IR 05000259/1990006
| ML18033B266 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 04/03/1990 |
| From: | Conlon T, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18033B265 | List: |
| References | |
| 50-259-90-06, 50-259-90-6, 50-260-90-06, 50-260-90-6, 50-296-90-06, 50-296-90-6, NUDOCS 9004230113 | |
| Download: ML18033B266 (13) | |
Text
~Pv8 REOIj Vp,0 ee A.
I nO IlA g
+eb*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report Nos.:
50-259/90-06, 50-260/90-06, and 50-296/90-06 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
Inspection Conducted:
Febuary 26 - March 2, 1990
Ins ector:
p J.
R.
arris Approved by:
T. Conlon, Chief Plant Systems Section Engineering Branch Division of Reactor Safety SUMMARY Date Signed Date cygne Scope:
This routine inspection was conducted in the areas of Fire Protection and followup on items identified during an Appendix R inspection conducted May 1-5, 1989 and July 17-21, 1989.
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 identified during this inspection.
9004M
" 'QO25-.
g 9OA40$
POP ADOCK
'
~I
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- G. Campbell, Plant Manager
- L. Clardy, equality Assurance
- R. Erickson, Technical Services
- R. Grantham, Electrical Engineering Modifications
- M. Herrel, Plant Operation Manager
- J. Hutton, Operations Superintendent
- P. Hsiel, Compliance Licensing
- T. Maddox, Fire Protection
- B. McKinney, Superintendent Technical Support
- P. Salas, Compliance Licensee Support
- F. T. Sakers, Radiation Protection Manager NRC Resident Inspectors
- D. Carpenter, NRC Site Manager
- W. Bearden, NRC Resident Inspector
- C. Patterson, NRC Resident Inspector
- Attended exit interview 2.
Fire Protection/Prevention Program (64704)
a.
Fire Protection/Administrative Control Procedures FPP-1 Fire Protection Plan, Revision 3, November 11, 1989 FFP-2 Fire Protection Attachments, Revision 4, November ll, 1989 FPP-3 Fire Protection Emergency Organization, Revision 1, July 7, 1989 Based on this review, it appears that the procedures meet the NRC guidelines of the document entitled,
"Nuclear Fire Protection Functional Responsibilities Administrative Controls and (equality Assurance,"
dated June 1971.
b.
Fire Protection Surveillance Procedures FP-0-00- INS-001 FP-0-00-INS-002 Inspection of Portable and Wheel Type Fire Extinguishers, Monthly Inspection of Fire Hose Cabinets, Reel Carts and Fire Equipment Houses, Monthly
FP-0-000-INS-007 Functional Check of Turbine Building and Service Building, Every Six Months FP-0-000-INS-023 Monthly Check of Detection System and Diesel Fire Pump Batteries FP-0-026-INS-003 Primary Hydrant Inspection Lubrication, Every Six Months FP-0-260-INS-001 quarterly Fire Door Inspection 2-SI-4.11.AI Functional Test of Smoke Detectors, Every Six Months 2-SI-4.11.Aa Functional Test of Heat Detectors, Every Six Months O-SI.4.11.8.3.c Diesel Driven Fire Pump Inspection, Every Eighteen Months O-SI-4.11.F. 1.B.
Safe Shutdown Inspection Flow Check, Every Six Months O-SI-411.G.1A Visual Inspection of Electrical Penetrations in Fire Barriers, Every Eighteen Months O-SI-4.11.
G-2A Test of Fire Door Supervisory Circuits, Monthly O-SI-4.11.G.2b Fire Door Inspections, Daily The above surveillance procedures were reviewed to determine if the various tests outlines and inspection instructions adequately implement the surveillance requirements of the plant Fire Protection Technical Specifications.
Fire Protection System Surveillance Inspections and Tests The inspector reviewed the following surveillance inspections and tests for the dates indicated:
FP-0-00-INS-001 FP-0-000- INS-002 Inspection of Portable Extinguishers, December 1,
1989 through February 23, 1990 Inspection of Fire Hose Cabinets Reel Carts and Equipment Houses, August 26, through January 30, 1990 FP-0-260-INS-003 FP-00- INS-002 Primary Fire Hydrant Inspection August 1989 through January 1990 Functional Check of Turbine Buildings, August 6, 1989 and January 9,
1990
2-SI-4.11.A.1 2-SI.4.11.
A.a Functional Test of Smoke Detectors, February 9, 1989 and July 6, 1989 Functional Test of Heat Detectors February 17, 1989 and July 16, 1989 0-SI-4. 11 B. lg2.A Yard Fire Hydrants and Hose House Flow Test, April 26, 1989 O-SI-4.11 B2A 0-SI-411 G.
2B Diesel Driven Fire Pump Operability weekly, December 89 to January 1990 Daily Fire Door Inspection September 89-January 1990 The surveillance test records and testing frequency associated with the above fire protection system surveillance test inspections were found to be satisfactory with regard to meeting the requirements of the plants fire protection program.
d.
Fire Protection Audits The most recent audit reports of the Browns Ferry plant were reviewed.
e.
Nuclear equality Audit and Evaluation Branch Audit Report B
FK 8802, conducted April 11 - April 15, 1988 Nuclear Mutual Limited Property Insurance, Audit Report LPSS-1870-C conducted October 24-27, 1988 Nuclear Mutual Limited Audit Report L10-890-725820 conducted May 30-31, June 1-2, 1989 These audits identified several findings.
The licensee has either corrected these findings or a scheduled date for correction has been implemented.
Fire Brigade (1)
The total fire brigade is composed of 28 level 1 brigade members and 22 reactor operators.
The inspector reviewed the on duty shift for the week of February 29 - March 2, 1990 and verified that sufficient qualified personnel were on duty to meet the requirements of the station procedure FPP-3, Fire Protection Emergency Organization.
(2)
The inspector reviewed the training and drill records for all the brigade members and reactor operators from the first quarter of 1989 through the first quarter of 1990.
Based on this review, it appeared that the brigade members and reactor operators
had received the required training.
In addition to the fire brigade members, the inspector verified that sufficient licensed operators were available to maintain minimum staffing in,the control room in the event of a fire.
(3)
Fire Protection Preplans The inspector reviewed the following Fire Protection Preplans:
TB2-557 Unit 2 Turbine Building Elevation 577 TB2-586 Unit 2 Turbine Building Elevation 586 TB2-604 Unit 2 Turbine Building Elevation 604 TB-607 RX2-519 Unit 2 Turbine Building Elevation 617 Torus Area and HPCI Room Elevation 519 RX2-565 Reactor Building Unit 2 Elevation 565 RX2-593 Reactor Building Unit 2 Elevation 593 RX2-621 Reactor Building Unit 2 Elevation 621 RX2-639 Reactor Building Unit 2 Elevation 634 RX2-664.
RX-DW2-550 RX-DW2-563 Reactor Building Unit 2 Elevation 664 Unit 2 Drywell Elevation 550 Unit 2 Drywell Elevation 563 RXDW2-584 Unit 2 Drywell Elevation 584 Based on this review, the inspector determined that the above fire preplans adequately addressed the fire hazards in these areas.
(4)
Fire Brigade Drill During this inspection, the inspector witnessed an unannounced fire drill.
The drill scenario was a fire in the diesel generator building and a loss-of-off-site power causing activation of the Units I and 2 Diesel Generators.
It was also reported that the B Diesel had failed to activate properly and that the auxiliary unit operator has been dispatched to the area.
Ten fire brigade members responded to the fire.
The brigade members assembled adjacent to the diesel generator building in full protective firefighting turnout clothing and 'elf
I
contained breathing apparatus.
An initial size up of the fire was made by the Incident Commander.
Three hose lines and two CO systems were used.
The fire was placed under control in 24 mi(utes.
The fire brigade utilized proper manual firefighting methods and reacted to the drill scenario in an effective and efficient manner.
f.
Plant Tour and Inspection of Fire Protection Equipment (1)
The inspector performed an inspection of the fire brigade equipment consisting of fire hoses, tools, self contained
'reathing apparatus and miscellaneous equipment stored at the Units I and 2 turbine building on elevations 557 and 565 elevation of the reactor building.
A total of ten sets of turnout gear, coats, boots, helmets, self contained breathing appartus, one hundred feet of 2-1/2 inch and l-l/2 inch hoses and emergency lights are stored in the 575 elevation of the turbine building.
Four sets of turnout gear, coats, boots, helmets, gloves, emergency lights and one hundred feet of 2-1/2 inch and 1-1/2 inch hoses are stored in the 565 elevation of the reactor building.
(2)
The following sectional control valves in the outside fire protection supply system were inspected and verified to be properly aligned and locked in position.
3-26-589 1-26-583 0-26-996 0<<26-512 0-26-513 0-26-511 Hydrant Isolation to Reactor Building Sprinkler System Isolation to Reactor Building Containment Hydrant Isolation Isolation To Service Building Isolation to Office Service Building Hydrant Isolation The following fire Hydrants and Fire Hydrant equipment houses were inspected:
Fire Hydrant Hose House Fire Hydrant Hose House Fire Hydrant Hose House Fire Hydrant Hose House Fire Hydrant Hose House Fire Hydrant Hose House Fire Hydrant Hose House Fire Hydrant Hose House FE H-I FE H-2 FE H-3 FE-M-4 FE-H-5 FE-H-6 FE-H-7 FE-K-8
(3)
The equipment houses contained the minimum equipment specified by NFPA-24, Private Fire Service Mains and Their Appurtenances and FSAR Commitments.
The equipment appeared to be adequately maintained.
2, Elevation 519 2, Elevation 549 2, Elevation 565 2, Elevation 593 2, Elevation 593 2, Elevation 621 2, Elevation 632 16, Elevation 586 16, Elevation 593 16, Elevation 606 16, Elevation 617 Area 20 Unit 2 Reactor Building, Fire Area Unit 2 Reactor Building, Fire Area Unit 2 Reactor Building, Fire Area Unit 2 Reactor Building, Fire Area Unit 2 Reactor Building, Fire Area Unit 2 Reactor Building, Fire Area Unit 2 Reactor Building, Fire Area Unit 2 Control Building, Fire Area Unit 2 Control Building, Fire Area Unit 2 Control Building, Fire Area Unit 2 Control Building, Fire Area Units 1 and 2 Diesel Building, Fire Intake Pump Station, Fire Area 25 Unit 2 Turbine Building, Fire Area 25 A plant tour was made by the inspector.
During the plant tour, the following safe shutdown related areas and their related fire protection features were inspected.
The fire/smoke detection systems manual firefighting equipment, portable extinguishers, hose stations, etc.
and the fire area boundary walls, floors, ceilings associated with the above plant areas were inspected and verified to be in service or functional.
3.
Action on Previous Inspection Findings (92701, 92702)
(Closed)
Unresolved Item 50-259/89-13-05, 50-260/89-13-05 and 50-296/
89-13-05, Potential Failure to Meet Section III.G.3 of
CFR Appendix R.
The inspector reviewed the licensee response to this item and verified that proper corrective action was taken on this item.
(Closed)
Inspector Followup Item 50-259/89-13-02, 50-260/89-13-02, and 50-296/89-13-02, Correction of drawing error for conduit 21E176 in fire areas 18.
Review of this item indicated that a note on the drawing had been missed and that cable 2ES178 was properly shown on drawing 45N8062R40 and drawing 45806-12R18.
(Closed)
Inspector Followup Item 50-259/89-13-09, 50-260/89-13-09, and 50-296/89-13-09, Proper Tagging of Valves Needed for Manual Action.
A field walkdown and review of appropriate labeling documentation for these valves was conducted and verified that all are now properly tagge (Open)
Unresolved Item 50-259/89-28-01, 50-261/89-28-01, and 50-296/89-28-01, Wall Separating the Battery, Battery Board and DC Equipment rooms for Each Unit (Fire Areas 17, 18, and 19)
from the Control Building (Fire Area 16)
Do Not Appear to Meet the Required Fire Rating.
The licensee is adding additional layers of gypsum wall board on the corridor side of the wall panel.
Completion date is March 26, 1990.
4.
Exit Interview The inspection scope and results were summarized on March 2, 1990, with those person indicated in paragraph 1.
The inspector described the areas inspected and discussed the inspection results.
The licensee did not identify as proprietary any of the material provided or reviewed by the inspector during this inspection.