | List: |
| References | |
| 50-324-90-12, 50-325-90-12, NUDOCS 9005030143 | |
| Download: ML20042E799 (7) | |
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- g,4%g NUCLEAR REOULATORY COMMISSION UNITED STATES
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REGION il h
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101 MARIETTA STREET,N.W.
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ATLANT A. GEORGI A 30323 4*
' e.,, **g Report Nos.: 50-325/90-12 and 50-324/90-12 Licensee:
Carolina Power and Light Company-P. O. Box 1551 Raleigh, NC 27602 Docket Nos.:
50-325 a;a. 50-324 License Nos.:
OPR-71 end DPR-62
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Facility Name:
Brunswick 1 and 2 j
Inspection Conducted: March 19-23, 1990
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Inspector:
O M/M g/25/ 90 s
J. R.? Harris Date' Signed
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Approved by: T. W rM Mtf /Po
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T. Conlon, Chief Date Signed
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Plant System Section Engineering Branch Division of Reactor Safety
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SUMMARY
Scope:
This routine, unannounced inspection was conducted in the areas of fire protection / prevention and followup on a sprinkler issue.
Results:
In the areas inspected, violations or deviations were not identified.
During this inspection, the inspector verified that the licensee meets the NRC Fire Protection requirements.
No weaknesses were t identified during this inspection.
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REPORT DETAILS l'
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1.
Persons Contacted l
Licensee Employees
- C. Blackmon, Manager Operations Support and Radwaste
- G. Cheatham, Manager Environmental and Radiation Control
- W. Dorman, Manager Quality Assurance and Quality Control i
- J. Harness, Brunswick Nuclear Plant Manager
- A. Healer, Superintendent Radwaste and Fire Protection
- R. Helme, Manager of Technical Support
- M. Jones, Manager on Onsite Nuclear Safety
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- D. Moore,-Engineering Unit Manager-
- T. Mull, Fire Protection. Specialist Operations T
- P. Poulk, Supervisor of Regulatory Compliance
- W. Simpson, Manager Site Planning and Control
- R. Warden, Maintenance Manager NRC Resident Inspector l
- 0 Nelson, NRC Resident Inspector
- Attended exit interview
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2.
Fire Protection Prevention Program (64704)
The inspectors reviewed the following Fire Prevention / Administrative Procedures Procedure No.
Title FPP-003 Fire Brigade Training l
FPP-005 Fire Watch Qualification
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FPP-006 Portable Fire Fighting Equipment FPP-013 Weekly Fire Inspection and Plant Housekeeping FPP-014 Control of Combustibles and Transient Loads FPP-015 Fire Barrier Penetration Seal Work Control FPP-019 Fire Investigation and Reporting FPP-031 Fire Brigade Roster These procedures were found to comply with the NRC guidelines in the document entitled, " Nuclear Fire Protection Functional Responsibilities, Administrative, Controls and Quality Assurance," dated June 14, 1977.
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Fire Protection Surveillance Procedures
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-The inspector reviewed the following fire protection surveillance procedures:
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Procedure No.
Title a
i PT-34-2.5.0 Fire Suppression System Control Valve Position. Verification
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PT-34.6.4.6 Hose Station Inspection Control Building)- and Radwaste Buildings (Monthly PT-34.5.3.1 HPCI High Pressure CO Operability
Test (Annual)
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PT-34.6.4.4 Diesel
' Generator Building Sprinkler and Spray System Visual Inspection (18-Months)
PT-34.11.1.0 Hydrant Hose Cabinet and Sprinkle Gauge Pressure Inspection (Monthly)
PT-34.4.2.0 C0 Cylinder Weight Verification
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(Six Months)
l PT-34.2.3.3 Hose Station Inspection, Control l'
Building) and Radwaste Building
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(Monthly The above surveillance procedures were reviewed to determine if the~
various test outlines and inspection instructions adequately implement the requirements of the fire protection Technical Specifications.-
In addition, these _ procedures were reviewed to determine if the inspection and test instructions followed-General Industry Fire Protection Practices, NRC Fire Protection Program Guidelines, and the guidelines of the National Fire Protection Association (NFPA) fire codes.
Based on this review, it appears that the above procedures are satisfactory.
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Fire Protection System Inspections and Tests The inspector reviewed the following surveillance inspection and test records for the dates indicated:
PT-34.2.5.0 Fire Suppression System Control Valve Position Verification (Monthly) September 89 through
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March 6, 1990
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PT-34.11.1.0 Hose House Inventory (Monthly) July 1989 through-t February 1990 PT-34.4.2.0 C0 Cylinder Weight Verification -(Six Months)
July 8, 1989 ar.d January 17, 1990
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PT-34.2.3.3 Hose -Statio.1 Inspection Control Building and Radwaste Building (Monthly): September 1989 through February 1990-FPP-013 Weekly Fire Inspection' and Plant Housekeeping January.1990 to March 1990
The surveillance test records associated with the above fire protection system surveillance tests / inspections: were found to be
satisfactory with regard to meeting the requirements of the plants Fire Protection Specifications, d.
Fire Protection Audits The most recent insurance audit reports of the Brunswick Fire Protection Program were reviewed.
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l Nuclear Mutual Limited Audit Conducted December 1-2, 1988 Nuclear Mutual Limited Audit Conducted November 15-16, 1989 l
These audits reconsnended several program improvements. The licensee I
has rAther implemented the corrective actions associated with these i
audit findings or a scheduled date for completion of the corrective
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actions has been established.
The licensee appears to be taking the appropriate corrective actions on these audit findings.
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Fire Brigade (1) Organization The fire brigade is composed of six shifts of fully dedicated
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fire brigade personnel from the operations. staff.
The brigade leader is normally one of the ~ Senior Reactor Operators and the remaining fire brigade members are composed of Auxiliary Operators-and a Radwaste Representative. The inspector reviewed the "on Shift Duty Rosters" for each of the weeks of February and March 1990 and verified that sufficient qualified fire brigade personnel were on duty to meet the provisions of Technical Specification 6.2.2.
In addition, the inspector verified that sufficient personnel were assigned to each shift to meet the minimum operating and fire brigade staff require-ments of the Technical Sxc.1fications.
Therefore it appears based on the review of tw duty rosters associated with the above dates, that there was sufficient manpower on duty to meet
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both the operational and fire brigade requirements of the plant
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Technical Specifications.
(2) The inspector reviewed the training and drill records for four Senior Reactor Operators, ten Auxiliary Operators and two Radwaste Representatives for 1990 and the first three quarters of 1989.
The records reviewed ir.dicated that each of these individuals had received an annual medical review, attended the required training, and participated in the required number of drills. The inspector also verified that the required amount of operators were on shift in the control room of Units 1 and 2 in the event of a fire, f.
Plant Tour (1) Outside Fire Protection Walkdown The inspector verified that the two fire protection water storage tanks contained sufficient water to n2et the require-mentt tf the Technical Specifications.
The two fire pumps
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locatv.i in the water treatment building were inspected and found to be inservice.
The following fire protection valves within the Water Treatment Building for fire pump alignment were inspected and verified to be properly aligned:
2-FP-V53 Diesel Fire Pump Discharge Valve
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2 FP-V54 Moto-Fire Pump Discharge Valve
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2-FP-V57 Suction Valve fe w Fire Protection Tank
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The following sectional control valves in the fire protection water sup)ly system were inspected and verified to be properly aligned and locced in position:
2-FP-PlV-33 Unit 2 Reactor Building Sprinkler Deluge Supply Valve P
2-FP-PIV-34 Diesel Generator Building Fuel Oil Vault Deluge Supply Valve 2-GP-PIV-44 Diesel Generator Building Deluge Supply Shutoff Valve 2-FP-PIV-49 Ring Header Sectionalizing Valve A tour of the exterior of the plant indicated that sufficient clearance was provided between permanent safety-related buildings and structures and temporary buildings, trailers a'nd other transient combustible materials, The general housekeeping of the areas adjacent to the permanent plant structures was satisfactory.
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(2)
Inside Plant Tour A plant tour was made by the inspector.
During the plant tour
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the following safe shutdown related plant areas and their related fire protection features were inspected.
Diesel Generator Building-2 and 23' elevation Service Water Building-4, 20' elevation Reactor Building Unit 1-17 to 117' elevation Control Building-23 to 49' elevation Turbine Building Unit 1 1 - 20' elevation
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Turbine Building Unit 2 1 - 20; elevation The inspector visually inspected the fire smoke detection, r
sprinkler protection, portable extinguishers, hose stations, emergency lights and fire barriers associated with the above plant areas.
Based on the visual inspection, it appears that the fire protection features associated with the above plant areas were properly maintained and fully functional.
3.
(0 pen)IFI 89-40-02 Sprinkler Issue
Concerns over potential steam leaks on the -17ft elevation of the Reactor Building 1 and 2 which are postulated to cause the following system
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interactions:
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Fire detection system activation, the ionization smoke detectors will
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be tripped by the steam.
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Sprinkler system deluge valve trip as the result of detection system
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actuation.
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Sprinkler heads (165'F) fuse open as the result of high ambient
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temperature, releasing water into the area.
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Water spray from sprinkler system causes decrease in ambient temperature, causing steam leak detection system sensors to fail to detect high temperatures / steam leak conditions, which would result in failure to initiate automatic steam line isolation.
This failure mode is of concern in that the sprinkler heads are generally set to fuse open at approxi-
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mately 165'F, while the steam leak detection sensors have setpoints ranging from 165'F to 190*F.
A plant modification is being implemented to replace the sprinkler heads throughout the -17f t elevation of the Unit I and 2 Reactor Building.
Installation of the new sprinkler heads will establish sufficient margin between the sprinkler systems and the Steam Leak Detection Systems (SLDS)
to ensure that in the event of a steam leak, SLDS actuation will consistently occur prior to steam induced sprinkler discharge.
In-addition, the moderate increase in sprinkler actuation temperature will not compromise the intent to provide relatively fast acting, responsive P
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systems in the RHR equipnent area, and, in particular in the -17 elevation
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separation ren:
The existing sprinkler head which activate at 165'F are being replaced with sprinkler heads which activate at 212'F.
This replacement will
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include the Appendix R Separation Zone, excluding the 400'F sprinkler l
i heads located above the RHR lines.
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The sprinkler heads were replaced in the -17 elevation of the Unit 2-
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reactor building under plant modification 90-007. This work was completed on March 9, 1990. The sprinkler header in Unit I reactor building will be l
replaced under plant modification 90-006 in April, 1990.
4.
Exit Interview l
The inspection scope and results were summarized on March 23, 1990, with those persons indicated in paragraph 1..The inspector described the areas inspected and discussed in detail the inspection results.
The licensee did not identify as proprietary any of the material provided to or
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reviewed by the inspector during this inspection.
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