IR 05000259/1987021

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Insp Repts 50-259/87-21,50-260/87-21 & 50-296/87-21 on 870527-29.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection/Prevention & Followup on Previous Insp Items
ML20234D691
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/15/1987
From: Conlon T, Miller W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20234D684 List:
References
50-259-87-21, 50-260-87-21, 50-296-87-21, GL-82-21, GL-86-10, NUDOCS 8707070305
Download: ML20234D691 (5)


Text

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Report Nos.: 50-259/87-21, 50-260/87-21, and 50-296/87-21 Licensee: Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Docket Nos.- 50-259, 50-260 and 50-296 License Nos.: DPR-33, DPR-52, and DPR-68 Facility Name: Browns Ferry 1, 2, and 3 Inspection Conducted; May R7-29, 1 87 Inspector f gM{ SQL clPI) b~"IV l W. H. Millir, J ' Date Signed Approved by:f- , M4 T. E. Conlon, Sec' tion Chief

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Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, announced inspection was in the areas of fire protection / prevention and followup on previous inspection finding Results: No violations or deviations were identifie ]

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I REPORT DETAILS 1 Persons Contacted Licensee Employees l l

  • R. L. Lewis, Plant Manager l
  • C. Madden, Compliance Engineer ];
  • J. R. Kern, Fire Protection Supervisor T. R. Davis, Fore Protection Group Other licensee employees contacted included engineers, technicians, operators, mechanics, security force members, and office personne NRC Resident Inspectors
  • G. L. Paulk
  • C. Brooks -
  • C. A. Patterson
  • Attended exit interview ] Exit Interview

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The inspection scope and findings were summarized on May 29, 1987, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The licensee did not identify as proprietary any of the materials provided j to or reviewed by the inspector during this inspection ] Licensee Action on Previous Enforcement Matters (Closed) Unresolved Item (259, 260 and 296/81-01-09) Corrective Action to be Taken on Triennial Fire Protection Audit. TVA has made a detail review of the fire protection features at Browns Ferry and compared these features with the NRC guidelines of NUREG 080 Items or features which do not meet these guidelines are to be modified to conform to the guidelines or appropriate justifications are to be submitted for NRC revie This evaluation is being tracked by TVA item NC0 86-0326-104 and the specific Region II audit items of concern are being tracked by TVA item SLT 86-1032-00 The commitment for TVA to evaluate / review Browns Ferry for compliance to the NRC guidelines of NUREG 0800 and provide a modification schedule prior to startup is included in Nuclear Performance Plan Volume This unresolved item was not based on regulatory requirement. This item is close ,

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b. (Closed) Unresolved Item (259, 260 and 296/82-15-07) Fire Protection Technical Specifications. The Technical Specifications have been revised to indicate that the applicability of the fire protection systems applies only to the applicable fire suppression and/or-detection systems installed for the reactor building, diesel building, control bay, intake pumping station, and cable trays along the south wall of the turbine building at 586' elevation. The cable

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tunnel has a fire detection system but does not have a fire suppression syste This was reviewed and approved by the NRC following the 1975 fir Therefore, it appears that a fixed suppression system is not required for this area. TVA has proposed to remove all fire protection features from the Technical Specifica-tions as permitted by Generic Letter 86-10. This item is close c. (Closed) Unresolved Item (259, 260 and 296/82-15-08), Fire Protection Piping 1.eak All deteriorated and leaking fire protection piping within che plant is to replaced prior to startu The main feed piping to the AFF foam systems for the motor generator sets have experienced a number of leaks and is to be replaced. Repairs are to be made using higher quality ASTM A106 Grade B piping in lieu of the original specified ASTM A53 grade piping. Appropriate corrective actions have been taken and as future leaks occur appropriate repairs will be made. This item is being tracked by TVA item No. SLT-86-1033-001 and is therefore close d. (Closed) Unresolved Item (259, 260 and 296/84-17-04), Unsupervised Sprinkler System and Fire Pump Actuation, Circuits.- This item has been evaluated by TVA as part of the detail Browns Ferry fire protection evaluatio Refer to above unresolved item 259, 260 and 296/81-01-09. TVA's final report will either provide a schedule date that these items will be corrected or provide sufficient justification as to why modifications are not required. The Report will be reviewed by the NRC staff. Therefore, this item is close e. (Closed) Unresolved Item (259, 260 and 296/84-17-05), Unsupervised C0 System Actuation Circuit To offset this-discrepancy TVA has initiated a monthly surveillance using procedure SI-4.11.C.1&5, system operability Testing for the COof2Smoke systemsand Heat in the Detectors, diesel to verify generator buil CO, ding This meets the intent of the NRC requirements. Therefore, this item is close f. (Closed) Unresolved Item (259, 260 and 296/84-17-09), Inadequate Onsite foam Capabilities. TVA has made an agreement with the nearby offsite Clement Fire Department who has a mutual aid agreement with a nember of area fire departments. These departments have sufficient manpower and equipment, including foam, to combat a major fir This resolves the inspector's concerns and closes this ite .

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I J (Closed) Violation (259, 260 and 296/86-09-02), Failure to Staff !

Annual Fire Protection / Prevention Audit Team with Qualified Fire

Protection Personne TVA's letter of June 20, 1986 to the NRC ,

Region II states that fire protection engineering personnel from 1 other internal TVA organizations are to be used to conduct future fire protection audits. The most recent April 1987 audit utilized a fire protection engineer from TVA's Division of Property and i Services. This appears to meet the intent of NRC Generic Letter j 82-21 and closes this ite l (Closed) Violation (259, 260 and 296/86-09-03), Failure to Include Piping Fire Barrier Penetrations Into a Surveillance Program. TVA has inspected all mechanical fire barrier penetrations and all identified installation discrepancies have been included in a repair program. Approximately 80% of the identified discrepancies have been corrected as required by a contracto The remaining discrepancies are to be repaired by on-site TVA personne The contractor is developing a surveillance inspection procedure which will identify all penetrations, type of construction, configuration, etc. for use during future surveillance to verify that all fire barrier penetrations are functional. This work which is being tracked by TVA NC0 86-0232-003 and 004 is scheduled to be completed by July 16,

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i 1987. This item is close ,

4. Unresolved Items Unresolved items were not identified during this inspectio . Fire Protection Program Review The inspector accompanied the site Fire Protection Supervisor on a plant tour necessary to complete surveillance procedure SI 4.11.D1 Fire Protection System Monthly Inspection. No significant discrepancies were identifie ,

6. Inspector Followup Items (IFI)

i (Closed) IFI (259/80-16-04, 260/80-13-02 and 296/80-14-04), '

Delinquent in Fire Protection Trainin Fire protection and prevention training is included in the general employee training progra Standard Practice BF-4.5, Plant General Employee Training ;

Program, requires fire protection training to be given to all 1 personnel who work within the industrial plant area. This training is required prior to personnel being badged and is repeated every two years. This item is close k l

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b. (Closed) IFI (259, 260 and 296/84-17-01), Deluge Valve Trim Set Discrepancies, TVA's 10 CFR 50 Appendix R fire protection evaluation has eliminated the need for these cable tray spray fire protection syste Therefore, these systems are either to be removed or disconnected which will eliminate the need to make any modification However, the trim configurations have been evaluated and found to be functional and the "As-Built" drawings are to be revised to reflect the installed configuration The pre-action systems are to remain in service and will be upgraded to meet the manufacturer's requirements or equivalent configuration. This commitment is in Nuclear Performance Plan, Volume This item is close c. (Closed) IFI (259, 260 and 296/84-17-02), Blocked Manual Deluge Valve Actuation Stations. The cable tray deluge systems are either to be removed from service or disconnected. Therefore, no modifications are to be made on these system Refer to item 259, 260 and 296/84-17-01 for additior.al ir. formation. This item is close d. (Closed) IFI (259, 260 and 296/84-17-03), Inadequate Deluge Test Trip Pressur The use of 75 psi air pressure in lieu of water pressure to test the operability of the deluge systems was evaluated by TVA and found to be acceptable. This item is close e. (Closed) IFI (259, 260 and 296/86-09-01), Fire Protection Procedures Do Not Meet NRC Guidelines. Procedurc FFP-1, Fire Protection Program l Plan (Revisions 1 and 2) has been revised to incorporate the items i not previously covered. This item is closed, j l

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