IR 05000324/1988012
| ML20151A151 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/22/1988 |
| From: | Conlon T, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20151A149 | List: |
| References | |
| 50-324-88-12, 50-325-88-12, NUDOCS 8804060319 | |
| Download: ML20151A151 (7) | |
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. R80vgo SQ URITED STATES
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NUCLEAR REGULATORY COMMISSION
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j 101 MARIETTA STREET. N.W.
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ATL ANT A, GEORGI A 30323
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Report Nos.: 50-325/88-12 and 50-324/88-12
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licensee: Carolina Power and Light Company i
P. O. Box 1551 (
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Raleigh, NC 27602
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Docket Nos.:
50-325 and 50-324 License Nos.:
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Facility Name: Brunswick 1 and 2 l
Inspection Conducted:
February 22-25, 1988
Inspector:
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G. R. Wiseman Date Signed l
Approved b h
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T. E. Conlon, Section Chief Date Signed j
Engineering Branch
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I Division of Reactor Safety i
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SUMMARY
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Scope:
This routine, unannounced inspection was in the areas of Fire
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Protection / Prevention, Review of the Status of Appendix R Fire Protection l
Modifications, and Previousiv Identified Inspection Items.
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Results: de violations or deviations were identified.
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8804060319 880329 i
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- D. Anderson, Project Engineer
- C. F. Blackmon, Superintendent Fire Protection /Radwaste
- A. G. Cheatham, Manager, Environmental and Radiation Control
- C. R. Dietz, General Manager
- E. R. Eckstein, Manager, Technical Support
- R. E. Helme, Director On-site Nuclear Safety
- L. E. Jones, Director, QA/QA
- M. B. Kesmodel, Supervisor, Document Control
- T. Mull, Fire Protection Specialist, Operations
- D. E. Novotny, Senior Specialist, Regulatory Compliance
- J. O'Sullivan, Manager, Maintenance
- M. J. Pastra, Specialist Regulatory, Compliance
- R. Porterfield, System Engineer, Technical Support
- B. Pullen, Engineer, Engineering and Construction Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security force members, and office personnel.
NRC Resident Inspector
- W. Ruland
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 25, 1988, with those persons indicated in Paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
No new items were identified during thb inspection.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addra sed in the inspection.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Fire Protection / Prevention Program (64704)
a.
Fire Prevention / Administrative Control Procedures The inspector reviewed the following Fire Prevention / Administrative Procedures:
Procedure No.
Ti tle FPP-005 (Rev. 3)
Fire Watch Qualification FPP-015 (Rev. 8)
Fire Barrier Penetration Seal Work Control FPP-019 (Rev. 2)
Fire Report and Investigation EFP-03 (Rev. 0)
Engineering Fire Procedure EFP-14 (Rev. 1)
Protection of Temporary Structures Based on this review, it appears that the above procedures meet the NRC guidelines of the document entitled, "Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance," dated June 1977.
b.
Fire Protection Surveillance Procedures The inspector reviewed the following Fire Protection System Surveillance Procedures:
Procedure No.
Title PT-34.0 (Rev.7)
Operations Unit Fire Protection Periodic Test Program PT-34.1.3.0 (Rev. 4)
Diesel Generator Building Swinging Fire Door Inspection (W2ekly)
PT-34.2.3.3 (Rev. 3)
Hose Station Inspection Control Radwaste Building Building) and (Monthly PT-34.35.1.5 (Rev. 2)
Halon Extinguishing Systems Liquid Level and Cylinder Pressure Verification (Semiannual)
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The above surveillance procedures were reviewed to determine if the various test outlines and inspection instructions adequately implement the surveillance requirements of the plant's Fire
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Protection Technical Specifications.
In addition, these procedures
were reviewed to determine if the inspection and test instructions
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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
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appears that the above procedures are satisfactory, except the Fire Protection Periodic Test program does not yet include those features
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provided in plant Appendix R Fire protection modifications and the alternate safe shutdown equipment.
These features include Appendix R fire barrier cable / conduit wraps, fire barrier enclosures, fire stops, sprinkler and water curtain
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suppression systems, the halon system for the diesel generator
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basement and the Appendix R sound powered phone system.
These will
be reviewed during a future NRC inspection,
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Fire Renorts a
The inspector reviewed the station fire reports for 1986 and 1987.
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These reports indicated that there were four incidents of the fire in
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1986 and three events in 1987.
Of the fires events reviewed, approximately one-half of-the events involved equipment failures and the remainder involved welding or cutting activities.
None of the
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fire events reviewed appeared to be of major safety significance.
d.
Fire Protection Audit The most recent insurance audit reports of the Brunswick Fire
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Protection Program were reviewed. These audit were:
j Nuclear Mutual Limited audit conducted April 8-9, 1987, and
American Nuclear Insurers liability review conducted i
January 2-23, 1987.
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These audits recommended several program improvements. The licensee has either implemented tht. corrective actions associated with these i
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audit findings or a scheduled date for completion of the corrective r
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actions had been established.
The licensee appears to be taking the appropriate corrective actions on these audit findings.
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Plant Tour
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(1) Outside Fire Protection Walkdown
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The inspector verified that the two fire protection water i
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storage tanks contained sufficient water to meet the require-ments of the Technical Specifications.
The two fire pumps i
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located 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
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inspected and verified to be properly aligned:
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Diesel Fire Pump Discharge Valve 2-FP-V53
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i Motor Fire Pump Discharge Valve 2-FP-V54
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Suction Valve From Fire Protection Tank
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2-FP-V57
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l The following sectional control valves in the outside fire
protection water supply system were inspected and verified to be
properly aligned and locked in position:
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2-FP-PIV 33 Unit 2 Reactor Building Sprinkler Deluge Supply Valve j
2-FP-PIV-34 Piesel Generator Building Fuel Oil Vault Deluge Supply Valve
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2-FP-PIV-44 Diesel Generator Building Deluge Supply
Shutoff Valve t
2-FP-PIV 49 Ring Header Sectionalizing Valve j
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l A tour of the exterior of the plant indicated that sufficient
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clearance was provided between permanent safety-related i
buildings and structures and temporary buildings, trailers, and I
other transient combustible materials.
The general housekeeping
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of the areas adjacent to the permanent plant structures was
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sa cis factory.
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Inside Plant Tour l
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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 I
related fire protection features were inspected:
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Diesel Generator Building - 2', 23' elevations f
1 Service Water Building -
4', 20' elevations
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Turbine Building Unit 1 - 20' elevation
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Turbine Building Unit 2 - 20' elevation
i Control Building - 23' and 49' elevations f
Water Treatment Building
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capabilities, the manual firefighting equipment (i.e., portable t
extinguishers, hose stations, etc.) and the fire barriers walls
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associated with the above plant areas.
In addition, the i
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l inspector visually inspected the sprinkler protection associated j
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with the Service Water Building and Diesel Generator Basement.
Based on the visual inspection, it appears that the fire protec-tion features associated with the above plant areas were properly maintained and fully functional.
The plant tour also verified the licensee's implementation of the fire prevention administrative procedures.
The control of combustibles and flannable materials, liquids and gases, and the general housekeeping were found to be good in the areas inspected.
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Hydrogen Injection System The inspector reviewed Design Modification Package (86-081) for the proposed Hydrogen Injection System.
The package indicated that hydrogen piping would be routed through portions of the plant Turbine Building which is designated as a alternative shutdown area -for a fire event.
The design proposes the installation of hydrogen excess flow check valves for the plant area; however, there appears to be no calculations onsite to establish the setpoints of the check valve's shutoff limits to prevent hydrogen concentrations from exceeding the lower explosive limits in the plant area should there be gas leakage.
This issue will be reviewed during a future NRC inspection.
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Inspector Followup Items a.
(Closed) Inspector Followup Item (325, 324/82-37-03), Maintenance of Sprinkler System Deluge System Valves in the Closed Position.
The sprinkler systems for the North and South portions of the Service Water Building are designed as preaction type systems, but were being maintained as wet pipe systems pending completion of repairs to annunciator cables JUS-XN3 and JUS-XN3/1 which were inoperable due to underground shorts within the cabling routed to the control room.
This condition had existed since the sprinkler control valves were tagged out on May 30, 1983.
The corrective actions to the cabling problems were completed in 1987 by Field Revis*on 23 to Plant Modifi-cation PM-86-064.
The system was declared ops,able on June 3, 1987.
Based upon the above, this item is closed, b.
(Closed) Inspector Followup Item (325, 324/84-37-03), Reevaluation of Cable Spreading Rooms Sprinkler System Design.
The inspector reviewed Engineering Work Request (EWR) 02216A in response to this issue.
The cable spreading room sprinkler system does not meet the guidelines of NFPA 13 relative to ti,e location of the sprinkler heads to the ceiling.
The heads are fitted with heat collectors in accordance with Appendix A 1 NFPA-13.
Baffles were installed on a number of heads that appeared to adversely impact the ability of the sprinkler system to perform its intended function.
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The licensee performed an engineering evaluation (EER No. 85-0167)
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which was used to determine the spreading room equipment required to be protected from sprinkler water impingement.
The evaluation determined that baffles were not needed for most equipment and these were remsed.
The existing baffle arrangement has been minimized to approximtely seven in number to protect lighting panels and four motor control centers.
The inspector raiewed these installations which now appear acceptable to prevent water impingement and also not reduce the sprinkler system coverage.
Based on this review and inspection, this item is closed.
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(Closed) Inspector Followup Item (324/86-31-01). Improper Mounting of Smoke Detectors in the Unit 2 Cable Spreading Room and EER Areas
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The inspector reviewed Engineering Work Requests Nos.84-170, 83-130, and 84889A which approved plant modification PM-86-272.
This modification made changes to fire detection zones C2, C5 and C9 in the control building to address the NRC concerns.
This work was j
completed and declared operational on December 22, 1987. These plant areas were reviewed by the inspector on the plant walkthrough during this inspection and it appears that the modifications are acceptable, Based on the above, this item is closed.
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