ML20153G412
| ML20153G412 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 07/14/1993 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20153G406 | List: |
| References | |
| NUDOCS 9809300068 | |
| Download: ML20153G412 (40) | |
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t AGENDA- [ Introduction Rick Hasselberg / i Andrea Sterdis Main Control Room / Technical Support Center HVAC ' i
System Description
Mike O'Connor-Modes of Operation Mike O'Connor Main Control Room Doses Jim Grover i i Main Control Room Emergency Habitability System i
System Description
Dan McDermott Modes of Operation Dan McDermott Testing i Dan McDermott Main Control Room Doses Jim Grover Requests for AdditionalInformation
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I t MCR/TSC HVAC (VBS) - SYSTEM DESCRIPTION Design bases Functions . Design features GDC 19 compliance ! \ i i t MODES OF OPERATION Normal operation
- High radiation ;
- Smoke purge Smoke / toxic chemicals i
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MCR/TSC HVAC (VBS) . . SYSTEM DESCRIPTION ,
- Design bases
- Nonsafety-related Maintain MCR at:
70 3 F ambient temperature Capable of maintaining 73 to 78 F 25% and 60% relative humidity range' ~ Slightly positive pressure Maintain TSC at-73 F to 78 F ambient temperature 25% and 60% relative humidity range Slightly positive pressure f
MCR/TSC HVAC J.VBS) . Design bases (cont'd) l Defense-in-Depth Maintain passive cooling heat sinks initial temperature s 80 F i , MCR/TSC El1/8 in. Wg pressure when high radiation present i Auto transfer to standby diesel on LOOP !
- Safety-related Provide MCR envelope isolation dampers and start emergency habitability system (VES) on high-high radiation i
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l MCR/TSC HVAC J.VBS.D Functions Nonsafety-related Control MCR/TSC ambient environment during normal op,eration
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Defense-in-Depth ,, Nonsafety-related Defense-in-Depth for control room habitability Maintain passive cooling heat sink ambient temperature Filter makeup air to MCR/TSC during high radiation ! condition MCR/TSC recirc mode when smoke detected from external fire (toxic chemicals are site specific)
i l MCR/TSC HVAC (VBS.h 4 j i Functions (cont'd) '
- Defense-in-Depth (cont'd) . . . i Provide smoke removal capability for internal fire 4
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e Initiate MCR Emergency Habitability System on high- i high radiation, if required i 4 i . i 4
l MCR/TSC HVAC (VBS? Design features Nonsafety-related Two 100% capacity trains with common duct work
, Kitchen and toilet exhaust fan-
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Defense-in-Dep'th 1 Tornado protection damper in the outside air intake duct Redundant smoke detectors in outside air intake duct . Operable during or after DBE if ac power is available Supplemental air filtration on high radiation, containment isolation or manual actuation
i MCR/TSC HVAC J.VBSh . i Design features (cont'd) 4 : Defense-in-Depth (cont'd? Support provided by Defense-in-Depth systems such as Chilled Water and Standby Diesels Safety-related
. Redundant safety-related radiation monitors in MCR supply air duct Redundant safety-related/ seismic I isolation dampers
. for MCR envelope -
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m m e r m e r e r - 6 6 1 8 9 0 8 . ) ) m m no o i o o C nR R ol nl A i so r r i o V etn ntr H I mo i on so e mC rC e v i e me md mids i _ t - os i c r n i n
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- r.. i AssumDtions Used to Determine CR Doses .
- LOCA Source Term as described in SSAR (EPRI Defined Source Term)
! I e Control Room Occupancy of: 100% for 0 to 24 hours 60% for 24 to 96 hours 40% for 96 to 720 hours e Breathing Rate: 3.47 x 10 4 3 m /sec I
e Atmospheric dispersion; factors (X/Q values) are as stated in the SSAR: 0 - 2 hr 2 2 x 10-3 sec/m3 - 1.5 x 10-3 2-8 ' 8 - 24 1.3 x 10-8 24 - 96 8.4 x 10 4 96 - 720 4.8 x 10 4 e Dose Conversion Factors are from ICRP Publication 30 and EPA Federal Guidance Report No.11
- Control Room volume: 42,260 cubic feet h ap01
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Assumntions Used to Determine CR Dosen (cont.) i t e Technical Support Center volume: 69,850 cubic feet ! e Unfiltered air inleakage of 40 cfm e Pressurization air flow of 960 cfm e Filtration of pressurization air flow: Particulate 99% Organic i 90 % Elemental 90 % ; e Recirculation air flow of 14,000 cfm with 3000 cfm passing through the , supplemental air filtration unit (all of the flow passes through the main air handling unit) ' e Filtration of recirculation air flow: Main Air Supplemental Air Handling Unit Filtration Unit Particulate 80 % 99 % i Organic N/A , 90 % Elemental N/A 90 % k apet i
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MCR EMERGENCY HABITABILITY SYSTEM (VES) -
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SAFETY-RELATED FUNCTIONS /, DESIGN BASIS , Provide MCR with an adequate supply of breathable air Maintain breathable air standards with CO2 levels below
- one percent by volume (OSHA,29 CFR 1910) 1 Pressurize MCR to, limit ingress of radioactive contaminants -
Maintain MCR pressure 1/8 inch water gage relative to adjoinirig areas
- Limit MCR temperature rise l Limit temperature excursion following DBE, with a loss of I all ac power, to 15 F for 72 hours
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MCR EMERGENCY HABITABILITY SYSTEM (VES) : l DESIGN CRITERIA GDC 19: Provide a control room to operate the reactor plant safely : under normal' conditions and maintain it safely under accident conditions. Adequate radiation protection to limit operator doses to less than 5 rem whole body or equivalent. j Safety-related design i ASME Section lil, Safety Class 3
. Seismic Category 1 4 Class 1E ! '
Meets single failure criterion j l
VES SCHEMATIC - ACTUATION - OPERATION <
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MAIN CONTROL ROOM HABITABILITY SYSTEM ( ) hs -- i i (\ A J . ( T l: EXXXXD
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REFILLING STORAGE TANKS CONNECTION ROOM ;
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EMERGENCY AIR REFILLING LONG. TERM STORAGE TANKS CONNECTION COOLING CONNECTIONS j i
.u VES SYSTEM PARAMETERS / PERFORMANCE Ji -l i
VENTILATION
. System design basis Air flow rate 20 cfm Max. CO2 concentration 1.0 % !
(OSHA,29 CFR 1910)
. Evaluation basis i
Initial CO2 concentration 0.25 % Personnel 5 Duration 72 hours CO2 production / person 0.0155 cfm i
- Results .
CO 2 concentration <1.00% g Margin ~ 12 persons
W f VES SYSTEM PARAMETERS / PERFORMANCE ' PRESSURIZATION i System design basis Air tank volume 664 ft (2 sets) Air tank pressure 2500 psia Evaluation basis MCR positive pressure 1/8 inch water MCR maximum leakage rate 20 cfm @ 1/8 inch water'
- Results Margin ~ 4 safety factor
' MCR envelope leakage rate calculations: Methodology and assumptions consistent with " Conventional Building for Redctor Containment." +- j. E a,
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VES SYSTEM PARAMETERS / PERFORMANCE - ,
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COOLING System design basis MCR max. temperature rise 15 F i l - Evaluation basis Heat sources (variation with time) Graph Heat sink initial temperature Tech Spec , Heat sink configurations Finned ceiling, flat walls
- - Margin
. Temperature rise Graph I
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; MCR HEAT SOURCES -
HEAT _E AJS VERSUS T :ME (3TU/HU : EQUIPMENT LOADS: 4& LIGHTING LOADS: (M _
/ / OCCUPANT LOADS:
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MCR THERMAL TRANSIENT . LOSS OF AC' TEMPERATURE TRANSIENT , MAIN CONTROL ROOM l 100 98 96 , ( o 94 w 92 i W go I T ' I 3 88 f 86 E 84 - - ! gj - l ! E 82 : g r W 80 F 78 i 76 [ c r 74 I i 72 70 ; O 16 20 30 40 50 60 70 80 ! TIME (HOURS) 2
i MCR EMERGENCY HABITABILITY SYSTEM ' (VES) MODES OF OPERATION Normal i i System in standby , Air supply / heat sinks maintained per Tech Specs
- Abnormal Smoke / Fire Normal HVAC (VBS) placed in recirc. mode Passive system (VES) maintained in standby, available for manual actuation i
Toxic releases Normal HVAC (VBS) placed in recirc. mode Passive system (VES) maintained in standby, available for manual actuation l
MCR EMERGENCY HABITABILITY SYSTEM (VES) . MODES OF OPERATION ; i Abnormal (cont'd) Design basis event ! Normal HVAC (VBS) automatically pinced in supplemental mode of operation i High radiation level at air intake Containment isolation signal i 1 Passive habitability system (VES) Automatic actuation on loss of all ac power or high-high radiation level signals Manual actuation capability I !
i MCR EMERGENCY HABITABILITY SYSTEM (VES) POST-72 HOUR DESIGN' PROVISIONS l Compressed-air storage tank refill connections i Located in truck / rail bay area Permanently installed Safety-related Seismic ' - Cooling capability Sealed penetrations provided through MCR envelope (provides for cooled water supply and return)
- Permanently installed
- Safety-related
- Seismic Portable unit cooler to be provided inside MCR Portable air-cooled chiller to be provided outside MCR envelope >
i MCR EMERGENCY HABITABILITY SYSTEM (VES) i SYSTEM TESTING PROVISIONS .
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ITAAC testing - ' Air flow rate ! Pressurization capability Temperature rise with heat sources System operation (proper valve operation and actuation) Initial test program! Air flow rate ' Pressurization capability Temperature rise with heat sources System operation (proper valve operation and actuation) Technical Specification Surveillance MCR Temperature Air storage tank pressure Valve operation Air flow rate Pressurization capability .
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Assumptions Used to Determine CR Doses e LOCA Source Term as described in'SSAR (EPRI Defined Source Term) i l e Control Room Occupancy of: 100% for O to 24 hours , 60% for 24 to 96' hours-40% for 96 to 720 hours e Breathing Rate: 3.47 x 10 4 m3/sec ! l ! e Atmospheric dispersioni factors (X/Q values) are as stated in the SSAR e Dose Conversion Factors are from ICRP Publication 30 and EPA Federal Guidance Rep' o rt No.11 e Control Room volume: 42,260 cubic feet e Unfiltered air inleakage: 0.3 cfm e Control Room pressurization air flow (from air bottles): 20 cfm e No recirculation air cleanup Atap01
i NRC REQUESTS FOR ADDITIONAL INFORMATION RAI 410.96: Justify the nonsafety-related designation of the VBS filtration function of the CRAVS i RAI 410.97: Demonstrate how the VBS complies with GDC 4
" Environmental and Missile Design Basis" RAI 450.1: Provide methodology for pressurization capability of VES. Provide methodology for assessing CO2 concentration. Provide rationale for habitability.
Provide justification that safety-related and ' defense-in-depth equipment will not be degraded during DBA's. Provide rationale for not providing an ESF filtration system in accordance with RG 1.52. RAI 450.2: Justify the unfiltered inleakage assumption fdr the : MCR envelope and explain MCR isolation actipns. t
1 NRC REQUESTS FOR ADDITIONAL INFORMATION l I i
!. P Al 410.96: Justify interfaces for future applicants to:
ensure VES complies with GDCs 4,5, and 19 verify procedures'are consistent with licensing ; basis documentation i verify technical specifications are consistent with licensing basis documentation
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Westinghouse . Energy Systems sox 355
~ Pittsburgh Pennsylvania 15230 0355 Electric Corporation .
DCP/NRC1409 NSD-NRC-98-5753 Docket No. 52-003 August 13,1998
- Document Control Desk U. S. Nuclear Regulatory Commission :
Washington, DC 20555 l ATTENTION:- T. R. QUAY
SUBJECT:
RESPONSE TO NRC LETTERS CONCERNING REQUEST FOR WITHHOLDING INFORMATION
Reference:
- 1. Letter, Sebrosky to McIntyre, " Request for withholding proprietary information for Westinghouse letters dated December 14,1992, and December 17,1992," dated July 10,1998.
~
- 2. Letter, Huffman to McIntyre, " Request for withholding information from public )
disclosure of Westinghousc AP600 design letters of December 15,1992," dated July 14,1998.
- 3. Letter, Sebrosky to McIntyre, " Request for withholding information from public disclosure for Westinghouse AP600 design letter of February 24,1993, April 19, 1993, and July 14, 1993," dated June 18,1998.
- 4. Letter, McIntyre to Quay, " Status review of AP600 proprietary submittals," dated September 18,1995.
Dear Mr. Quay:
Reference i provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated December 14,1992, that provided the NRC with copies of presentation material from a management meeting held December 14,1992, discussing the AP600 testing program. The NRC has no record of a nonproprietary version of the slides being provided. At the time this presentation was made, the information was proprietary since that description of the AP600 testing program had commercial value to Westinghouse. At this time, almost six years later, this information does not have commercial value and is no longer considered to be proprietary by Westinghouse.
' Reference 1 also provided the NRC assessment of the Westinghouse claim that proprietary information j was provided in a letter dated December 17,1992, that provided the NRC with copies of presentation material from a meeting with the technical staff hcid December 9-10,1992, discussing the AP600 _
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m DCP/NRCl409 NSD-NRC-98 5753 August 13,1998 testing program. The NRC has no record of a nonproprietary version of the slides being provided. At the time this presentation was rnade, the information was proprietary since that description of the AP600 testing program had commercial value to Westinghouse. At this time, almost six years later, this information does not have commercial value and is no longer considered to be proprietary by Westinghouse. Reference 2 provided the NRC assessment of the Westinghouse claim that proprietary infortnation was provided in a letter dated December 15,1992, that contained a preliminary description of the AP600 refueling outage plan activities. The NRC assessment was that no n'aterial in be letter was specifically identified as being proprietary and that a nonproprietarf version was cot provided. At the time this subject was being discussed with the NRC technical staff. the information was considered to he proprietary by Westinghouse since it contained information that had commercial value to Westinghouse. At this time, almost six years later, this information does not have commercial value and is no longer considered to be proprietary by Westinghouse. Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated February 24,1993, that contained presentation materials from the February 24,1993, Westinghouse /NRC AP600 senior management meeting. The NRC assessme'it was that the material was similar to material that exists in the current (1998) nonproprietary version of the AP600 probabilistic risk assessment and AP600 standard safety analysis report. In addition the staff indicated the material was used by the staffin the development of the AP600 draft safety evaluation report and therefore should remain on the docket. Our 1995 request, Reference 4, indicated that the material provided in the Westinghouse letter of February 24,1993, was presentation material that was intended i a for clarification only, not part of the formal review material and requested that the material be returned
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to Westingl( use. At the time this subject was being discussed with the NRC technical staff, the l infomation was considered to be proprietary by Westinghouse since it contained information that had l commercial value to Westinghouse. If this presentation material was indeed used by the staffin l development of the AP600 draft final safety evaluation repxt in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse. Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated April 19,1993, that contained presentation materials from the April 20, 1993, AP600 overview. The NRC assessment was that the material was similar to material that exists ; in the current (1998) nonproprietary version of the AP600 probabilistic risk assessment and AP600 ' standard safety analysis report. In addition the staffindicated the material was used by the staffin the development of the AP600 draft safety evaluation report and therefore should remain on the docket. Our 1995 request, Reference 4, indicated that the material provided in the Westinghouse letter of April 19,1993, was presentation material that was intended for clarification only, not part of the formal review material and requested that the material be returned to Westinghouse. At the time this subject was being discussed with the NRC technical staff, the information was considered to be proprietary by Westinghouse since it contained information that had commercial value to Westinghouse. If this presentation material was indeed used by the staffin development of the AP600 draft final safety evaluation report in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse, w,w G0/CO a 2002Gir10C18 01 244r PLC 2tr 3771n30dNOW-3de ad C2:Cl 86.C1 ene
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1 DCP/NRCl409 ! NSD NRC-98-5753 -3 August 13,1998 l Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was provided ir a letter dated July 14,1993, that contained presentation materials from the July 14, 1993, meeting where the AP600 main control room habitability was discussed. He NRC assessment was I that the material was similar to material that exists in the current (1998) nonproprietary version of the AP600 probabilistic risk assessment and AP600 standard safety analysis report. In addition the staff j indicated the material was used by the staff in the development of the AP600 draft safety evaluation
- report and therefore should remain on the docket. Our 1995 request, Reference 4, indicated that the l material provided in the Westinghouse letter of July 14,1993, was presentation material that was intended for clarification only, not part of the formal review material and requested that the material be returned to Westinghouse. At the time this subject was being discussed with the NRC technical staff, the information was considered to be proprietary by Westinghouse since it contained information ,
that had commercial value to Westinghouse. If this presentation material was indeed used by the staff l in development of the AP600 draft final safety evaluation report in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse. His response addresses the proprietary issues delineated in the references. w V fr-**' Brian A. McIntyre, Manager l Advanced Plant Safety and Licensing l l
. . , jml ec: J. W. Roc - NRC/NRR/DRPM J. M. Sebrosky - NRC/NRR/DRPM W. C. Huffman - NRC/NRR/DRPM H. A. Sepp - Westinghouse l
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