IR 05000327/1981014
| ML20004D865 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/24/1981 |
| From: | Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20004D857 | List: |
| References | |
| 50-327-81-14, 50-328-81-14, NUDOCS 8106100242 | |
| Download: ML20004D865 (12) | |
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'o UdlTED STATES
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NUCLEAFI REGULATORY COMMISSION
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I REGION ll
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101 MARIETTA ST., N.W.. SulTE 3100
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ATLANTA, GEORGIA 30303 o
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nU Report Nos. 50-327/81-14 and 50-328/81-14
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Licensee:
Tennessee Valley Authorit'y l
500A Chestnut Street
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Chattarooga, TN 37401 l
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Facility Name:
Sequoyah 1 and 2 i
Docket Nos. 50-327 and 50-328 License Nos. DPR-77 and CPPR-73 Inspection at Seq yah site near hattanooga, TN c#.
,N 24/8/
Inspector:
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W. H. Miller Jr."
Date Signed
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Approved b :
1//!84'
T. E. Conlon, Section Chief Date' Signed
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Engineering Inspection Branch
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Engineering and Technical Inspection Division SUMMARY j
Inspected on March 24-27, 1981 Areas Inspected This special, unannounced inspection involved 32 inspector-hours on site in the areas of fire protection / prevention.
Results
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Of the areas inspected, no violations were identified. One apparent deviation was found; Fire detectors not provided over ERCW pumps paragraph 5.b.(61) and
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E.b.(64).
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310 610 Oh-L i
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w REPORT DETAILS 1.
Persons Contacted Licensee Employ:tes
- J. M. Ballentine,' Plant Superintendent / Plant C. R. Brimer, Outage Director
- C. E. Chmielewski, Nuclear Engineer / Plant
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- J. D. Collins, Supervisor Electrical Design /ENDES i
- E. A. Craigge, Supervisor Plant Safety # Fire Protection Staff
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L. Cowan, Outage Electrical Engineer
- D. L. Cowart, QA Engineer /Po.ier
- A. W.. Crevasse, QA Manager / Power
- H. E. Crister, Mechanical Engineer /ENDES
- C. C. Denney, Electrical Engineer /ENDES
- V. L. Dudley, Fire Protection Engineer / Power M. K. Eisenbise, Outage Engineer
- A. H. Gelston, Compliance / Power
- M. R. Harding, Compliance Supervisor D. O. McCloud, QA Supervisor / Power
- J. McGriff, Assistant Plant Superintendent
- P. A. Thornton, Electrical Engineer / Construction
- V. P. Thomas, Supervisor Coordination / Construction
- R. Thompson, Supervisor Fire Protection Engineering / Power
- K. O. Smith, Electrical Engineer / Construction
.G. Williams, Fire Protection Specialist NRC Resident Inspector
- E. J. Ford
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 27, 1981 with those persons indicated in paragraph I above.
3.
Licensee Action on Previous Inspection Findings a.
(0 pen) Deviation (327/80-10-01):
Substandard fire protection admin-1strative control procedures. This item is being evaluated by NRR and will remain open pending completion of the evaluation.
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b.
(0 pen) Deviation (327/80-10-02):
Substandard supervision of fire protection control valves.
This item is being evaluated by NRR and will remain open pending completion of the evaluation.
c.
(0 pen) Unresolved Item (327/80-10-03): Two inch drain test fitting for sprinkler systems.
This item is under review by the licensee and remains open.
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d.
(Closed) Unresolved Item (327/80-10-05): Equipment-list for exterior fire equipment houses. The licensee revised the list of equipment to be provided within each house and forwarded this data to NRR on June 11, 1980 in a letter from L. M. Milis, TVA to L. S. Rubenstein, NRR. NRR subsequently issued Supplement 2 to the Safety Evaluation Report which apparently approved TVA's revised equipment list.
This item is closed.
e.
(0 pen) Unresolved Item (327/80-10-07):
Supervision of containment isolation fire protection valves. TVA has taken no action on this item and is awaiting guidance from NRC. This item is being evaluated by NRR and will remain open pending completion of the evaluation.
f.
(Closed) Deviation (327/80-17-01):
Inadequate fire barriers for conduits containing redundant steam generator instrumentation circuits.
The inspector reviewed the licensee response of June 30, 1980, from L. M. Mills, TVA to James P. O'Reilly, NRC Region II. The inspector walked down the conduit installation. All of the conduit appeared to be properly insulated. This item is closed.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 5.b.(14), 5.b.(35), 5.b.(60), and 5.b.(61B) & (648).
5.
Fire Protection / Prevention Program Modifications and Commitments (Unit 2)
a.
Commitments (Unit 2)
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The inspector evaluated the licensee's action on fire protection commitments made to the NRC. The NRC Fire Protection Safety Evaluation Report (FPSER), Section 9.5 of the facility Safety Evaluation Report, Supplement 1 of February 1980 and Supplement 2 of August 1980, and the licensee's Sequoyah Nuclear Plant Fire Protection Program Reevaluation (FPPR) of January 20, 1977, Revision 4 were used in this evaluation.
These documents describe the fire protection commitments, requirements,
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and schedule dates of implementation. The commitments and findings are as follows:
No.
Location / Item Section Status Primary Containment - Reactor Bldg.
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p (1)
Reactor Coolant Pomp
(IA)
- Fire Detection (Thermal & Flame)
F.1.H Closed
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-(18)
- 011 Collection System F.1.B Open (IC)
- Noncombustible Housing F.1.8 Open (10)
- Water Spray System (Closed Heads)
F.1.F
- Closed (2)
Standpipe Fire Hose System (Dry)
F.1.D Closed (3)
Fire Detection - Cooling Units F.1.H Closed Annulus Area - Reactor Bldg.
(4)
Sprinkler System - Divisional Cable F.1.G
- Closed Interaction (5)
Fire Detection (Smoke)
F.1.H Closed
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(6)
Standpipe Fire Hose System F.1.0 Closed (7)
Fire Extinguishers F.1.C Closed (8)
Exposed Cables Coated (Flame-mastic)
F.1.A Closed Control Building - Control Room Complex (EL 732')
(9)
Fire Detection F.2.B
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Peripheral Areas (Ionization & Thermal)
Closed Control Room (Ionization)
Closed
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Control Consoles (Ionization)
Closed Fire Barriers F.2.A Fire Dsors (3 Hr) - Between Control Room & Turbine & Auxiliary Buildings Closed Fire doors (11s Hr) - Between Peripheral Rooms Closed (11)
Standpipe Fire Hose System (Stairwells)
F.2.0 Closed (12)
Fire Extinguishers (Halon 1211)
- Q20.C Closed (13)
Sprinkler System
- Closed
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Mechanical Room F.2.E Operators Living Area F.2.E Corridor F.2.E Record Storage F.2.F PS0 Engineer Shop F.2.F HEPA/ Charcoal Filters F.2.G
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(14)
Ceiling for Control Room /N:... combustible
- Q20.A Open Curbs F.2.I Closed Control Room Doors AHU Compressor / Mechanical Room Control Building - Spreading Room (EL 706')
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(16)
Fire Detection (Ionization)
F.3.E Closed
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(17)
Sprinkler System (Two Levels)
F.3.E
- Closed (18)
CO2 System (Manual)
F.3.E Closed (19)
Standpipe Fire Hose System F.3.D Closed (20)
Fire Extinguishers F.3.C Closed (21)
Fire proof Structural Steel (Pyro-crete)
F.3.B Closed (22)
Exposed Cable Coated (Flame-mastic)
F.3.A C1csed (23)
Fire Barriers F.3.8 Fire Doors (3 Hr)
Walls, Floor and Ceiling Control Building - Auxiliary Instrument Room (EL 685')
(24)
Fire Detection (Ionization & Thermal)
F.5 Closed (25)
CO2 System (Automatic)
F.5 Closed (26)
Fire Barrier F.5 Closed
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Fire doors (1 Hr)
Fire Dampers (1h Hr) - Wall
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Fire Dampers (3 Hr) - Floor Turbine Building (27)
Fire Barrier - Between Turbine & Control F.8 Closed Butiding Fire Doors (3 Hr)
Water Curtain for Wall Penetrations Auxiliary Building - (EL 653')
(28)
Fire Detection (Ionization)
"Q.1 Closed Open Area
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RHR Pump Rooms Containment Spray Pump Rooms (29)
Fire Bar' ter (1h Hr) - Pump Compartments
- Q.1 Closed
- Fire De ars (1h Hr)
(30)
Standpipe Fire Hose System
- Q.1 Closed
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5 Auxiliary Butiding - (EL 669')
(31)
Fire Detection (Ionizatinn)
- Q.1 Closed Open Area Pump Compartments (Ioni on & Thermal)
(32)
Fire Barriers (1h Hr)'. ump Compartments
- Q.1 Clcsed (33)
Standpipe Fire Hose System
- Q.1 Closed (34)
Sprinkler System
- Q.1
- Closed Open Area Pump Compartments (35)
- Redundant Cable Separation (20') Between
- Q.1 Open Reciprocal Charging Pump, Power Supply, Control Circuit, Room Cooler Circuits and Redundant Train A Circuits Auxiliary Building - (EL 690')
(36)
Fire Detection (Ionization) - Area
- Q.1 Closed (37)
Sprinkler System
- Closed Open Area Beneath Pipe Break Barriers for
- Q13.B Feedwater Pump Beneath Mezzanine For Component
- Q13.C Cooling Water Pumps (38)
Fire Barrier (1 Hr) for Cable Above
- Q13.E Not Component Cooling Water Pumps Required (39)
Fire Barriers (h Hr) Between Component
- Q13.0 Closed Cooling Water Pumps (40)
Standpipe Fire Hose System Closed (41)
Fire Rated Enclosure (1h Hr) - ERCW
- Q11.B Incomplete Nmp Junction Box (42)
Fire Barrier (h Hr) Between Redundant
- Q11.B Incomplete Power Cables (43)
Reroute Train B ERCW Pump Cable and
- Q11.B Incomplete Transformer Caoles - 20' Clearance Auxiliary Bui1 ding - Fuel Storage Area (EL 706')
(44)
Fire Detection (Ionization)
F.12 Closed (45)
Standpipe Fire Hose F.12 Closed (46)
Fire Extinguishers F.12 Closed
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Auxiliary Building - Waste Package Area (EL 706')
(47)
Sprinkler System F.14 Closed (48)
Standpipe Fire Hose F.14 Closed (49)
Fire Detection (Ionization)
F.14 Closed L
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Auxiliary Building - Auxiliary Control Complex (EL 734')
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(50)
. Sprinkler System F.6
- Closed (51)
Fire Detection (Ionization)
F.6 (52)
Fire Barr'er - Between Cells &
F.6 Closed Adjacent Areas Fire Doors (1h Hr)
Fire Dampers (1h Hr)
(53)
Standpipe Fire Hose System (Adjacent Areas)
F.6 Closed (54)
C Jrbs at Doorways F.6 Closed (55)
Eyosed Cables Coated (Flame-mastic)
F.6 Closed
Auxiliary Duilding - 125V Vital Battery Rooms I-IV (EL 749')
(56)
Sprinkler Systems,(Mant 1)
- Q.1 Closed (57)
. Fire Detection (Ionization)
- Q.1 Closed
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(58)
Fire Barrier (1 Hr) - Between Compartments
- Q.1 Closed Fire Doors
Fire Dampers (59)
Exhaust Systems
- Q.19 Closed Redundant Fans Loss of Flow Alarms Auxiliary 3uilding - General Areas (60)
Fire Barrier for Pressurizer and Steam
- Q.1 Open Generator Instrumentation ERCW Pumping Station (61).
Fire Detection (61A)
Electrical Equipment Rooms (Ionization)
- Q.1 Closed (61B)
ERCW Pumps (Thermal)
- Q.14 Open
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(62)
. Standpipe Fire Hose System
- Q.1 Closed (63)
Fire Barriers /Between Compartments
- Q.14 Closed Fire Doors (3 Hrs)
Intake Pumping Station (64)
Fire Detection
- Q.1 (64A)
Elevation 690' (Ionization)
- Q.1 Closed (648)
ERCW Pump (Thermal)
- Q.14 Open (65)
Standpipe Fire Hose System
- Q.1 Closed u
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Diesel Generator Building (66)
Fire Barriers (3 Hr)
F.9.A Closed Between Generators Between Electrical Board Rooms / Fire Door Automatic Closing (67)
Curbs - Generator Doors F.9.A Closed (68)
Fire Detection F.9.B Closed Generator Rooms (Thermal)
011 Storage & Transfer Rooms (Therma'.)
Pipe Gallery & Corridor (Thermal)
Air Intake & Exhaust Rooms (Thermal)
Engine Room / Electrical Cabinets (Ionization)
Electrical Board Rooms & Cabinets (Ionization)
(69)
Standpipa Fire Hose System F.9.D Closed (70)
Sprinkler System (Corridor)
F.9.E
- Closed (71)
CO2 System (Automatic)
F.9.E Closed Generator Rooms Board Rooms Lubrication Oil Sto, rage Room NOTES:
"Open" - Item is not complete.
Refer to Paragraph 5.b for details.
"Ciosed" - Item appears to meet the commitments to the NRC based on review of documentation data and field inspection by the inspector.
Installation of portions of the fire protection systems, such as the annulus sprinkler systems, have not been completed or fully tested. However, the system installations are nearing completion and the licensce's prncedures appear adequate to assure that the systems will be functional prior to fuel Inad.
"*Q" - Response to NRC questi,n on FPPR.
"* Closed" - Automatic sprinkler systems at Sequoyah do not fully meet all of the provisions of NFPA-13. The principal discrepan-cies include the unsupervised electrical actuation circuits and piping for the pre-action systems. These items are discussed in IE Reports 50-327/79-34, 50-328/79-19, 50-327/80-10 and 50-32.8/
80-06.
NRR's memorandum of February 13, 1980 from V. Benaroya, NRR/ASB to H. Thornburg, IE/HQ stated that the sprinkler systems
'at Sequoyah were acceptable to NRR. Therefore, no further action is to be taken on this item.
b.
Findings Additional information on the "Open" items in paragraph 5.a is listed below.
The below listed numbers correspond to the items in paragraph 5.a.
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(IA) & (IB) - The oil collection system for the reactor coolant pumps does not meet the description provided within the FPPR and does not appear to meet the provisions of 10 CFR 50, Appendix R, Section III.O.
However, NRR's memorardum of February 13, 1980 from V. Benaroya, NRR/ASB to H. Thornburg, IE/HQ advised that the fire protection features provided for these pumps were adequate and met the NRC guidelines.
Refer to IE Reports 50-327/79-34, 50-328/79-19, 50-327/
80-10 and 50-328/80-06 for additional informatien an this item.
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(14) - The suspended ceiling for the control room is a combustible plastic material and does not conform to the noncombustible provisions of 10 CFR 50 Appendix A, Criterion 3.
This item is cur:ently under review by TVA and NRC/NRR and it appears that all or a portion of this ceiling may be replaced. This item is identified as Unresolved Item (37.7/81-14-01 and 328/81-14-01), combustible ceiling in control room, and will be reviewed following the evaluation.
(35) - Table 1.2 in TVA's response to NRC's Question 1 in the FPPR states that the cables for the reciprocal charging pump power supply and control circuits and the power cable to the reciprocal charging pump room cooler unit will be relocated, installed in conduit from.the pump room to the associated 480V switchgear, and located such that these circuits will be separated by at least 20 feet from the charging pump train A circuits. This work was accomplished under Engineering Change Notice No. 2463 and Release No. E874 and was completed on December 19, 1979. The inspector reviewed the construction instalia-tion documents for this modification and visually inspectad the cable /
conduit installation from the pump room on the 669' elevation to the switchgear rooms at the 734' elevation. It appears that at least 20'
minimum separation was provided between the reciprocal charging pump components (pump C) and the redundan:; circuits from charging pump A in all areas except at the 669' elevation. At column line A10-t on the 669' elevation, the reciprocal charging pump component circuits were located approximately 13 feet from cable tray MT-A which contains the control circuits for charging pump A and were located approximately 15 feet from cable tray AB-A which contained the power circuits for charging pump A.
This item is identified as Unresolved Item (328/81-14-02), electrical cable to reciprocal charging pump and room cooler are inadequately separated from charging pump A circuits. This item is required to be completed prior to fuel load for Unit 2.
(38) - The licensee's evaluation determined that the pcwer and control circuits located on the mezzanine level above the component cooling water pumps are not reouired for safe shutdown and t wrefore do not have tr. be provided with the 1-Is hour fire rated barrier.
(41)-(43) - T..ese items are not required to be completed until June 1981.
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l (60) - Table 1.3 in TVA's response to NRC's Question 1 on the FPPR identifies the conduits in Unit 2 to be wrapped with a 1-inch "Kaowool" insulation to provide a h hour fire barrier.
These conduits contain instrumentation circuits for the pressurizer and steam generator and extend in the auxiliary building from the containment penetration at the 734' elevation of the auxiliary butiding to the control building penetrations of the Q-line wall at the 714' elevation of the auxiliary
, building.
These conduits have been insulated; however, a large percentage of the conduit insulation on the 714' elevation has been removed and damaged due tc the construction activities. The 1.censee is aware that these conduits are required to be insulated prior to the fuel load of Unit 2.
This item is identified as Unresolved Item
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(328/81-14-04), damaged fire barrier for pressurizer and steam
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generator instrumentation circuits, and will be reviewed during a
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subsequent NRC inspection.
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(618)&(648) - Table 1.1 in TVA's response to Question 1 of the FPPR states that rate compensated thermal detectors with heat collectors will be provided above each ERCW pump in the ERCW pump house and the
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intake pumping station. TVA's response to NRC's Questions 14.B of the FPPR also states that thermal spot datectors and heat collectors will be provided immediately above each ERCW pump in the CCW intake pumping station and the ERCW pumping station to provide early warning fire detection capability. However, fire detectors are not provided over
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the ERCW pv>y. This is a failure to meei, a commitment to the NRC and for Unit 1 is identified as Deviation Item (327/81-14-03), fire detec-tion is not provided over ERCW pumps and is identified as Unresolved Item (328/31-14-03) for Unit 2.
This item is required to be completed prior to the fuel load for Unit 2.
i c.
Unit 1 Fire Damper Modifications Paragraphs 2.c.(16) of the Unit 1 operating license required the licensee to install five (3) fire dampers prior to November 1,1981.
The licensee stated that these dampers were inst.alled under Work Plan No. 8832 and Engineering Change Notice No. 5005 and are as follows:
Mark Tag
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Fire Rating No.
No.
Size (Hr)
Location 551 1-31C-1224 11 " X 11 "
1h Aux. Bldg. 669' EL 552 0-31A-258 30h" X 32h" 1h Unit 1 Instrument Room 553 0-31A-259 36h" X 26 "
Unit 1 Instrument Room 554 0-31A-260 69" X 27"
Unit 1 Instrument Room 555 0-31A-261 33" X 61"
Unit 1 Instrument Room W
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Installation of these dampers was completed on October 31, 1980. The inspector reviewed the work plan, QC inspection and installation documents and visually inspected three (3) of the damper installations.
No discrepancies were noted.
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. Unit 1 Sprinkler System Modifications Paragraph '2.c.(16) of the Unit 1 operating license required the licensee to replace and relocate sprinkler heads in the auxiliary building. The FPSER, Supplement 2, page 9-2 states that 58 sprinkler
heads in the auxiliary building needed to be installed or relocated but i
did not identify the specific location of these heads. The licensee stated that these modifications were accomplished under Work Pian 8817
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and Engineering Change Notice No. 5007. which required a total of 58 sprinkler heads to be added on the 669', 690', and 714' elevations of the auxiliary building.
The last modification was completed on October 30, 1980. The inspector reviewed the work plan and construc-tion documents for the modifications and visually inspected the modifications on the 714' elevation. No discrepancies were noted.
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Operating Plant Fire Protection Procedures Refer to IE Report 50-327/80-10 and 50-328/80-06 for details on the inspection and review of the licensee's administrative fire protection procedures.
f.
Fire Brigade Equipment and Fire Fighting Equipment The inspector inspected the fire brigade equipment storage locker and found an adequate supply of fire fighting turnout gear and other
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miscellaneous items to satisfactorily equip the plant fire brigade.
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Two 5200 cfm portable electric smoke ejectors were stored in the equipment locker and four additional units were stored on the 653'
elevation on the auxiliary building.
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Exterior Fire Equipment Houses
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The inspector inspected fire equipment house Nos. FHS, FH6, FH9 and
GH11 and found the equipment to be in accordance with TVA's response of
. lune 11, 1980 to NRC's Question 26. The licensee stated that all of
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equipment houses required for Unit 1 operation were equipped like those inspected and that all remaining equipment houses would be installed and equipped prict to intial fuel load for Unit 2.
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Emergency Breathing Apparatus l
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A total of 10 self contained breaching apcaratus and 10 spare cylinders l
are designated for fire brigade use. A total of 92 units and 154 spare
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cylinders are available at the site. The cylinders are recharged l
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onsite with an air compressor and cascade system which has a capacity to recharge approximately 8 cylinders per hour.
The number o' units and refill capacity available meets the intent of BTP9.5.1.
1.
Fire Brigade Drills The inspector reviewed the fire drill log data for January 1980 through February 1981 and noted that each operating crew ha'd^ participated in at least one drill per quarter. The number and frequency of drills was in accordance with the licensee's procedures.
Training records for three fire brigade leacers and five-fire brigade members were reviewed by the inspector and found to be satisfactory.
The traini..g records for the quarterly classroom brigade training is presently being filed as a general safety training.
However, the licensee is to revise the plant procedures to classify the quarterly classroom training as staff training and to classify the training records as permanent plant records. Records for previous fire brigade classroom training are currently stored with other QA/QC type documents and would only have been retained for two years.
Initiation of the licensee's proposed action will correct this potenLial discrepancy.
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Offsite Fire Protection Ort 11s and Training The 1980 annual full scale site fire drill was conducted on December 17. The fire departments frcm the city of Soddy-Daisy with a chief and 12 fire fighters and the city of Chattanooga with a Chief Officer and 5 fire fighers participated.
The insoector reviewed the drill critique records and had no further questions.
The licensee conducts an annual training in security, radiation protection, plant fire hazards and fire brigede and fire department interface with plant tour for the Soddy-Daisy and Chattanooga Fire Departments. For 1980, this training was conducted on August 7, 1980, for 22 fire fighters from the Soddy-Daisy Fire Department and on November 6, for 12 fire fighters from the Chattanooga Fire Department.
Except as noted above, no additional violations or deviations were identi-fied, within the areas examined.
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