ML20204F366

Forwards Comments on SER Section 9.5.1 Re Fire Protection Program,Issued by NRC on 830222.W/four Oversize Drawings. List of Room Descriptions Also Encl.Aperture Cards Are Available in PDR

ML20204F366
Person / Time
Site:	Catawba
Issue date:	04/14/1983
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20204F371	List: ML20204F366 ML20263T225 ML20263T228 ML20263T231 ML20263T241
References
NUDOCS 8305020020
Download: ML20204F366 (14)

Text

r DuxE POWER GOMPANY P.O. HOx 33180 CHAMLOTM N.o. 28242 HALU. TUCKER rELEPHONE vna essassant (704) 373-4531

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April 14, 1983 i

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission l

Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Mr. Denton:

On February 22, 1983 the NRC issued the Safety Evaluation Report (SER) for Catawba Nuclear Station. Section 9.5.1 discussed the Fire Protection Program.

Attached are comments and additional infor

nation related to this protion of the SER.

$ Very truly yours, hS V lg Hal B. Tucker ROS/php Attachment cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq. $O Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412

,M Palmetto Alliance )

2135 Devine Street Columbia, South Carolina 29205 N. p i

esoso20020 830414

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PDR ADOCK 05000413 E PDR

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Mr. Harold R. Denton, Director April 14,1983 Page 2 cc: Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Mr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition 943 Henley Place Charlotte, North Carolina 28207 i

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3 Duke Power Company

Catawba Nuclear Station Comments on SER Section 9.5.1 Fire Protection r 9,.5.1.5 Control of Combustibles Bulk gas (hydrogen) storage is located in the plant yard. Cylinders are ,

arranged with the long axis parallel to building walls. Piping inside the Auxiliary Building is Duke Class F which is designed to maintain pressure i boundaries during the Design Basis Seismic Event. In each Reactor Building there are two 150 lb. hydrogen cylinders and associated piping which provides a gas " blanket" for Reactor Coolant Pump drain tanks. Piping is Class F as j described above. Cylinders are seismically restrained. Drawings showing

hydrogen and oxygen pipe routing in the Auxiliary and Reactor Buildings are i sttached (Attachment 1).

9.5.1.6 Safe Shutdown for Fires (Appendix R)

A safe shutdown analysis will be provided by July 1983 and will include drawings j marked to show cable routing inside containment, Standby Shutdown System cable routing in the Auxiliary Building and a discussion of associated circuits.

9.5.1.7 Fire Detection Ultraviolet and photoelectric detectors are used in addition to fixed tempera-ture, rate-of-rise and ionization detectors. A corrected list of rooms where fire detection is not provided is attached (Attachment 2). A sketch detailing i normal and backup power supplies for the fire detection system (EFA) is also  ;

included (Attachment 3).

9.5.1.7 Fire Protection Water Supp);E The full water demand for the largest sprinkler system and hose demand (3645 j- GPM as presently designed) can be met with a single fire pump (i.e., with two pumps out of service). Copies of acceptance test performance curves for "A" and "B" fire pumps are included (Attachment 4) . Pump "C" data vill be provided when available.

9.5.1.7 Sprinkler and Standpipe Systems Reactor Coolant Pump and pipe corridor sprinkler systems are manually actuated.

Sprinklers will be provided in the annulus between redundant cable trains if separation is determined to be less than Appendix E requirements.

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9.5.1.8 Reactor Building Electrical penetrations and mechanical pipe penetrations are sealed to provide three hour fire rated barriers. U.L. listed fire dampers are not provided in HVAC ducts which penetrate the Reactor Building wall.

The Containment Purge System (described in FSAR Section 9.4.5) has four pene-trations per unit, located in the vicinity of column HH-52 (Unit 2 at HH-62) on Elevation 594+0 (penetrations are located at elevations 600'+0" - 606'+0").

Two penetrations are 28 inches by 68 inches. Ducts are \ inch steel plate designed to allow thermal and seismic movement. These penetrations are flashed with 3/8 inch stainless steel angles similar to fire damper sleeve arrangement.

A "zero leakage" damper is provided in each duct constructed of inch carbon steel plate housings and inch carbon steel blades as compared with 18 gauge galvanized steel housing and 22 gauge blades of typical fire dampers. The other two penetrations of the containment purge system consist of 10 inch diameter, schedule 40 stainless steel pipe also designed for thermal and seismic movement.

A motor operated valve serves as a damper in each of these penetrations. All "zero leakage" dampers and motor operated valves are normally closed and fail closed.

The Annulus Ventilation System (described in FSAR Section 9.4.9) has four penetrations per unit in the Reactor Building walls in the general vicinity of the Containment Purge System penetrations. Penetrations are 30 inches by 28 inches constructed of k inch stainless steel plate designed to allow thermal and seismic movement. The Annulus Ventilation System is an engineered safety feature system. This system functions to effect a negative pressure with respect to the containment and the atmosphere within 60 seconds following a LOCA. If fire dampers were to be included in the design of this system, the potential for inadvertent closure of a damper would decrease the reliability of this systen. In addition, the duct is sealed to maintain integrity of the secondary containment so that dampers could not be reopened in the event of inadvertent closure.

The area around these eight penetrations is generally void of combustibics with fire detectors on each side of the wall. There are no power or control cables important to safe shutdown in the vicinity of these penetrations. Therefore, it is concluded that not providing fire dampers in the Containment Purge and Annulus Ventilation Systems is an acceptable deviation from the recommendations of the Standard Review Plan (NUREG-0800), Section 9.5.1 and is consistent with the NRC's previous approval of similarly designed systems at other facilities.

9.5.1.8 Control Room Control room doors are constructed in accordance with U.L. methods for fire resistance but are not " approved" because of pressure resistance and other l modifications.

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9.5.1.8 Safety Related Batteries As stated in the Catawba Fire Hazard Analysis, page C-29,.the Standby Shutdown System is available following loss of all functions.in fire areas 9 and 10.

This will be confirmed by the electrical cable separation submittal. When i this is confirmed by the Staff, requirement for sprinklers in these fire areas

-will be relieved, i-d 6

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Attachment 1 Drawing Nos.

CFP-lG CFP-2G CFP-3G CFP-4G l

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Attachment 2 Room Number Description ELEVATION 522 113 Pipe Chase ELEVATION 543 200A Stairwell North of East Elevator 2008 Area in Front of East Elevator 200C Groundwater Drainage Sump & Pumps 2000 Stairwell Adjacent to Room 248 201 Area South of Valve Gallery 202 202 Valve Gallery 203 Waste Gas Decay Tanks 204 Hydrogen Recombiner Control Panel Area (Corridor) 204A Exhaust Fan Concrete Pad 204B Waste Gas Analysis Rack "A" 205 Waste Gas Hydrogen Recombiner "A" 205A Gas Analysis Rack 206A Waste Gas Hydrogen Recombiner "B" 206B Waste Gas Compressor Package "B" 207 Waste Gas Compressor Package "A" 209A Stairwell 210 Corridor Adjacent to Recycle Evap.

Feed Pump 210A Recycle Evap. Feed Pump "A" & "B" 210B Valve Galler) 211 Recycle Evap. Package 212A Stairwell 212B Exhaust Fan Concrete Pad 213 Gas Decay Tank Drain Pump 214 Chemical Drain Tank, Floor Drain Sump, Waste Evap. Feed Sump 215 Access Corridor 215A Waste Drain Tank Pumps 215B Waste Evap. Feed Tank Pumps 215C Waste Drain Tank 215D Waste Evap. Feed Tank 216 Waste Evaporator Package b 220 Mixing & Settling Tank Pumps 221 Mixing & Settling Tank 222 Spent Resin Valve Body Room 222A Spent Resin Storage Tank B 2228 Spent Resin Storage Tank A 223 Spent Resin Sluicing Pump & Valve Body Area

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I 1 Room Number Description 224 Laundry & Hot Shower Tank Pump 225 Laundry & Hot Shower . Tank /Fooor i Drain Tank

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226 Floor Drain Tank Pump 250A- Stairwell 260A Sta i rwel l I ELEVATION 560 l

-300A Stairs 3008 Elevator Lobby 300C Duct Shaft 300D Duct Shaft 301 Boric Acid Transfer Pumps - Unit'2 302 Boric Acid Transfer Pumps - Unit 1 303A' Stairs 303B Duct Shaft 305 Boric Acid Tank "A" 307 Boric Acid Tank "B" 309 Volume control Tank - Unit 2 310A Stairs l 310B Duct Shaft l

-311 Pipe Trench & Hall l 312 Pipe Trench & Hall  ;

314 Recycle Holdup Tank "A" 316 Recycle Holdup Tank "B"

317 Valve Gallery l 319 Volume Control Tank - Unit I l 321 . Seal Water Heat Exchanger - Unit 2 322A Stairs I 323A Pipe Chase 324 Boronometer - Unit 2 331 Seal Water Heat Exchanger - Unit I l 332 Boronometer - Unit 1 333A Pipe Chase 340A Cable Shaft 3408 Cable Shaft 342A Battery Charger 2ECB 350A Cable Shaft 350B Duct Shaft

352A Battery Charger IECB 360A Stairs 370A Stairs E

ELEVATION 577 400A Stairs

'400B Stairs 400C Duct Shaft 400D Duct Shaft i 400E Stairs 400F Duct Shaft I 400G Duct Shaft i

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Room Number Description i 401A Stairs 404 Access to Rooms 410 Recycle Evaporator Feed Demin. (Hatch) 411 Recycle Evaporator Condensate Demin.

(Hatch) 412 Recycle Evaporator Condensate Filter (Double Hatch) 413 Boric Acid Filters (2 Adjacent Hatches) 414 Recycle Evaporator Feed Demin. (Hatches) 415 Recycle Evaporator Condensate Filter hia tch) 416A Recycle Evaporator Feed Filter (Double Hatch) 416B Recycle Evaporator Feed Filter (Double Hatch) 420 Fuel Pool Cooling Post Filters and Pre-Filters and Fuel Pool Skimmer Filter (6 Hatches) 421 Thermal Regenerative Demineralizer 2B (Hatch) 422 Thermal Regenerative Demineralizer 2C (Hatch) 423 Cation Bed Demineralizer 2A (Hatch) 424 Waste Monitor Tank Demineralizer (Hatch) 428 Laundry / Hot Shower Carbon Filter 430 Fuel Pool Skimmer Filert & Waste Evaporator Condensate Filter (3 Hatches) 431 Thermal Regenerative Demineralizer IE (Hatch) 432 Thermal Regenerative Demineralizer IC (Hatch) 433 Cation Bed Demineralizer lA (Hatch) 441 Floor Drain Tank Filter 442 Laundry & Hot Shower Filter (Primary and Secondary) 443 Thermal Regenerative Demi'neralizer 2A (Hatch) 444 Thermal Regenerative Demineralizer 2D 445 Mixed Bed Demineralizer (Hatch) 446 Reactor Coolant Filter 2B (Hatch) 447 Seal Water Return Filter (Hatch) 448 Thermal Regenerative Demineralizer 2E (Hatch) 449 Hixed Bed Demineralizer 2A (Hatch) 450 Fuel Pool Cooling Filters

• Unit I (5 Hatches) 451 Seal Water Return Filter - Unit 1 (2 Hatches) 452 Thermal Regenerative Deminerallxer 10 (Hatch)

Thermal Regenerative Demineralizer IB 453 (Hatch) 454 Mixed Bed Demineralizer IB (Hatch)

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r Room Number -

Description 455 I. 456 Reactor Coolant Filter.IB (2 Hatches)

Reactor Coolant Filter l A (2 Hatches) 457 Waste Evaporator Condensate Demineralizer (I Hatch) 458 Thermal Regenerative Demineralizer IA I

(I Hatch) 459 Mixed Bed Demineralizer IA 460 Reactor Coolant Filter 2A 461 Waste Monitor Tank Filter 462 Seal Water injection Filter 2B 463 Seal Water injection Filter 2A 464 Spent Resin Sluice Filter 470 Seal Water injection Filter lA 471 Seal Water injection Filter IB

.472 Waste Evaporator Feed Filter B 473 Waste Evaporator Feed Filter A 482 Duct Shaft (East of #2 Corridor &

. Cable Room) 483 Corridor 484A Stairs - Entry to Electrical Penetration Room 492 Duct Shaft (Adjacent to #1 Corridor) 493 Corridor Unit 1 494A Stairs & Access to Electrical Penetration Room 500A NE Stairwell 500B NW Stairwell 500C SE. Stairwell 500D SW Stairwell 510 Counting Room 551 Instrument C.**ibraeion l 551A Corridor 1 561 Corridor / Hatch Area 561A Stairwell 561B Stairwell 562 Unit 2 Penetration Area (Steam Doghouse) 571 Corridor 571A Stairwell 572 Unit 1 Steam Penetration (Doghouse) 580 N2 Accum. Tank Blowoff, Unit 2 580A Stairwell 581 Steam Penetration, Unit 2 (Outside Doghouse)

! 590 N2 Accum. Tank Blowoff, Unit 1 590A Stairwell h 591 Steam Penetration, Unit I (Outside l Doghouse)'

600A Duct Room 601 Reactor Personnel Lock Area 614A Duct Room 615 Reactor Personnel Lock Area #2

Room Number Description ELEVATION 611 4

.750 Purge Supply Room - Unit i 751 - Purge Supply Room - Unit 2 ELEVATION 623 + 10 801 Fuel Pool Purge Unit-(Unit I) l 802 Fuel Pool Purge Unit (Unit 2) 4 4

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