ML20115C086
| ML20115C086 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 07/01/1996 |
| From: | Quirk J GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MFN-094-96, MFN-94-96, NUDOCS 9607110164 | |
| Download: ML20115C086 (247) | |
Text
{{#Wiki_filter:. . . . _ _ 9 'IENuclearEnergy
- Joteph F. Quirk GeneralElectnc Company i ABWR Licensing Manager 175 Curtner Avenue. Ilc 782, San Jose, CA 95125-1014 ProjectManager ABWRCert16 cation 408 925-6219(phone 1 408 L?$-4257(facsimile)
July 1,1996 l MFN 094-96 l Docket No. 52-001 Document Control Desk U.S. Nuclear Regulatory Commission Washington DC 20555
Subject:
ABWR Design Control Document Changes l
Reference:
- 1. Letter (MFN 050-96) fromJoseph F. Quirk (GE) to Dennis M.
Crutchfield (NRC), dated April 16,1996, with enclosures of ten change packages for the Design Control Document.
- 2. Letter from Thomas H. Boyce (NRC) to GE Nuclear Energy,
" Summary of Meeting Held on May 1,1966 to Discuss Changes to the Design Control Document (DCD) for the GE ABWR", Dated May 8,1996.
- 3. Letter (MFN 079-96) fromJ. F. Quirk (GE) to Document Control Desk (NRC)," Changes to Design Documentation for the Advanced Boiling Water Reactor (ABWR)," datedJune 10,1996.
GE submitted for the NRC staff review ten proposed changes (Reference 1) to the l ABWR Design Control Document (DCD) which resulted from information developed in the course of the ABWR First-Of-A-Kind Engineering (FOAKE) program. The Reference 1 letter, included herewith as Attachment 1, provided background for the l need for the proposed changes. 9607110164 960701 l PDR ADOCK 05200001 A PDR l 1 l s
p I l Attachment 2 includes updated markups which incorporate comments resulting from l interactions between GE and the staff (References 2 and 3). Attachment 3 provides DCD markups for an additional proposed change identified following the submittal of Reference 1. Attachment 3 also includes the corresponding l ABWR design change assessment review of this FOAKE design change. GE will discuss Attachments 2 and 3 at the ACRS meeting on August 8,1996. Sincerely,
~
U J . Quirk
@roject Nianager ABWR Certification cc: (w/ attachments)
JN Wilson (NRC) FA Ross (DOE)
.~.
F ATTACHMENT 1 I l Letter (MFN 050-96) fromJoseph F. Quirk (GE) to Dennis M. Crutchfield (NRC), dated April 16,1996 (Not including enclosures transmitted with the letter) i I t i l l
. GENudearEnergy l Joseph F. Ouut GeneralElectnc Company ABWR Ucenshg Manager 175 Curtner Avenue, MC 782; San Jose, CA 951251014 Project Manager ABWR CerttRcation 408 925-6219(phone) 408 925-4257(facsimae)
April 16,1996 MFN 050-96 Docket No. 52-001 Mr. Dennis M. Crutchfield Associate Director for Advanced Reactors and License Renewal OfIice of Nuclear Reactor Regulation l U S. Nuclear Regulatory Commission i Washington, D.C. 20555
Dear Mr. Crutchfield:
Transmitted herewith,in the form of markups to pages of the ABWR Design Control Document (DCD), are ten proposed changes to the ABWR design description which result from information developed in the course of the ABWR First-Of-A-Kind Engineering (FOAKE) program. Ten copies are enclosed for review by the NRC staff. The need for the proposed changes prior to completion of rulemaking has only recently been determined from an updated analysis of FOAKE detailed design information. The background for that analysis and this submittal is set forth below. GE undertook the ABWR FOAKE activity pursuant to aJune 1993 contract with the Advanced Reactor Corporation (ARC) to perform detailed design of the ABWR for its use in the United States. The basic approach of the GE FOAKE activity is to develop the design details of the ABWR consistent with the requirements of the design undergoing NRC certification, a key objective being the development and maintenance of a highly standardized design. This means that the certified design and the FOAKE design must be consistent, with the FOAKE design being much more detailed in its description. The FOAKE design activity may identify changes which would result in a substantial benefit to safety, reliability or economy. Their consideration, however, is done under an approach which is closely controlled. Any proposed design change to the DCD is processed in accordance with rigorous internal GE review procedures; and proposed changes are only accepted for compelling reasons,in the spirit of maintaining the detailed ABWR design as close as practicable within the boundaries of the DCD. In December of 1995, two design changes were identified that were needed to bring the DCD into compliance with NRC regulations in effect at the time of FDA issuance. In order to take full advantage of the thoroughness of the FOAKE activity, it was then decided to re< valuate all the FOAKE Engineering Change Authorizations (ECAs) for purposes of determining if any other proposed DCD changes should accompany the two that were initially identified. Enclosed is a summary description of the resulting proposed DCD changes and of the screening criteria used by GE to evaluate whether the FOAKE infonnation requires, or otherwise merits, change to Tier 1 or Tier 2 of the DCD. 3Q < 9 (g D 'l NM N9
f l 1 1 O GENuclearEnangy i Five of the changes proposed herewith are to Tier 1 (and corresponding portions of i Tier 2) of the DCD and five are to Tier 2 only. None of the proposed changes are necessary to assure adequate protection of the public health and safety. Rather, as described in the enclosure, two are proposed to bring Tier 1 or Tier 2 into compliance with regulations in ; effect at the time the ABWR FDA was issued, four are proposed to make the design described I in the DCD functionally operable as intended, one is proposed to effect a change to technical specifications, and three would effect design improvements which require minor modificadons and which GE believes should be incorporated in the DCD at this time. We believe the six changes proposed to assure regulatory compliance and functional operability need to be made prior to completion of design certification. As respects the change to technical specifications and the three design improvement changes, we believe it desirable, though not essential, that these changes be made now; we are, however, prepared to defer them if their present consideration would delay timely completion of staff review of the six required changes. The FOAKE program has identified a number of additional desir ble design improvements; however, the implementing design change. nccd net be made at this time since they qualify for post <ertification 950.59-type change treatment (i.e., they do not affect Tier 1 or Tier 2* or technical specifications, or result in an unreviewed safety question). Those changes will be made in accordance with governing procedures as established by the Commission. We will, of course, cooperate fully with the staffin completing early review of and action on the proposed design changes submitted herewith. Sincerely yours,
. , e,x FOR Joseph F. Quirk cc: (w/o attachments)
WT Russell (NRC) FJ Miraglia (NRC) TH Boyce (NRC) SM Franks (DOE)
GENuclearEnergy ABWR Design Change Assessment Review of FOAKE Design Changes Change Description Tier 1 Screen Remarks No. Impact (Notes) 1 Change the Reactor Building and Radwaste Yes 4 This change addresses a Building HVAC Systems to use electric heating reliability & maintainability in place of hot water heating, split the single issue, rather than a safety intake configuration into three to provide concern. The change redundancy, and use high efficiency filters in results in a minor place of medium grade bag-type filters. Use of modification to Tier 1, electric heating will avoid in senice freezine. although there is no The change will provide air intake redundt icy functional Tier 1 impact. to satisfy system maintenance needs. 2 Add an additional chiller / pump set to the No 4 The change does not impact IIVAC Emergency Cooling Water System. This Tier 1 because Tier 1 does provides functional redundancy to avoid the not specify divisional loss of cooling for the Control and Reactor equipment quantity and Building Safety-Related Electrical Equipment logic. Area HVAC Systems, potentially challenging electrical equipment emironmental qualification temperature limits. The added l redundancy will also satisfy system maintenance I needs. 3 Change the smoke removal method for three Yes 3 The change ensures HVAC systems (for Reactor Building Safety- functionality and Related Electrical Equipment, Control Room compliance with Tier 2 liabitability Area, and Control Building Safety- commitments. Related Equipment Area) to comply with the accepted method prescribed by the industrial standards (ASHRAE and NFPA) referenced in Tier 2. Further, replace centrifugal fans with vaneaxial type fans as necessary for space conservation. Finally, provide senice to the FMCRD Panel Rooms from Divisions A and B of the Reactor Building Safety-Related Electrical Equipment HVAC System, instead of Disisions B and C. 4 Reassign the Main Control Room HVAC Yes 4 The change has no safety exhaust fans ("B" as "C," and "C" as "B") significance and no impact according to their respective divisional space. on the safety functions This change will avoid a potential divisional described in Tier 1. crossover of cooling and power. However, it does impact designations on Tier 1 ar,d Tier 2 figures. l .
l . h GENuclearEnergy ABWR Design Change Assessment Review of FOAKE Design Changes l 5 This change package identifies various Tier 1 Yes 3 Tier 1 and Tier 2 figures and i and Tier 2 inconsistencies, such as the text are modified. I radiation zone classification of a room shown in figure, " Reactor Building Radiation Zone Maps, Elevation 12300 mm."
)
6 Provide power for each pair of motor operated Yes 1 The change is necessary to I isolation dampers in series (total four pairs in a ensure compliance with division) for the Control Room Habitability single failure criteria. l Area HVAC System from two independent Class ' 1E divisions,instead of powering both dampers l from a single division. Also, reflecting the Tier 2 arrangement, a cross-tie is added between the two inlet ducts of the Emergency Filtration Unit l on the Tier 1 figure. All of this assures necessan alignment of dampers and prevention ofinfiltration of unfiltered air in case of l emergency and loss of one division of power. 7 Delete the rupture disks originally intended to No 3 The change is necessan for protect the low pressure exhaust side of the conformance to Tier 2 l RCIC turbine case and exhaust line from commitments on ISLOCA. overpressurization. Existence of the rupture disks is not consistent with interfacing system LOCA (ISLOCA) requirements. Removal of the rupture disks and upgrading of the associated piping and valves corrects a SSAR inconsistency regarding ISLOCA. 8 Upgrade the FMCRD and scram piping design No 1 A change in design pressure pressures based on tests and evaluations of is needed due to new design water hammer effects. The changes are infonnation. The change consistent with the ASME Code which requires ensures compliance with use of equipment events rather than plant ASME Code per events in determining the design pressure. 10CFR50.55a. 9 Use a higher strength material for the cladded No 3 Based on detailed design shells of the lower drywell access tunnels and evaluations, the materials RPV pedestal. This change is identified based specified in the DCD are not on considerations of cladability of the material adequate. and strength to withstand high thermal stresses predicted by detailed analyses performed subsequent to the SSAR review stage of the licensing process. 10 Correction of inconsistencies in technical No 2 Based on detailed design specifications (Chapter 16 and related Tier 2 evaluation and review of l sections), technical specifications. 1
L l
. GENudoarEnergy l
l ABWR Design Change Assessment Review of FOAKE Design Changes 1 i Noich Screeninc Criteria: GE will not propose to change its DCD during the period from FDA issuance to Design Certificadon unless: 1.) The change corrects an error or deficiency necessary to assure adequate protecdon of the public health and safety, or to bring the DCD (Tier 1 or Tier 2) into compliance with regulations in effect at the dme the ABWR FDA was issued; 2.) The change affects a technical specification: 3.) The change is necessary to make the DCD design functionally operable (as intended); or 4.) The change is a design improvement which GE determines should be incorporated into the design at this dme. All changes which sansfy Criteria 1,2 or 3 shall be incorpo ated into the DCD prior to Design Certificadon. Any Tier 1 or Tier 2 changes which satisfy Criterion 4 should be addressed on a case-by-case basis. i i 1 l l
i 1 l ATTACHMENT 2 Change Packages ! (Include Updated Markups of the ABWR DCD Pages) l Not : Each marked up page is identified with the Change Package No., e.g., CP 1, it belongs to.
l i ABM Design contret oocument PROPOSED CHANGES i l i ! CHANGE PACKAGE NO.1 I l \ l 1 l I l Eliminate Hot Water Heating ! ! for RB and RWB HVAC and Reconfigure RB HVAC Filters ! l l L I
i 1 i Rev.0
, ABWR oasioncananarcocaneavner1
( 2.11.3 Reactor Building Cooling Water System 1 Design Descnption l The Reactor Building Cooling Water (RCW) System distributes cooling water through three physically separated and electrically independent divisions. The system removes ; heat from plant auxiliaries anf msfers it to the Ultimate Heat Sink (UHS) via the ' Reactor Senice Water (RS%" * ; am. The RCW System removes heat from emergency , core cooling equipment,induding the emergency diesel generators (DGs) during a l l safe reactor shutdown cooling function. RCW System configurations are shown in Figures 2.11.Sa,2.11.Sb, and 2.11.Sc. Figure 2.11.Sd shows the RCW System control interfaces. All components cooled by the RCWSystem are parts of othersystems and are l not part of the RCW System. Each RCW division indudes two pumps which circulate l l cooling water through the equipment cooled by the RCW System and through three I l heat e; changers which transfer the RCW heat to the UHS via the RSW System. l The RCW System performs a safe reactor shutdown cooling function following either a ' loss-of coolant accident (LOCA) or a loss of-preferred-power (LOPP)or both. Assuming l l a single active failure in any mechanical or electrical division or RCW support system, )
; which disables any one of the three RCW divisions, the other two divisions perform safe
( reactor shutdown cooling. l Tables 2.11.Sa,2.11.Sb, and 2.11.Sc show which equipment receives RCW flow during l various plant operating and emergency conditions. The tables also indicate how many heat exchangers are in service under each condition. The RCW System is dassified as safety-related except for those portions as shown on Figures 2.11.Sa, 2.11.Sb, and 2.11.Sc as non-nudear safety. l The PIM System responses to a LOCA signal are the following-(1) Stans any standby RCW pumps. l (2) Opens any dosed standby RCW heat exchanger outlet ulves. (S) Opens all Residual Heat Removal (RHR) System heat exchanger cooling l water outlet valves. l (4) Closes all RCW containment isolation valves. 1 (5) Closes valves to the following non-safety-related components (to Reactor Water Cleanup System (CUW) =d "n '/ law Ik2ing 9 '") S r = N 2-hnhrge.; and reactor internal pump (RIP) MG sets). 7 o Reactor Building Cooling Water System 2.11.3-1 1
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. ABWR okien canrotDocumanmer1 MUWP RCW RCW OTHERS OTHERS RCW SNU KW f~
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RCW HX C (Conard Buktnr3 3 RCW RCW PUMP N M l t NOTES:
- PRIMARY CONTAINMENT l 1. ALL ELECTRICAL POWER LOAD 3 FROM THE CLASS 1E COMPONENTS SHOWN ON THIS FIGURE ARE POWERED FROM CLASS 1E DIVtSION I EXCEPT FOR TE l
OUTBOARD CONTAINMENT ISOLATION YALVE. WHICH IS POWERED FROM DIVISION 11. Figure 2.11.3a Reactor Building Cooling Water System (RCW-A) Reactor Building Cochng Water System 2* I '*
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R RCW HX C FROM RSri ;I Q ['W TO RSW RCW PUMP (Cosmol Bekang) NOTES:
* = PRIMARY CONTAINMENT
- 1. THIS DIVISION IS POWERED FROM CLASS 1E DNISION 11 EXCEPT FOR THE CONTAINMENT OUTBOARD ISOLATION VALVE.WHICH IS POWERED FROM DIVISION lit i
Figure 2.11.3b Reactor Building Cooling Water System (RCW-B) Reactor Building Cooling Water System 2.11.3-6 3 l f i
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B <10 l c<so D<250 E <1000 F 210C0 l Figure 3.2k Reactor Building Radiation Zone Map for Full Power and Shutdown Operations, Floor 3F-Elevation 23500 mm 3.2-12 Radiation Protection 6
1 Rev.O c ABWR oeiira cenaetoocamentmer2 1 .. (.. , 1.2.2.12.10 Turbine Service Water System The Turbine Senice Water System is summarized ion Subsection 9.2.16.1.3 and 9.2.16.2.3. 1.2.2.12.11 Station Service Air System The Station Service Air System provides a continuous supply of compressed air of , suitable quality and pressure for general plant use. The service air compressor discharges into the air receivers and the air is then disuibuted throughout the plant. 1.2.2.12.12 instrument Air System ; l l The Instnunent Air System is summarized in Subsection 9.3.6.2. I 1.2.2.12.13 High Pressure Nitrogen Gas Supply System Nitrogen 1;as is normally supplied by the Atmospheric Control System to meet the requirement of (1) the Main Steam System SRV automatic depressurization and relief function accumulators, (2) the main steam isolation valves, and (3) instruments and pneuraatic valves using nitrogen in the Reactor Building. When this supply of pres surized nitrogen is not available, the High Pressure Nitrogen Gas Supply (HPIN) , System aatomatically maintains nitrogen pressure to this equipment. The HPIN System { consicr. of high pressure nitrogen storage bottles with piping, valves, instruments, controls and control panel. 1.2.2.12.14 Heating Steam and Condensate Water Return System The Heating Steam and Condensate Water Return System supplies heating steam from the House Boiler for general plant use and recovers the condensate return to the boiler feedwater tanks. The system consists of piping, valves, condensate recovery set and associated controls and instrumentation. 1.2.2.12.15 House Boiler System i The House Boiler System consists of the house boilers, reboilers, feedwater components, boiler water treatment and control devices. The House Boiler System l supplies turbine gland steam and heating steam, including the concentrating tanks and devices of the high conductivity waste equipment. , 1.2.2.12.16 Hot Water Heating System 3, [e h The Hot Water Heating System is a closed-loop hot water supply to the various heating coils of the HVAC systems. The system includes two heat exchangers,@-7Er a [ [ ' Qhg[ urge and chemical addition tanks and associated equipment, controls ai j instrumentation. 5 tie)L Generaf Plant Description 1.2 30 7
1 1 m 1 R3.0 . ABWR isine eneetoecamattrnr2 ! r 1 j Table 3.2-1 Classification Summary (Continued) Quality Quality Assur-Group anee Safety Classi- Require. Seismic Principal Component
- Class" Location
- fication d ment
- Category' Notes l
- 6. Other non-safety- N SC,RZ,X - E - ,
I related electrical components I P14 Hosting Steam and N T,SC,W - E - i Condensate Water Retum Syste m 6tet " T " P15 House Boiler N T - E - cpl P16 Hot Water Heating System N ,
- E -
C,
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( P17 Hydrogen Water Chemistry N T - E - i System P18 Zineinjection System N T - E - P19 Breathing Air System N C,SC,T E -
)
P20 Sampling System (includes N SC,RZ,T - E -- PASS) P21 Freeze Protection System N O - E -
- l P22 fron injection System N T - E -
R1 Electrical Power Distribution System
- 1. 120 VAC safety-related 3 SC,X, - B 1 distribution equipment RZ,U including inverters
- 2. Safety-related Motors 3 SC,C,X, -
B I RZ,U Notes and footnotes are listed on pages 3.2-54 through 3.2-61 Classification of Structures Components, and Systems 12M 8
s Rev.0 , ABWR ouien Conrolananuttrier2 Table 6.2 9 Secondary Containment Penetration List * (Continued) Penetration Name Elevation Diameter Number (mm) (mm) 32 RCW (C) -1700 100 33 RCW(C) -1700 200 34 RCW (C) -1700 200 35 HS 4800 150 36 MS 4800 80 37 LCW(FPC) 4800 150 38 LCW(CUW) 4800 150 39 RCIC 4800 50 40 MS (4) 16191 700 ) 41 FDW (2) 13810 600 t 42 HVAC Exhaust 27200 t 43 HVAC Supply 31700 12300 44 Controlled Access (2) ( 45 Equipment Lock 12300
* "58'# ..
46 Railroad Car Door 12300 47 HS 12300 150
^
48 "?!" 12^-- 0 100 -f CPL 4~4 "?ai 12000 100 , 50 HNCW 12300 200 i 51 HNCW 12300 200 52 MUWP 4800 150 53 AC 4800 50 54 AC 4800 250 h at'+ 55 - l '"Mi 4 00 50 ( e" De I C + 56 - l lV " l '.000 00 o' 57 Cabletrays 23500 58 Cabletrays 12300 59 Cabletrays 4800
- This table is provided in response to Question 430.34.
t These HVAC openings have safety-related isolation valves with both local monitoring and remote (in control room) monitoring.
- These doors are monitored in the control room as per Subsection 13.6.3.4.
6.2-183 Containment Systems 9
_ _ _ _ - _ - _ _ _ _ _. _ ~_ . _ _ - _ _ _ - _ _ _ _ -. - __ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ .-_ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _
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Table 9.2-4a Reactor Building Cooling Water Division A 1h
@ Of 8 Emergency 3 Normal (LOCA) g Operating Shutdown at 4 Shutdown at Hot Standby Not Standby (Suppression Conditions Hours 20 Hours (No Loss of AC) (Loss of AC) Pool at 97'C Operating Mode / Components Flow Heat Flow Heat Flow Heat Flow Heat Flow Heat
- Flow
- Heat Essential
- - - 13.40 229 13.40 229 Emergency Diesel Generator A - - - -
108.02 1,199 34.75 1,199 - - 25.54 1,199 89.18 1,199 RHR Heat Exchanger A - - 205 3.60 205 3.81 205 3.39 205 4.10 205 4.19 205 Others (essentiall' 3.18 Non-Essential 20.10 159 159 159 20.10 159 20.93 159 - - CUW Heat Exchanger' - - 7.12 279 7.12 279 7.12 279 0.63 279 FPC Heat Exchanger A I 7.12 279 7.12 279 320 5.86 320 5.86 320 5.86 320 3.39 320 - - inside Drywell" 5.86 2.64 160 2.64 160 2.64 160 0.84 59 0.75 59 2 Others (non-essential)" 2.64 160 127.24 2,322 54.01 2,322 38.94 1,123 75.36 2,450 117.23 1,971 k Total Load 38.94 1,123
- Heat in GJ/h; flow in m%- ,,ms may not be equal due to rounding.
t HECW refrigerator, C . aolers, room coolers (RHR, RCIC, CAMS), RHR motor and seal coolers.
- The heat transferred from she CUW heat exchanger at thd start of cooldown is appreciable, but during the critical last part of a cooldown, the heat removed is very little because the temperature difference between the reactor water and the RCW System is small. Sometimes, the operators may remove the CUW heat exchangers from service during cocidown.Thus, the heat removed varies from about that during normal operation at the start of cooldown to very little at the end of cooldown.
f includes FPC room cooler. [ U g, N - g-
" Drywell (A & C) and RIP coolers.
t t instr _uments and service air coolers: CUW pump cooler, CRD pump oil, and RIP MG sets A tc; ..r:: wh=;;;r !: 5 ^t?: i::':- '- t? h rr r: R p h::: S;r the "CY! Sy *:r [ P hlc le I c, x k
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I Table 9.2-4b Reactor Building Cooling Water Division B b E Emergency W w ILOCA)
)g Normal Operating Shutdown at 4 Shutdown at Hot Stendby Hot Standby (S5.- _ i.
Conditions Hours 20 Hours (No Loss of AC) (Loss of AC) Pool at 97*C Operating Mode / Components Heat
- Flo w
- Heat Flo w Heat Nw Host Nw Heat Flow Heat Flow Essential 13.40 229 13.40 229 Emergency Diesel Generator B - - - -
108.02 1,199 34.75 1,199 - - 25.54 1,199 89.18 1,199 RHR Heat Exchanger B - - 6.28 360 6.70 360 6.70 360 6.28 360 7.12 360 7.95 360 Others (essential)' Non-Essential CUW Heat Exchanger' 20.10 159 - 159 - 159 20.10 159 20.93 159 - - 7.12 279 7.12 279 7.12 279 7.12 279 7.12 279 9.63 279 FPC Heat Exchanger Bf 279 6.28 279 5.40 279 5.40 279 2.51 279 - - Inside Drywell" 5.44 159 1.47 159 1.47 159 1.47 159 0.33 9.1 - 9.1 2 Others (non essential)" 2.93 Total Load 41.87 1,236 129.79 2,435 55.27 2,435 40.19 1,236 77.04 2,514 120.16 2,076 k
- Heat in GJ/h; flow in m /h,3 sums may not be equal due to rounding.
t HECW refrigerator, room coolers (RHR, HPCF, SGTS, FCS, CAMS), CAMS cooler, HPCF and RHR motor and mechanical seal coolers.
- The heat transferred from the CUW heat exchanger at the start of cooldown is appreciable, but during the critical last part of a cooldown, the heat removed is very little because the temperature difference between the reactor water and the RCW System is small. Sometimes, the operators may remove the CUW heat exchangers from service during cooldown. Thus, the heat removed varies from about that during normal operation at the start of cooldown to very little at the end of cooldown.
f includes FPC room cooler. hfc ,
*
- Drywell (B) and RIP coolers.
t t Reactor Building sampling coolers;1.CW sump coolers (in drywell and reactor building) RIP _hiG sets and CUW pump coolers. ,5 ',- -r - ' m:91. .. . . . 2:':n;;:;:::- 5:: ni:n;;:: 5 P 'S: :-:: _
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1 Design inside air temperatures for the secondary containment during normal operation is 40*C maximum in the summer and 10*C minimum in the winter. 4 4 9.4.5.1.2 System C:: 1'/k -
- deIdc 3 The Reactor Building secondary arminnient HVAC Sys m P&ID is sh in Figure 9.4-3.The system flow are given in Table 9. , and the sys m compon t thermal capacides are given in able 9.4-4.The HVAC m is a on rough .
Outdoor airis filtered, tempe and delivered to th secondary co tainment. supplyairsystemconsistsofn9-' ,, 'li filte ,$lIcating co' , gcooling co' , and (.f1 4 three 50% supply fans located in the Turbine Budding. Two are normally operating and i' the other is on standby. The supply fan delivers conditioned air through ductwork and j registers to the secondary containment equipment rooms and passages. The exhaust air j system consists of 3 filters and S-50% capacity fans to be located in the Turbine Building. ! The exhaust fans pull air from the secondary contmnment rooms through ductwork, ' and filters. Moniton measure radioactivity before it is exhausted from the plant stack. HVAC air supply and exhaust used by the ACS for pnmary containment deinerting is I sm-d in Subsection 6.2.5.2.1(14) and the shutdown mode of operation in 4 Subsection 6.2.5.2(3). Electric unit heaters are located in the large component j' entrance building. Supply air is directed into the space when the interior <foors are H open. I' 9.4.5.1.3 Safety Evaluatio6: ! Operation of the Secondary Contamment HVAC System is not a prerequisite to ! assurance of either of the following: 9 (1) Integrity of the reactor coolant pressure boundary. ! I (2) Capability to safely shut down the reactor and to maintain a safe shutdown ! condition. I i However, the system does incorporate features that provide reliability over the full l.
- range of normal plant operation. The following signals automatically isolate the l Secondary Containment HVAC System
j (1) Secondary containment high radiation signal (LDS) t j- (2) Refueling floor high radiation signal (LDS) 2 i (S) Drywell pressure high signal (LDS) i (4) Reactor waterlevellow signal (LDS) (5) Secondary containment HVAC supply / exhaust fans stop f 94-17 Air Conditioning. Heating. Cooling and Ventilating Systems 3 13 l 1
Rev. o . ABWR osine coneetoocmeenvrier2 flows for conformance. to the desgn requirements. All major components are tested and inspected as separate components prior to installation to ensure design performance. The system is preoperationally tested in accordance with the requirements of Chapter 14. 9.4.6.5 Instrumentation Application 9.4.6.5.1 Radweste Building Control Room o ncJ ca n e l e c+ de. h
- chS coII D*I The air-conditioning unit for the dwaste control room HVAC is started manually. A
' ' ' tem .rature indicating controller odulates the air-conditioning system via f ot ter hilled water valve to maintain space conditions. A differential pressure -Cg 3,i,q mdicanng controller modulates inlet vanes in the supply fan air inlets to maintain the positive static room pressure. Differential pressure indicators measure the pressure drop across the filter bank.
9.4.6.5.2 Radweste Building Process Area HVAC The air exhaust and supply fans for the Radwaste Building Process Area HVAC are started manually. The fan inlet dampers open when the fan is started. A flow switch installed in the exhaust fan discharge duct actuates an alarm on indicadon of fan failure in the main and radwaste control rooms and automatically starts the standby f.m. The exhaust fan is interlocked with the supply fan to prevent the supply fau from operating if the exhaust fan is shut down. Two pressure-indicating controllers modulate variable inlet vanes in the supply fan to maintain the area at a negative static pressure with respect to the atmosphere. The switch causes an alarm to be actuated if the negative pressure falls below the presetlimit. Diferential pressure indicators measure the pressure drop across the Siter section. The switch causes an alann to be actuated if the pressure drop exceeds the preset limit. Radiation monitors are installed in the radwaste process area exhaust duct to the main plant stack. A high radiation signal in the duct causes alarms to annunciate in the main control room and the radwaste control room. If the radwaste process area exhaust radiation alarm continues to annunciate, the work area branch ducts are manually isolated selectively to locate the affected building area. Should this technique fail, because the airborne radiation has generally spread throughout the building, control room air conditioning continues operating. However, the air conditioning for the balance of the building is shut down. The operators, using approved plant health physics procedures, then enter the work areas to locate and isolate the leakage source. 9.433 Air Conditioning Meeting. Cooling and Ventitating Systems 14
. l R.w. 0 -
ABWR oesias coneosoocaarengrier2 Table 9.44f HVAC System Component Descriptions-Non-Safety Related Heating Cooling coilsjResponse to Question 430.243) (p.ept.c w%e o., A )..) T
'3, ( t . .,
- Cooling Hosting l Hosting / Cooling Coils s Querstity (MJ/h) (MJ/h)
R/B Secondary Containment HVAC Ng* 6435.95 9601.17 ( RIP ASD HVAC Division A 1 2110.15 RIP ASD HVAC Division B 1 2110.15 Table 9.4-4g HVAC System Component Descriptions-Non-Safety-Related Fans (Response to Question 430.243) Cfb Fans Quantity Capacity (m3 /h) R/B Secondary Containment Supply Fans 3 (1 on standby) 84,250
, R/B Secondary Containment Exhaust Fans 3 (1 on standby) 86,250 R/B Primary Containment Supply Fan 1 22,000 R/B Primary Containment Exhaust Fan 1 22,000 RIP ASD Division A Supply Fans 2 (1 on standby) 50,000 RIP ASD Division B Supply Fans 2 (1 on standby) 50,000
)
l Table 9.4-4h HVAC System Component Descriptions-Non-Safety-Related Filters l (Response to Question e~ 430.243)-
$ Repias. w%
Filters a Ity Capacity (m3 /h) R/B Secondary Containment HVAC % " M .h J fr 172,5^^ f tls6a so R/B Primary Containment intake HEPA Filter 1 22 ,000 R/B Secondary Containment Exhaust Fans 3 57,500 (each) l l 4 Air Conditioning. Hearing. Cooling and Ventilating Systems 9AM l 15
Rev.o ABWR oasion coneoloocamentmer2 Table of Contents (Continued) (. , 9A.4.1.6.22 Not Used .. ......... ....... .... ...... ..... .... .... ... ... .... .... .. . 9A.4-297 9A.4.1.6.23 Not Used ..................~................................9A.4-297 9A.4.1.6.24 Upper D/G A HVAC Room (Rm No. 653) ...... .... . 9A.4-297 9A.4.1.6.25 FMCRD A/C Panel Room (Rm No. 654) ............... .... 9A.4-298. 9A.4.1.6.26 Not Used ............ . .................................... 9A.4-300 9A.4.1.6.2 7 No t Used . .- .. .......... .......... -.. ............ ....... 9A.4-300 9A.4.1.6.28 Not Used . . . . ........ .... ....... . ......... ........ .. 9A.4-300 9A.4.1.6.29 Not Used . ........... ..... . .. . . . . . . . . . . 9A.4-300 9A.4.1.6.30 Upper D/G C HVAC Room (Rm No. 673) .. ......... .... 9A.+300 9A.4.1.6.31 Not Used . ..... ... . . . . . . . . . . . . . .. ........ . . . 9A.4-302 9A.4.1.6.32 Upper D/G B HVAC Room (Rm No. 663) .............-.. . 9A.4-302-9A.4.1.6.33 Upper Corridor B (Rm No. 626) ............ ...... .. ... . -. . 9A.4-304 9A.4.1.s .34 Not Used . .. ... .... ...... . ... ........ .. ....... .... ......... . . 9A.4-306 9A.4.1.6.35 FMCRD D/B Panel Room (Rm No. 681) ......... ... .9A.4-306 - 9A.4.1.6.3 6 Not Used .. ................... .... .............- . ........................ 9A.4-307 9A.4.1.6.37 Not Used. .. ..........................................................9A.4-307 - 9A.4.1.6.38 MS Tunnel HVH Room (Rm No. 685) ..... .................... 9A.4-307 9A.4.1.6.39 Pits and Pools. ...... . .. ....... ... ... . .. . .. .... ...... . 9A 4-30 9 9A.4.1.6.40 PVC Purge Exhaust Fan (Rm No. 623) .... ... ... . . ... 9A.4-310 9A.4.1.6.41 D/G C Corridor Room (Rm No. 635) ..... .... . 9A.4-311 g_ _ 9A.4.1.6.42 _ RIP Power Supply Room (Rm No. 638) .. .. ........... .. ... 9A.4-312 9A.4.1.6.43 Q("JII h p ud IIca Langer Room
. , ep: g r
( Rm No. 640 ) .... ........... .... .... ......... ..... ........ ........ 9A.4-314 9A.4.1.6.44 Fission Product Monitoring (Rm No. 657)... ..... ... .. 9A.4-315 9A.4.1.6.45 Room No. 658 ...................................... 9A.4-317 - 9A.4.1.6.46 Contamment Atmospheric Monitoring System (CAMS) Rack A (Rm No. 659)... .... ..... . ... ..... ...... 9A.4-318
** 4 "M C F d-
, e 9A.4.1.6.47 ppu I"S '-Ic= Ed=g= =d F=JRoom (Rm No. 680) ...... .. ... . .... ..... .... ..... .. ........ .. ... 9A.4-320 9A.4.1.6.48 Not Used ...... ........ . .......... .... .......... .... 9A.4-322 9A.4.1.6.49 Containment Atmospheric Monitoring System (CAMS) Rack B (Rm No. 621)- .... .. .... ..... .. .. . 9A.4-322 9A.4.1.6.50 Not Used . .................... .... .. .............. ..... .... 9A.4-324 9A.4.1.7 Building - Reactor Bldg EI 31700mm .. ..... ...... - 9A.4-324 9A.4.1.7.1 Reactor Building Operating Deck (Rm No. 716) .. .. .. . 9A.4-324 9A.4.1.7.2 RIP (A) Supply Fan and RCW (C) Surge Tank (Rm No. 715) . . ... ..... . . . . . . . . . -.................. .. ... . 9A.4-32 6 9A.4.1.7.3 Not Used .... .. ... ... . . . . . . . ..... ........ ..... .......... 9A.4-328 ~
9A.4.1.7.4 DG (C) Exhaust Fan Room (Rm No. 730) ...... .. ..... .... 9A 4-328 9A.4.1.7.5 Not Used .. .... ... . . . . . . . . . . . . . . . . . . . . . . . . . 9A.4-329 9A.4.1.7.6 RIP (B) Supply Fan and RCW (B) Surge Tank (Rm No. 740) . . .. ........................ 9A.4-329 9A.4.1.7.7 Access Service Area (Rm No. 764) . .......... ......... - 9A.4-331 9A.4.1.7.8 Refueling Machine Control Room (Rm No. 760)... ...... 9A.4-333 9A.4.1.7.9 Gallery (Rm No. 762). ... . ..... . . . . . . . . . . - 9A.4-334 9A.4.1.7.10 Memmne Corridor (Rm No. 761) .......... .. ....... . . 9A 4-336 9A.4.1.7.11 Roof A/C Area (Rm No. 810 and 830) ... ......... . 9A.4-337 9A.0 vi Table ofContents 16
Rev.0
- ABWR oests centrossecumentiner2 s
(3) Radioactive Material Present-None that can be released as a result of fire. (4) Qualifications of Fire Barriers-The exterior wall, inside wall, ceiling and floor of this corridor are of S h fire-resistive construction. This corridor extends across the reactor building. At the south end of the corridor, a S h fire-resistive door opens to the "?" F.=: =fcgr rd pung =:f(Rm 640). - At the otherend ofthe corridor, a nonrated door opens into D/G (A) exhaust fan area (Rm 613). ,.g ;pw ,,,m (5) Combustibles Present: g Fire Ledag Total Heat of Combustion (MJ) 2 None 727 MJ/m2 NCLL (727 hq/m maximum average) applies. (6) Detection Provided-Class A supervised POC in the room and manual alarm pull station at Col.1.0-B.2 and 6.2-B.O. (7) Suppression Available: Type Location / Actuation Standpipe and hose reel Col.1.0-B.2 & 6.2-B.0/ Manual ABC hand extinguishers Col.1.0-B.2 & 6.2-B.0/ Manual (8) Fire Protection Design Criteria Employed: (a) The function is located in a separate fire-resistive enclosure. (b) Fire detection and suppression capability is provided and accessible. (c) Fire stops are provided for cable tray and piping penetrations through rated fire barriers. (9) Consequences of Fire-Alternate routes to the areas interconnected by the corridor are provided. Smoke from a fire will be removed by the EHVAC(A) system operating in its smoke removal mode. (10) Consequences of Fire Suppression-Suppression extinguishes the fire. Refer to Section 3.4 " Water Level (Flood) Design", for the drain system. Analysis 9A.4.gy 17
Rev. o a ABMfR DEtinacennretoecanenttrierz ( (2) Equipment: See Table 9A.62 Safety-Rel= tad Provides Core Cooling Yes, D1 Yes, D1 (S) Radioactive Material Present-None that can be released as a result of fire. (4) Qualifications of Fire Barriers-All walls are of S h fire-resistive construction. A section of the ceiling below the FMCRD panel room (Rm 681, fire, F7200) is of S h fire-resistive concrete construction. Secdons of the floor above the D/G Fan and HVAC room B (Rm 524), and the service corridor B (Rm 527) are of S h Sre-resisdve concrete construction. Access to the area is provided from the stairs and elevator (areas 329 and 328 respectively), from corridor ~ Rm 655 (via corridor Rm 626) and from p the "."1" h= cd .;;. == (Rm 640). Each access route is through a S h fire-resistive door. (5) Combustibles Present elecDic"I *1"'Y ~ # ~ Fire Loading Total Heat of Combusdon (MJ) 2 2 Cable Tray 727 MJ/m NCLL (727 MJ/m maximum average) applies (6) Detection Provided-Class A supervised POC in the room and manual alarm pull stations at 1.4 D.7,1.0-B.2. (7) Suppression Available: Type Locadon/ka=* ion Standpipe and hose reel Col.1.4-D.7, and 1.0-B.2/ Manual ABC hand extinguishers Col.1.4-D.7,and 1.0-B.2/ Manual (8) Fire Protection Design Criteria Employed-(a) The function is located in a separate fire-resistive enclosure. (b) Fire detection and suppression capability is provided and accessible. (c) Fire sts ns are provided for cable tray and piping penetrations through rated fire uarriers. Analysis 9A4-287 18
Rev. o
. ABWR onsinia coneetoeanmenttrier2 eleefrical *P; Hat (S) Radioacdve Material Present-None.
(4) Qualifications ofFire Barrien-The walls common with the g . "' i~...p nd . he- ^ ger room (Rm 640), the SBGTS filter train room (Rm 642), corridor room (Rm 614), the floor above the steam tunnel and the ceiling serve as fire barriers between adjacent fire areas and are of S h fire-resistive concrete construction. A 3 h fire mted door provides access from the AC filter / fan area (Rm 615). Room 643 connects direcdy into room 622. C O i-(5) Combustibles Present: HreIoadmg Total Heat of Combustion (MJ) 2 2 Cable Tray 727 MJ/m NCLL (727 MJ/m maximum average) applies (6) Detecdon Provided-Class A supervised POC in the room and manual alarm pull stations at 2.7 C0 and 2.8 F.1. r (7) Suppression Available: Type Locadon/ Actuation Standpipe and hose reel Col. 2.7-C.0,& 2.8-F.1/ Manual A'3C hand exdnguishers Col. 2.7-C.0,& 2.8 F.1/ Manual (8) Fire Protecdon Design Criteria Employed: (a) The funcdon is located in a separate fire-resisdve enclosure. (b) Fire detecdon and suppression capability is provided and accessible. (c) Fire stops are provided for cable tray and piping penetrations through rated fire barriers. (9) Consequences of Fire-The postulated fire assumes the loss of the function. Loss of the SGTS by an exposure fire is acceptable. Smoke from a fire will be removi by the normal HVAC System operating in its smoke removal mode. (10) Consequences of Fire Suppression-Suppression exdnguishes the fire. Refer to Section 3.4 " Water Level (Flood) Design", for the drain system. Analysis 9A4-292 19
Rev.o oestia careerooanneagrier2 ABWR ( . (11) Design Criteria Used for Protection Against Inadvenent Operadon, Careless Operadon or Rupture of the Suppression System: (a) Provision of raised supports for the equipment (b) Refer to Secdon 3.4 " Water Level (Flood) Design", for the drain system. (c) ANSI BSI.1 standpipe (rupmre unlikely) (12) Fire Containment or Inhibiting Met'aods Employed: , I (a) The funcdons are located in a separate fire-resisdve enclosure. i (b) The means of fire detection, suppression and alarming are provided and l i accessible. (13) Remarks-None. l SA.4.1.6.20 SGTS B Division 2 Room (Rm No. 641) (1) Fire Area-F4201 cpl. (2) Equipment See Table 9A.6 2 Safety-Related Provides Core Cooling Yes, D2 No (S) Radioactive Material Present-Filters within their housing may become contaminated with use. Releases up the stack could occur as a result of fire. However, the system is capable of being isolated in case of any fire, and burn itself out by cutdng the oxygen to the fire. e g , c e ,, c.l ey u;p J l (4) Qualifications of Fire Barriers-The walls common with th SG prp rd l hm =6mgr room (Rm 640), the SGTS A division S room (Rm 642), the ceiling, and a secdon of the floor common to fire area FS400 (Rm 543) below serve as fire barriers between adjacent fire areas and are of S h fire-resistive concrete construcdon. The remainder of the floor (not common to FS400), the wall common with SLC Area and corridor B room 622 are not rated as they l are internal to fire area F4201. A non-fire rated door provides access from corridor D (Rm 643). 9A4*293 Analysis 20
Rev.o ABWR osinacontrolDocunasner2 9A.4.1.6.34 Not Used 9A.4.1.6.35 FMCRD D/B Panet Room (Rm No. 681) (1) Fire Area-F7200 (2) Equipment See Table 9A.62 Safety-Related Provides Core CooEng Yes, D2 & DS No i l (3) Radioacdve Material Present-None that can be released as a result of fire. ; (4) Qualificadons of Fire Barriers-All walls, the ceiling, and the floor are of S h fire-resistive concrete constniction. Access to room 681 is from stair well (Rm 329) and elevator (Rm 328) via 3 h rated fire-resisdve doors. The room provides access to D/G B upper fan room (Rm 663) and to the upper !!"" i room (Rm 680) through S h rated fire-resistive doors. r he:: =6=ger =d f=k eiecke:c4 (5) Combustibles Present: c P 1. Fire Imading Total Heat of Combusdon (MJ) Cable Tray 2 727 MJ/m2 NCLL (727 MJ/m maximum average) applies (6) Detection Provided-Class A supenised POC in the room and manual alarm pull stations at 1.4-E.0,1.7-C.0. (7) Suppression Available: Type Location /Actuadon Standpipe and hose reel Col.1.4-E.0, and 1.7-C.0/ Manual ABC hand extinguishers Col.1.4-E.0, and 1.7-C.0/ Manual (8) Fire Protection Design Criteria Employed: (a) The function is located in a sepamte fire-resistive enclor c. (b) Fire detection and suppression capability is provided and accessible. (c) Fire stops are provided for cable tray and piping penetrations through rated fire barriers. 1 i 9A4-306 Analysis ( 21
O h.O o ABWR onsincanotDecamenmer2 (11) Design Criteria Used for Protection Against Inadvertent Operation, Careless Operadon or Rupture of the Suppression System: (a) location of the manual hose suppression system external to the room (b) Provision of raised supports for the equipment (c) Refer to Secdon 3.4 " Water Level (Flood) Design", for the drain system. (d) ANSI B31.1 standpipe (rupture unlikely) (12) Fire Containment or Inhibiting Methods Employed: (a) The funcdons are located in a separate fire-resistive enclosure. (b) The means of 6re detection, suppression and alarming are provided and accessible. (13) Remarks-None. l E3uQ mW 9A.4.1.6.bw"J: T....,, : ..J '. ; " .". .,M _. noom g i,,9,.co (Rm No. 640) C (" L (1) Fire Area-F6200 (2) Equipment See Table 9A.6-2 Safety-Related Provides Core Cooling No No (3) Radioacdve Material Present-None that can be released as a result of fire. (4) Qualifications of Fire Barriers-All walls and the floor are of S h fire-resisdve concrete construction. A section of the ceiling is common to the FMCRD room (Rm 681) above and is of S h fire-resistive concrete construcdon. The remainder of the ceiling is internal to fire area F6200 and is not fire rated. Access is provided from rooms 625 and 614 through S h fire-resistive doors. (5) Combusdbles Present Fire Le-Ag Total Heat of Combustion (MJ) 2 2 Cable Tray 727 MJ/m NCLL (727 MJ/m maximum average) applies ( s (6) Detection Provided-Class A supervised POC in the room and manual alarm i pull stadons at 1.0-B.2 and 1.4-D.7. 9A4 314 Analysis 22
1 I e Rev. 0
. ABWR Ska canotosannentmer2 (10) Consequences of Fire Suppression-Suppression extinguishes the fire. Refer to Section S.4 " Water Level (Flood) Design", for the drain system.
(11) Design Criteda Used for Protection Against Inadvertent Operation, Careless Operation or Rupture of the Suppression System: (a) Location of the manual hose suppression system external to the room (b) Provision of raised supports for the equipment (c) Refer to Section 3.4 " Water Level (Flood) Design", for the drain system. (d) ANSI B31.1 standpipe (rupmre unlikely) (12) Fire Containment or Inhibiting Methods Employed: , 1 (a) The functions are located in a separate fire-resistive enclosure. l (b) The means offir detection, suppression and alarmmg are provided and accessible. ! l I (13) Remarks-None. l
/
9A.4.1.6.47 U;;:: :""P M-d "-h: ;;-- --d 8-} Room (Rm No. 680) cpl
\
(1) Fire Area-F6400 Eicctrical (2) Equipment: See Table 9A.6-2 Safety-Related Provides Core Cooling No No (S) Radioactive Material Present-None. (4) Qualifications of Fire Barders-The walls in common with the FMCRD room (Rm 681), the SBGT fiher train room (Rm 642), corridor B room (Rm 643), ; l both exterior walls and the ceiling are of S h fire-resistive concrete l construction. The floor is common to room 640 below and is not fire rated. Access to room 680 is provided from the FMCRD t oom via a S h fire-resistive , I door and directly from room 640 below via a stairwell. l l Analysis 9A.4-320 23 l
1 Rev.O o ABWR ourne comretDecanoevrier2 l Table 9A.6-2 Fire Hazard Analysis Equipment Database Sorted by Room - Reactor Building (Continued) Lacetion Location Number Alphe System Room item k.act Elev. Coord. Desenption Drewmg h. No. NFL h Div. I Loost6on Coord. 2466 P54-F003B 2 23500 1.8 A.6 MO GLOBE VALVE 107E5128/0 640 :N A.6 MO GLOBE VALVE 107E5128/0 640 2467 P54-F012B 2 23500 1.8 A.6 MO GLOBE VALVE 107E5128/0 640 [ 2468 P54 F203 N 23500 1.8 1.8 A.6 PRESS IND SWITCH 107E5128/0 640 2489 P54-PIS001B 2 23500 2470 P54-PT004 N 23500 1.8 A.6 PRESS TRANSMITTER 107E5128/0 640 $ , A.5 H HEAT EX ANGER 55-812 2471 P63- 1A N 23 1.5 I A) A.5 HWHH EXCHANG 10Q255-8 640 247 P63-800 N 23500 1.2 (B) p CKUP H EXCH 1 5-812 640 _ d 2473 B002 23500 1.2 CAMS GAS CYL RACK B 107E5139/1 640 2474 H22-P044B' 2 23500 1.7 B.8 0.5 ,;.7 ; Fui.;7 A ;; ;Z;;;O ;^.
.) 2t?5 "O C001.'. N 2Z00 " .3 7, 2330G i.5 E7 m.;; FUiviF 6 iG oill- . Z fM70 % C0010 C.3 MULTIPLEXER 640 2477 H23-P029' N 23500 1.9 N 23500 1.9 C.5 MULTIPLEXER 640 2478 H23-P030' C.7 MULTIPLEXER 640 2479 H23-P031' N 23500 1.9 SOLENOID VALVE 107E6071/0 641 2480 D11-F053 N 23500 2.4 C.9 SOLENOID VALVE 107E6071/0 641 2481 D11-F054 N 23500 2.4 C.9 SBGTS ION CHAMBER 107E6071/0 641 2482 D11-RE002A N 23500 2.5 C.1 SBGTS lON CHAMBER 107E6071/0 641 2483 D11-RE002B N 23500 2.5 C.1 2484 H22-P043B 2 23500 2.2 C.5 SBGTINSTR RACK 10Q273-285 641 f DIFF PRESS SWITCH 107E5128/0 641 2485 P54-DPS003 N 23500 2.0 C.5 DRYER HEATER B 107E6046/1 641 2486 T22 B001B 2 23500 2.2 C.7 EXHAUST FAN B 107E604G/1 641 2487 T22 C001B 2 23500 2.2 C.1 COOUNG FAN B 107E6046/1 641 2488 T22-C002B 3 23500 22 C.7 C.6 PRENTR & FAN B - FLTR 107E6046/1 641 2489 T22-C003B' 2 23500 2.2 AFTRHTR & FAN B - FLTR 107E6046/1 641 2490 T22-C004B* 2 23500 2.2 C.6 PRE HEPA FILTER 8 107E6046/1 641 2491 T22-D003B 2 23500 2.2 C.6 POST HEPA FILTER B 107E6046/1 641 2492 T22-D004B 2 23500 2.2 C.2 PRE FILTER TRAIN 107E6046/1 641 2493 T22-DOO2B' 2 23500 2.2 C.7 DIFF PRESS INDICATOR 107E6046/1 641 2494 T22-DP1003B 2 23500 2.2 C.7 OfFF PRESS INDICATOR 107E6046/1 641 2495 T22-DP1007B 2 23500 2.2 C.7 OfFF PRESS INDICATOR 107E6046/1 641 2496 T22-DPl008B 2 23500 2.2 C.6 DIFF PRESS INDICATOR 107E6046/1 641 2497 T22-DPl0128 2 23500 2.2 C.6 DIFF PRESS INDICATOR 107E6046/1 641 2498 T22-DP1017B 2 23500 2.2 C.2 Fire Hazard Analysis Database 9A.6-82 24
Insert "B" for Table 9A.6-2, Page 9A.6-82 Renlacement of Electrical Equipment for IIWII Eauipmment .
-l 2471 R23 P/C ENI10A N1 23500 1.5 A.5 P/C ENI10A - LO VOLT SWTGR 107E5072/0 640 i 2472 R23 P/C ENI10B N2 23500 1.2 A.5 P/C EN]10B - LO VOLT SWTGR 107E5072/0 640 2473 R23 P/C EN110C N3 23500 1.2 A.2 P/C EN110C - LO VOLT SWTGR 107E5072/0 640 1
2475 R24 MCC ENI10A N1 23500 1.3 B.5 MCC ENI10A - R/B 107E5072/0 640 2475a R24 MCC EN110B N2 23500 1.3 B.6 MCC EN11OB - R/B 107E5072/0 640 2476 R24 MCC ENJ0C N3 23500 1.3 B.7 MCC ENI10C - R/B - 107E5072/0 640 i bD i b hr m bR' - i U 09 D V% h
Rev.O
; . ABWR osion conentoocanmattrar2 Table SA.6-9. Fire Hazard Analysis Equipment Database Sorted by Room - Reactor Building (Continued)
Locomon Laestion Nurnbar Alpha System Room leens Elect Elev. Coont Desenption Drawing No. i No. IdeL No Div. Looemon Coord. D.9 SO VALVE 107E5139/1 669 2674 D23-F197A 1 26000 5.3 D.9 D23, CAMS RACK A 107E5139/1 659 2675 H22-P053A* 1 26000 5.3 D.7 D23, CAMS CAUS RACK A 107E5139/1 659 2676 H22-P054A' 1 26000 5.2 D.7 CAMS (A) ROOM HVH 107E51894 659 2677 U41-D113 1 27200 5.3 1.4 E.8 DG(B)HVAC SUPP FAN 8 107E51894 663 2678 U41-C204B 2 27600 1.2 E.8 DG(B) HVAC SUPP FAN F 107E51694 663 2679 U41-C204F 2 27600 E.8 TEMP ELEMENT 107E5189/0 663 2680 U41.TE056 2 27600 1.4 F.3 TCV;DG B RM CLG 107E51824 663 2681 P25-F022B 2 27600 1.2 E.8 DG(C) HVAC SUPP FAN C 107E51894 673 2682 U41-C207C 3 27600 6.8 E.8 DG(C) HVAC SUPP FAN G 107E51894 673 2683 U41-C207G 3 27600 6.5 E.8 TEMP ELEMENT 107E51894 673 2684 U41-TE060 3 27600 6.7 F.3 TCV: DG C RM CLG 107E51824 673 2685 P25-F022C 3 27600 6.7 A TEMP NTROL V 1002 2 600 g ~2686 -F010 N 27600 .5 P CONTRO ALVE 1 55-812 A.5 l 2 P63 27 1.5 880 100255-81 N, 688 -M002 N 1.5 AS TEMPERAT E TRANS R pL pp . + P63- 005 27600 1.5 5 TE ELEMENT 1 55-812 680[ T'fd N 27 1.5 A5 MP ELE NT 10Q255-812 _w
-TE007
[ 2000 681 2691 H21-P009-01 N 27600 1.5 D.0 REMOTE COMM CABNET 103E1167 (C11) REMOTE COMM CABNET 103E1167 681 2692 H21-P009-03 N 27600 1.5 D.0 (C11) REMOTE COMM CABNET 103E1167 681 2693 H21-P009-05 N 27600 1.5 D.0 (C11) REMOTE COMM CABNET 103E1167 681 2694 H21-P009-07 N 27600 1.5 D.0 (C11) REMOTE COMM CABNET 103E1167 681 2695 H21-P009-09 N 27600 1.5 D.0 (C11) REMOTE COMM CABNET 103E1167 681 26b6 H21-P009-11 N 27600 1.5 D.0 (C11) REMOTE COMM CABNET 103E1167 681 2697 H21-P009-13 N 27600 1.5 D.0 (C11) REMOTE COMM CABNET 103E1167 681 2698 H21-P009-15 N 27600 1.5 D.0 (C11) REMOT5 COMM CABNET 103E1167 681 2699 H21-P009-17 N 27600 1.5 D.0 (C11) REMOTE COMM CABNET 103E1167 681 2700 H21-P009-19 N 27600 1.5 D.0 (C11) 9A689 Fire Hazard Analysis Database 26
Rev.0 . ABWR aineeconeercocamenttra2
'4 14.2.12.1.30 Not Used 14.2.12.1.31 Hot Water Heating System Prooperational Test (1) Purpose Verify the ability of the Hot Water Heating Sptem (HWHS) to provide hot water to the appropriate HVAC systems and the operation of HWH pump, heat exchanger, surge tank and chemical addition tank.
(2) Prerequisites The construction tests have been completed, and the SCG has reviewed the test procedure and approved the initiation of testing. Electrical power, SA Sptem, TCW System, Heat Steam System, "cr "dL g Oc~!hg T=r -c D Q.a. ., HVAC System, HNCW System and other required interfacing systems shall be available, as needed, to support the specified testing. Additionally, a temporary strainer shall be installed at the suction side of the HWH pump. (3) General Test Methods and Acceptance Criteria cP4' Performance shall be observed and recorded during a series ofindividual ' q~ component and integrated system tests.These tests shall demonstrate that the HWHS operates properly as specified in appropriate HWHS design speci6 cation and manufacturer's technical instruction manual through the following testing: (a) Proper operation ofinstrumentation and system controls in all combinations oflogic and instrument channel trip (b) Verification ofvarious component alarms, for correct system response to process variable, and provides alarms at the prescribed value (c) Proper operation of system valves, including open/ closure cycling and position indicator verification, if applicable (d) Proper operating conditions (flow, vibration, bearing temperature) of the HWH pumps during continuous pump run test (e) Acceptable pump NPSH under the most limiting design flow conditions. (f) Proper operating conditions and system performance capability during the following operation mode tests: (i) Plant normal operation mode (ii) Plant shutdown and inspection mode * (g) Proper pump motor start sequence and actuation of protecae devices 14.2-60 Specific Information to be includedin Final Safety Analysis Reports 27
aev. o , o ABWR nesea cenednocemenmer2 (- 1 (b) Proper operation ofinterlock functions, including operation of all components subject to interlockmg (e.g., HWHS pump trip on low surge tanklevel, per=: :::L el ofI"/"IS1--A-p L= - i-- em 7I and system water temperature control, etc.) ; C P 1. j (i) Proper operation of pentussive, prohibit, and bypass functions (j) Proper operation of system surge tank and chemical addition tank and their associated functions during system operation mode tests 14.2.12.1.32 HVAC Emergency Cooling Water System Prooperational Test (1) Purpose To verify the ability of the HVAC Emergency Cooling Water (HECW) System to supply the design quantities of chilled water at the specified temperatures , to the various cooling coils of the HVAC systems sening rooms and areas l contammg essential systems and equipment. (2) Prerequisites l
?
The construction tests have been successfully completed, and the SCG has reviewed the test procedure and approved the initiation vf testhig. Normal and aimhary electrical power, IA, MUWP, RCW, applicable HVAC Systs cooling coils, and other required system interfaces shall be availsble, as needed, to support the specified system testing. (3) General Test Methods and Acceptance Criteria Performance shall be observed and recorded during a series ofindividual component and integrated system tests.These tests shall demonstrate that the HECW System and its amihng equipment operate properly as specified % Subsections 9.2.13 and 7.3.1.1.9 and applicable HECW System design specification through the following testing-(a) Proper operation of instrumentation and system control functions incNding flow switch, surge tank level controller, and chilled water temperature controller (b) Verification of various component alarms, for correct alarm actuation and reset, alarm set value, alarm indication and operating logic (c) Proper operation of system motor-operated and air-operated valves, including operability and position indication verifications, if applicable (d) Proper operation of HECW pumps and motors during continuous run tests 14.2-61 l Specific Information :o be included in Final Safety Analysis Reports 28 l 1
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i 9 y ABM oasign ceneroiDocument
.j PROPOSED CHANGES l i
CHANGE PACKAGE NO. 2 Additional Chiller / Pump Set
t Rev.0 ABWR Desina ceae,nroecamentmers d Table 2.11.3a Reactor Building Cooling Water Cooling Loads Division A Hot Stam1by Normal (lo:4 of Operating AC Emergency Operating Mode / Components
- Conditior s Shutdown Power) (LOCA)
RCW/RSW Heat Exchangers in Service 2 3 3 3 SAFETY-REL.ATED Emergency Diesel Generator A t t *
- RHR Heat Exchanger A t * *
- Others (safety-related)f * * *
- NON-SAFETY-RELATED CUW Heat Exchanger * *
- t FPC Heat Exchanger A" * * *
- Inside Drywell * *
- t
,- Others (non-safety-related) * * * *
(
- Some of these cooling loads are serviced by only one or two RCW divisions.These components rnay be reassigned to other RCW divisions if redundancy and divisional alignment of supported and supporting systems is maintained and the design basis cooling capacity of the RCW divisions is assured.
t Equipment does not receive RCW in this mode.
- Equipment receives ftCWin this mode.
f HECW refrigeratohm coolers (RHR, RCIC, CAMS), RHR motor bearing and seal C f' 2-and CAMS cooler. { coolers, l
** Includes FPC room cooler.
i i i l Reactor Building Cooling Water System 2.1139 1
3 nov. o ABWR oesier conmutDecaneetmer1 (, 2.11.6 HVAC Emergency Cooling Water System Design Description The Heating Ventilating and Air Conditioning (HVAC) Emergency Cooling Water (HECW) System delivers chilled water to the: (1) Control Room Habitability Area HVAC System. (2) Control Building Safety Related Equipment Area HVAC System. l l l (3) lleactor Building HVAC System (safety-related elecuical equipment HVAC). Figures 2.11.6a and 2.11.6b show the basic system configuration and scope. The HECW System is classified as safety-related_except for the chemical addition tank and associated piping and valves. n DM% A, a r- re 6:y<nNe i uo;e U " " ' en
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am ~ .m3 The HECW System is manually initiated. j u m; & - .5 4k W ) Each HECW System refdgerator unit has a capacity of not less than 2.43 GJ/hyn cPA l l (, N* Divisions B and C, any refrigerator unit on standby automatically starts if any of the other refrigerator units in Divisiog B or C1e stopped.
.s l
Safety-related portions of the HECW System are ch==fied as Seismic Category L Figures ! 2.11.6a and 2.11.6b show the ASME Code class for the HECW System piping and components. The HECW System pumps and refrigerator units are located in the Control Building. ; i Each of the three HECW System divisions is powered from the respective Class IE l l -- divisions as shown on Figures 2.11.6a and 2.11.6b;1n the HECW System, independence t is provided between Cass IE divisions, and also between Qass IE divisions and non-Class IE equipment. Except for the connections to the chemical addition tanks, each mechanical division of the HECW System (Divisions A, B, C) is physically separated from the other divisions. The HECW System has the following main control room (MCR) disp *.avs and controls: (1) Control and status indications for the refrigerator units and pumps shown on Figure 2.11.6a and 2.11.6b. (2) Parameter displays for instruments shown on Figures 2.11.6a and 2.11.6b. 2.11.6-1 HVAC Emergency Cooling Water System 2
Rev.o
- , ABWR oesso acarentoocumerwners HECW 'HVAC HVAC 'HECW 3 ; 3 FROM SURGE TANK RCW REACTOR BUILDING HVAC 3y HECW 3 SYSTEM (SAFETY-RELATED --
ELECTRICAL EQUIPMENT HVAC)
~
I ~l CONTROL BUILDING SAFETY-RELATED EQUIPMENT l-l AREA HVACSYSTEM M 3 NNS CHEMICAL 8 NNS 3 4 C-- ADDITION TANK
-- - - ----4 - U N REFRIGERATOR 3 HECW
~ h RCW {
NV NOTES: h' -
- 1. DIVISION A IS POWERED FROM CLASS 1E. DIVISION 1. .
l REFRIGERATOR - 3 HECW h RCW CPA
% _- i Figure 2.11.6a HVAC Emergency Cooling Water System (HECW-A) hvAC Emergency Cooling Water System 2116-3 3
1
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[ Totde 2.11.6 HVAC Emergency CooNng Water System g ' inspections, Tests, Analyses and Acceptance Criteria h Design Commitment inspections, Tests, Analyses Acceptance Criteria 4 1. The basic configuration for the HECW 1. Visualinspections of the as-built system 1. The as-built configuration of the HECW configuration will be conducted. System is in accordance with {y System is shown on Figures 2.11.6a and 2.11.6b. Figures 2.11.6a and 2.11.6b. u
- 2. A hydrostatic testwill be conducted on 2. The results of the hydrostatic test of the g 2. The ASME Code components of the those Code components of the HECW ASME Code components of the HECW a HECW System retain their integrity under '
m internal pressures that will be System required to be hydrostatically System conform with the requirements in tested by the ASME Code. the ASME Code, Section 111. experienced during service.
- 3. Each HEWC System refrigerator unit has e 3. Type tests will be conducted on an as- 3. Each HEWC System refrigerator unit has a capacity of not less than 2.43 GJ/h. built HECW System refrigerator units at a capacity of not less than 2.43 GJ/h.
test facility. Min Divisions B and C, any refrigerator unit 4. Tests will be conducted on each as-built in Divisions B and C, the refrigerator unit on standby automatically starts upon ; on standby automatically starts if any of HECW System refrigerator unit in receipt of a simulated signal indicating = the other refrigerator units in Divisions B visionslB and C, using simulated signals or C age stopped. Indicating another refrigerator unit is at he othe: tafrigerator units in k stopped. Divisions B or C stopped. ( c3 f
- 5. Each of the three HECW System divisions 5.
is powered from the respective Class 1E
- 5. b '5
- a. The test signal exists only in the Class
- a. Tests will be performed on the HECW divisions as shown on Figures 2.11.6a and System by providing a test signalin 1E division under test in the HECW nly ne ass 1 si n at a time. System.
r depe e e s pr vided between Clar 1E divisions, and between Class 1E b. Inspections of the as-built Class 1E b. In the HECW System, physical . divisions and non-Class 1E equipment. divisions in the HECW System will be separation or electrical isolation exists , performed. between Class 1E divisions. Physical
% h De< s: on A, ne vt f, ej er.For separation or electrical isolation exists
- und en Dand6 aub m kcm3 between these Class 1E divisions and p non-Class 1E equipment. g
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% 4 o mel Cal 4 t a Of 5 ypm re w fe 04' a s P
- % A;p A A 4:p trJec.{aj -.
yw M o n~<f G er o%c pMV (5 A h f f' t si
Rev.0 ABWR Desina coneerDecamenersea Table 3.9-8 Inservice Testing Safety-Related Pumps and Valves1 (Continued) Safety Test Test Class Param Freq. Tier 2 Fig. No. Oty Description (h)(1) (a) (b) (f) (g) System Pumps C41-C001 2 Standby Liquid Control System Pump 2 Pd,Vd, 3 mo 9.3-1 Q E11-C001 3 Residual Heat Removal System Pump 2 Pd, Pi, 3 rno 5.4-10 Q, Vv (Sh. 3, 4, 6) E11-C002 3 Residual Heat Removal System fill 2 Pd,Pi, E10 5.4-10 pump (11) Vv (Sh. 3, 4, 6) E22-C001 2 High Pressure Core Flooder pump 2 Pd,Pi, 3 mo 6.3-7(Sh. 2) Q,Vv E51-C001 1 Reactor Core isolation Cooling pump 2 N,Pd.Pi 3 mo 5.4-8(Sh.1) Q,Vv P21-C001 6 Reactor Building Cooling Water pump 3 Pd, Pi, E10 9.2-1 Q, Vv (Sh.1,4,7) P25-C001 HVAC Emergency Cooling Water 3 Pd, Pi, E10 9.2-3 System pump Q, Vv (Sh.1,2, 3) P41-C001 6 Reactor Service Water System pump 3 Pd, Pi, E10 9.2-7 Q, Vv (Sh.1,2,3) Y52-C001 6 Standby D/G Fuel OilTransfer Pump 3 Pd, Pi, 3 mo 9.5-6 Q, Vv 1 This table responds to NRC Questions 210.47,210.48 and 210.49 regarding provisions for inservice testing of safety-related pumps and valves within the scope of the ABWR Standard Plant in accordance with the ASME Code.The information is presented
' separately for each system for the MPL number.
I l l I CPA f MechanicalSystems and Components 3.9-98 5
Rev.0 ABWR oneine coneetoncemenerne2 I Table 3.9-8 Inservice Testing Safety-Related Pumps and Valves (Continued) Safety Code Valve Test Test f b Class Cat. Func Para (d) (e) Freq (f) Ver 2 Fig.(g) No. Oty pleson'ption (a) (c) F025 $ Cooling water supply line to 3 B A S E2 9.2-1 HECW refrigerator PCV sh. 2.5,8 5 Cooling water supply line to 3 B P E1 9.2-1 1 F026 HECW refrigerator maintenance sh. 2,5,8 i 6 vgive l [ Cooling water line to HECW 3 B P E1 9.2-1 F027 sh. 2,5,8 F028 [gefrigerator bypass Cooling water retum line line from 3 B P E1 9.2-1 , sh. 2,5,8 HECW refrigerator f 2 Cooling water supply line to FPC 3 B P E1 9.2-1 F029 sh. 2,5 Hx yg 2 Cooling water retum line from FPC 3 B P E1 9.2-1 ; F030 sh. 2,5 Hx 2 Cooling water supply line to FPC 3 B P E1 9.2-1 F031 sh. 2,5 ' pump room air conditioner 2 Cooling water retum line from FPC 3 B P E1 9.2-1 ; F032
' sh. 2,5 l pump room air conditioner 2 Cooling water line to PCV 3 B P E1 9.2-1 F033 sh. 2,5 Atmospheric Monitoring System cir l 2 Retum line from PCV Atmospheric 3 B P E1 9.2-1 F034 sh. 2,5 Monitoring System clr 2 Cooling water supplyline to SGTS 3 B P E1 9.2-1 F035 sh. 2,5 room air conditioner l
2 Cooling water retum line from 3 B P E1 9.2-1 l F036 sh.2,5 SGTS room air conditioner 2 Cooling water supply line to FCS 3 B P E1 9.2-1 F037
' sh. 2,5 l l room air conditioner 2 Cooling water retum line from 3 B P E1 9.2-1 F038
, sh. 2,5 1 FCS room air conditioner 3 Cooling water supply line to RHR 3 B P E1 9.2-1 F039 sh. 2,5,8 equipment room air conditioner 3 Cooling water retum line from 3 B P E1 9.2-1 F040 sh. 2,5,8 RHR equipment room air conditioner 3 Cooling water supply line to RHR 3 B P E1 9.2-1 F041 sh. 2,5,8 pump motor l 3.9-123 l Mechanical Systems and Components 6
i Rev. 0
, ABWR Denine CeneelD=42 i /
i s Table 3.9-8 Inservice Testing Safety-Related Pumps and Valves (Continued) l Safety Code Valve Test Test Class Cat. Func Para Freq lier 2 No. Oty Description (a) (c) (d) (e) (f) Fig.(g) F719 3 Cooling water line to DG 3 8 P E1 9.2-1 instrument line sh. 2,5,8 F720 3 Retum water line from DG 3 B P E1 9.2-1 instrument line sh. 2,5,8 F721 3 Cooling water supply line to non- 3 B P E1 9.2 1 essential coolers FT instrument sh. 2,5,8 root valve F722 3 Cooling water supply line to non- 3 8 P E1 9.2-1 essential coolers FT instrument sh.2,5,8 root valve P24 HVAC Normal Cooling Water System Valves F053 1 HNCW supply line outboard 2 A I,A L,P RO 9.2-2 isolation valve S 3mo F054 1 HNCW supply line inboard 2 A, C 1,A L,S RO 9.2-2 isolation check valve (h1)
! F141 1 HNCW retum inboard isolation 2 A 1,A L.P,S RO 9.2-2 f2 valve (h1) l F142 1 HNCW retum outboard isolation 2 A I,A L,P RO 9.2-2
( S 3mo valge P25 HVAC E gency Cooling Water System Valves F001 5 Pump discharge line check valve 3 C P S E2 9.2-3 sh.1,2,3 (o F002 Pump discharge line maintenance 3 B P E1 9.2-3 l ! valve sh.1,2,3 F003 [ efrigerator outlet line 3 B P E1 9.2-3 maintenance valve sh.1,2,3 l F004 2 Maintenance valve at HECW 3 B P E1 9.2-3 f sh.1,2,3 l supply to MCR cooler TCV F005 2 HECW supply to MCR cooler 3 B A S E2 9.2-3 Temperature Control Valve (TCV) sh.1,2,3 l l F006 2 Maintenance valve at HECW 3 B P E1 9.2-3 supply to MCR cooler TCV sh.1,2,3 F007 6 Maintenance valve at HECW 3 B P E1 9.2-3 supply to MCR cooler sh.1,2,3 F008 6 Maintenance valve at HECW 3 B P E1 9.2-3 l retum from MCR cooler sh.1,2,3 ] I 3.9-127 MechanicalSystems and Components 7 , l
nev. o
, ABWR Danine caneetoocammtmer1 e
Table 3.9-8 Inservice Testing Safety-Related Pumps and Valves (Continued) Safety Code Valve Test Test Class Cat. Func Para Freq Tw 2 No. Oty Description (a) (c) (d) (e) (f) Fig.(g) F009 Pump suction line maintenance 3 B P E1 9.2-3 sh.1,2,3 6 valve F010 2 TCV bypass at HECW discharge to 3 B P E1 9.2-3 CP2 MCR cooler sh.1,2,3 F011 3 Pump suction line/ discharge line 3 B P E1 9.2-3 PCV maintenance valve sh.1,2,3 F012 3 Pump suction line/ discharge line 3 B A S E2 9.2-3 PCV sh.1,2,3 F013 3 Pump suction line/ discharge line 3 B P E1 9.2-3 PCV maintenance valve sh.1,2,3 F014 3 Pump suction line/ discharge line 3 B P E1 9.2-3 PCV bypass line sh.1,2,3 F015 3 Maintenance valve at HECW 3 B P E1 9.2-3 supply to C/B Essential Electrical sh.1,2,3 Equipment Room Cooler TCV F016 3 HECW supply to C/B Essential 3 B A 6 E2 9.2-3 Electrical Equipment Roora cooler sh.1,2,3 TCV F017 3 Maintenance valve at HECW 3 B P E1 9.2-3 l supply to C/B Essential Electrical sh.1,2,3 j l Equipment Room Cooler TCV F018 6 HECW supply to C/B Essential 3 B P E1 9.2-3 Electrical Equipment Room cooler sh.1,2,3 maintenance valve F019 6 Maintenance valve at HECW 3 B P E1 9.2-3 retum from C/B EssentialElectrical sh.1,2,3 i Equipment Room Cooler F020 3 TCV bypass valve at HECW supply 3 B P E1 9.2-3 to C/B Essential Electrical sh.1,2,3 Equipment Room cooler F021 3 Maintenance valve at HECW 3 B P E1 9.2-3 l supply to DG zone cooler TCV sh.1,2,3 F022 3 HECW supply to DG zone cooler 3 B A S E2 9.2-3 TCV sh.1,2,3 F023 3 Maintenance valve at HECW 3 B P E1 9.2-3 supply to DG zone cooler TCV sh.1,2,3 F024 6 Maintenance valve at HECW 3 B P E1 9.2-3 supply to DG zone cooler sh.1,2,3 3.9 128 MechanicalSystems and Components 8 l
O Mev. 0
, ABWR onser coneetneceameroer2 i
Table 3.9-8 Inservice Testing Safety-Related Pumps and Valves (Continued) Safety Code Valve Test Test Class Cat. Func Para Freq Tier 2 No. Oty Description (a) (c) (d) (e) (f) Fig.(g! F025 6 Maintenance valve at HECW 3 B P E1 9.2-3 return from DG zone cooler sh.1,2,3 F026 3 TCV bypass valve at HECW supply 3 B P E1 9.2-3 to DG zone cooler sh.1,2,3 F030 3 Chemical addition tank retum 3 B P E1 9.2-3 valve from HECW sh.1,2,3 F031 3 Chemical addition tank feed valve 3 B P E1 9.2-3 to HECW sh.1,2,3 F050 2 Make-up Water Purified (MUWP) 3 C A S E2 9.2-3 (3line to pump suction check valve sh.1,2,3 l F070 h Pump discharge line drain valve 3 B P E1 9.2-3 l sh.1,2,3 l g, F400 h Pump drain line valve 3 B P E1 9.2-3 sh.1,2,3 pq
< F401 [f, Pump bearing cooling water needie vaive 3 B P E1 9.2-3 sh.1,2,3 F402 3 Refrigerator outlet line sample line 3 B P E1 9.2-3 yalve sh.1,2,3 F700 [P mp discharge line pressure 3 B P E1 9.2-3 sh.1,2,3 F701 @ FE pstrument line root valve P25-FE003 upstream 3 B P E1 9.2-3 instrument line root valve sh.1,2,3 F702 E P2E ! E003 downstream 3 B P E1 9.2-3 1
instrument line root valve sh.1,2,3 F703 I ump suction pressure instrument 3 B P E1 9.2-3 sh.1,2,3 line root valve 6 Pump suction / discharge line Ap 3 B P E1 9.2-3 F704 sh.1,2,3 instrument line root valve i 39429 Mechanical Systems and Components 9
. _ . . _ . . . _ . _ . . . . _ _ ___ _ .__- ..._. .~ _ _ _ _ .__ _ _. _ _ . .
s l nov, o ,
, ABWR asair,ceaueransansevner2 k
(k) Parts of System Not Required for Safety The non-safety-related portions of the RCW System include the annunciators and the computer. Other instrumentation considered non-safety-related are those indicators that am provided for operator l-information, but are not essential to correct operator action. 7.3.1.1.8 Essential HVAC Systemo-instrumentation and Controis i l See Subsections 9.4.1 and 9.4.5. l 13.1.1.9 HVAC Emergency Cooling Water Syste.T. : . amentation and Corr 1rol j l ( (1) System Identification l l l The HVAC Emergency Cooling Water System (HECW) supplies ! deminerahzed chilled water to the cooling coils of the control building safety- ! related electrical equipment rooms and main control room coolers, and the diesel generator zone air conditioning systems. The system is composed of three divisions, each cf; ; ' .i : containing twoMirigerators and chilled water pumps =d 2: 1.dr :: ' ;;; .d.;;;.cx sd -' '":d " ( .- . e
- 7. .
The Control Building Chilled Water System instrumentation and controls are shown on P&ID Figure 9.2 3 and the corresponding logic on Figure 7.54. (2) Support Systems (Power Source) l The instrumentation and controls of the HECW System are supplied with i I 120 VAC and 125 VDC electdc power from Division I,an[pwer buses.
^
% nA %C (S) EquipmentDesign 3
+ b .-e e The HECW System consists of Mecgijly (and electrically) ,eparate systems-DivisionfA r? D:. 2[The system is des {tggej to ov}i e chilled
@It'EO36["?'$ ??bS"%'A"$ W-3ll?ki 5 $h w l dMMnlEPWe'd NMj4WG Wio6A 5GetWc-1 E.Cy'S"'7~AIIK'c'~ ~s s TJ A 5 i The HECW System is designed to operate during both accident conditions' l
and normal plant operation and during all modes ofoperation for the C tre! + 1 ? E.2f:g =d fr:1 g .:.:2 :::: cooling system (._ t, 4e r vu. Each division of the HECW System consists of a+urgeaanV%dYabr pum . and refrigerator uni each refdgerator unit includes the condenser,
~*
7.3-67 l Engineered $sfety Feature Systems. Instrumentation and Control M 10 j i
i % Rev.0
' ABWR Design ComrolDecanenVTier2 i
1 evaporator, centrifugal compressor, refrigerant pipings and package chiller controls. The system condenser is cooled by the ROV System. Lack of flow of Reactor Building cooling water to the refrigerant condenser automatically stops the refrigerator. Supply flow is controlled by the condensing pressure of the refrigerant. A flow switch provided at the chilled water line shuts down the refrigerator and chilled water pump indication of low flowin the chilled waterline. (a) Initiating Circuits The HEQV System operation is initiated automaticallywhen the controls in the main contr.ol r om are set for automatic operation and any of the HVAC systems,l'c::g((iU$c
- Ccn:re! "dding er dic.;ci
; genenter rer are started. The HEOV System can also be staned manually from the main control room.
(b) Logic and Sequencing to b;,;se,,, A un
'Ihe standby sp:1- om (refrigerator and chillegter pump) is automaticall mu i s.o m d .nitiated when
. ~s c., e mtheum.,
operating
<n 4%n svaem is shut down. n iM H' M ******
- q o '5 ,m. e4 Me ofeea h. esuett5 u ,mM. m ab (c) Bypass and Interlocks 2 ti,es., ec c. .3 4+-pp-d.
Low and high surge tank level switches actuate the demineralized water makeup or supply valves. Low-low or high-high surge tank level initiates an alarm in the control room to indicate a leak or a failure in the level controlloop. How switches pro ided on the chilled water line are interlocked to , automatically shut down the refrigerator in the event oflow flow in the l chilled water line. A common trouble alarm for each refrigerator unit is annunciated in the control room upon detection ofany refrigerator unit alarm or trip. A running signal from each ROV pump in each di ision is interlocked to trip the refrigerators if at least one ROV pump is not operating. s.> k a e on &^ ^ % , ja,e,;s,,t Each refrigerator unit,is interlocked to automatically start,i,: cir r.efd r~-hen & eper&grefdgen crE:hu:d;=.foren; r;nn i n cb . The running refrigerator is interlocked to trip on abnormal operating
- conditions such as lack of flow of chilled water and chiller package trouble.
-{-
(d) Redundancy and Diversity g 7M8 Engineered Safety Feature Systems, Instrumentation and Control 11 1 I
3 0 Rev. 0
, ABGVit cesena convoinecmaentmerz goon H o L:\*k:l3,3 An The Control "% Chilled Water System is divided into two
, completely independent and functionally redundant systems.s l S Ch bn I .nd D6.eu II. Physical and electrical separation is ( f 2. l maintained between the two redundant systems. l (e) Actuated Desices One refrigerator and chilled water pump in each division is running at all times during all modes of plant operation. l l The chilled water pumps and refrigerator units are started automatically l or by remote manual switch. Status lights in the control room are also l provided for this equipment. l I High and low surge tank level switches actuate the opening and closmg j of the demineralized water makeup valve and high-high and low-low : l tank level switches annunciate an alarm in the control room. l The refrigerator capacityis controlled to maintain the chilled water temperature at the refrigerator outlet constant. This is done by adjusting ! l the suction valve and hot-gas bypass within the refrigerator. (f) Sepnation ! The instrumentation, controls, and sensors of car a operating division l have sufficient physical and electrical separation to prevent emironmental, electrical, or physical accident consequences from inhibiting the systems from performing each protective action. Physical l separation is maintained by use of separate cabinets and racks for cach
- division, and by housing redundant chiller equipment in separate l cubicles.
Elecuical separation is maintained by separate independent sensors and
- circuitry.
1 1 (g) Testability Manualinitiation of the HECW System is possible from the control room. Redundant standby components can be periodically tested, j manually, to ensure system reliability while the other system is operating. i
- Surge tank operation can be checked byvarying the tank level and 3
observing the level at which the demineralized water makeup valve starts to open and close and when the level alarm annunciates. Automatic initiation of the standby system can be tested by simulating the trip action of the operating refrigerator system. Engineered Safety Feature Systems, Instrumentation and Control 7.3-59 12 i
Rev.o l , ABWR oesira controsDocumentmer2 1 In accordance with the Standard Review Plan for Section 7.3, and with Table 7.1-2, only BTPs 21 and 22 are considered applicable for the HVAC System. They are addressed as follows-I
. (a) BTP ICSB 21
- Guidance for Application for Regulatory Guide 1.47" l The ABWR design is a single unit. Therefore, item B-2 of the BTP is not applicable. Otherwise, the HVAC System is in full compliance with this l BTP.
l i i (b) BTP ICSB 22 " Guidance for Application of Regulatory Guide 1.22" All actuated equipment within the HVAC System can be fully tested dunng reactor operation. (5) TMI Action Plan Requirements (TMI) I 1 i In accordance with the Standard Review Plan for Section 7.3, and with 1 1 Table 7.1-2, there are no TMI action plan requirements applicable to the HVAC System. 7.32.9 HVAC Emergency Cooling Water System-instrumentation and Control 7.3.2.9.1 Conformance to General Functional Requirements ! v e er The HVAC Emergency CoolingkHECW) Sysjem pgo s chilled water to the control ! building safety-related,c!:=icckquipment recr cc_.e-:s and to the cec!!ng p;m of 9M "a control roo ce!!ng :cih =d it dic c! g=:rnor cclIng ccil. It is designed j l t to function under all rating, emergency and accident conditions. ! m 4 s: UQ Ann W c. M $%chs t YW%ac~l 1 . 7.3.2.9.2 Specific Regulatory Requ.irements Conformance 6 9 m . n t. h t E 'w ggg g g c, s p % , ! f u scw 3 5 9-l Table 7.1-2 identifies thep'V.'.C ECCS1E'nd the associated codes and standards applied i in accordance with the Standard Review Plan. The following analysis lists the applicable l criteria in order of the listing on the table, and discusses the degree of conformance each. Any exceptions or clarifications are so noted. (- f 2. l (1) 10CFR50.55a (IEEE-279) we. -J
)
I The HVAC Emergency Cooling Water (HECW) System has t independent elecuical divisions and is redundantly designed so that failure of any single electrical component will not interfere with the required safety action of the system. ! The HECW System is manually actuated, but is designed to run continuously during reactor operation. Should a loss of station power or a LOCA event occur, the system power sources will automatically switch over to the l Engineered Safety Feature Systems. Instrumentation and Control 7.3-91 13 l
~
Rev.0
, ABWR ouiun canreioocamenvrier2 .
l emergency diesels. Thus, continuous operation is assured for all plant i condidons. I 1 All components used for the safety functions are qualified for the emironments in which they are located (Secdons 3.10 and 3.11). I A ,'S a s a C 1 The HECW System utilizes mechanical Divisions A(&-B corresponding with electrical Divisions respectively. Elecuical separation is maintained between the redund t divisions. L,1C
- M 5 >
The HECW System is designed to meet all applicable requirements ofIEEE-l 279. Detailed system design descriptions are given in Subsection 7.3.1.1.9 and ! in Chapter 9. (2) General Design Criteria (GDC) In accordance with the Standard Review Plan for Section 7.3, and with Table 7.1-2, the following GDCs are addressed for the HVAC System: (a) Criteria: GDCs 2,4,13,19,20,21,22,23,24,29, and 44. (b) Conformance: The HECW System is in compliance as a whole, or in part as applicable, with all GDCs identified in (a), as discussed in Subsection 3.1.2. l (3) Regulatory Guides (RGs) In accordance with the Standard Review Plan for Section 7.3, and with Table 7.1-2, the following RGs are addressed for the HECW System: l (a) RG 1.22 " Periodic Tesdng of Protection System Actuation Functions" (b) RG 1.47 " Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems" l (c) RG 1.53 " Application of the Single-Failure Criterion to Nuciear Power l Protection Systems" 1 (d) RG 1.62 " Manual Initiation of Protective Acdons" (e) RG 1.75 " Physical Independence of Electric Systems" l (f) RG 3.118 " Periodic Tesdng of Electric Power and Protecdon Systems"
- The HECW System conforms with all the above listed RGs, assuming the same
, interpretations and clarificadons identified in Subsections 7.3.2.1.2 and 7.1.2.10. 7.3 92 Engineered Safety Feature 5ystems. Instrumentation and Control l I 14
l i $ nov. o j l , ABWR oneion coneelDocumensmerz l 1 l .' (6) Design features to preclude the adverse effects of water hammer are in . accordance with the SRP section addressing the resolution of USI A-1 l discussed in NUREG.0927. i These features shallinclude: 1 ! (a) An elevated surge tank to keep the system filled. l (b) Vents provided at all high points in the system. (c) After any system drainage, venting is assured by personnel training and procedures. l (d) System vahrs are slow acting. 1' (7) The HECW System shall be protected from failures of high and medium energy lines as discussed in Section S.6. 1 j l (8) The design operation of the HECW compressors will take into account power ' or operational perturbations which could resultin a) frequent immediate or l elongated restarts, b) in unacceptable compressor coolant and lubrication oil l ! I' interactions, and c) compressor coolant leaks or releases. (9) The system piping design will take into account unacceptable nil-ductility- ' temperature conditions associated with normal and transient operation. l CP A 1 9.2.13.2 System Description ,s A b .~ 4 l The HECW System consists of subsystems in three divisions. Divisiorq' u y re;;:rterud r -- P =d N.i= B and C have two refrigerator l ! instrumentation and distribution piping and valves to corresponding cooling coils. A chemical addition tank is shared by all HECW dhisions. Each HECW dhision shares a surge tank with the corresponding division of the RCW System. The refrigerator capacity is designed to cool the Reactor Building safety-related electrical equipment HVAC Systems and Control Building safety-related equipment area HVAC Systems. The system is shown in Figure 9.2-3. The refrigerators are located in the Control Building as shown in Figures 1.2-20 and 1.2-21. Each refrigerator unit consists of a evaporator, a compressor, refrigerant, piping, and package chiller controls. This system shares the RCW surge tanks which are in the Reactor Building (Figure 1.2-12). Equipment is listed in Table 9.2-8. Each cooling coil is controlled by a room thermostat. Alternately, flow may be controlled by a temperature control valve. Condenser cooling is from the corresponding division of the RCW System. Piping and valves for the HECW System, as well as the cooling water lines from the RCW System, designed entirely to ASME Code, Section III, Class 3, Quality Group C, Quality i i Water Systems 9.2-31 i I 15 l l
. .- - .- . . .. - - ~ _ - - -- .- . . - . - ~-
s i nov. o .
,. ASWR aserse casestassensseners l
! Assurance B requirements. The extent of this c1===Hcation is up to and includmg : l drainage block valves. There are no primary or secondary containment penetrations ! within the system. The HECW System is not P~I ot contain radioactivity. ! i l High temperature of the remrned cooling water c=neen the standby refrigerator unit to start automatically Makeup wateris supphed from the MUWP System, at the surge tank. Each surEe tank has the capacity to replace system water losses for more than 100 days ! l during an emergency. The only non-safety-relate n. portions of the HECW dmsions are i the chemical addition tank and the piping from the tank to the safety-related valves ! which isolate the safety-related portions of the system. l Also, see Subsection 9.2.17.1 for COL license information requirements.
.i 9.2.13.3 Safety Evaksation The HECW System is a Scumic Category I system, protected from floodmg and tornado miamiles. All components of the system are designed to be operable during a loss of l
normal power by connection to the ESF buses (Tables 8.3-1 and 8.5-2). Redundant components are provided to ensure that any e component failure does not g preclude system operation.M v_._2 d o.The system is designed to meet the requirements of Criterion 19 of 10CFR50. The refrigerators of each dmsion are in separate rooms. During a Station R1=riraut (SBO), the HECW refrigerators, pumps and instrumentadon ! will be powered by the AAC System which will become avadable in ten minutes. Provisions will be made to ensure prompt and reliable restart of the chiller units. COL license information requirements are provided in Subsection 9.2.17.1. The response to SBO is dim-d in Chapter 1, Appendix IC. Dunng the SBO, little heat will be generated in the areas cooled by HECW because only battery powered l equipment will be operating. These areas are the main control room, the Control Building essential electrical equipment rooms and the Reactor Building essential electrical equipment rooms. The HVAC fans in these areas are powered by Class IE ' buses. When AAC power becomes available, these fans will be pued and will start supplying outside air and exhausting any hot air from these areas. When chilled water becomes available, cooled air will be ' circulated in these areas to restore normal temperature. 1 If a LOPP event occurs, there are provisions for a stop signal to the HECW pumps to trip the breakers or for sequencing the HECW pumps back onto the emergency bus ; ! during the allotted time frame (load block 3), which is 15 seconds after the emergency buses are picked up by the diesel generators. Once the pumps are reconnected to the l
; emergency bus, they are prevented from cycling on and off until the remammg LOPP ~
- sequence loads are connected to the emergency bus. lf a LOCA follows a LOPP, there s.2.s2 watersystems 16 1
l
l l ' nev. o i
. ABWR nesseconeosoecamensmer2 l l , l
(. i l are prmisions for resetting the start timers and connecting the HECW pumps to the emergency busses at the proper time if they are not already connected when the LOCA i
*PPean.
I Power is provided to the HECW refrigerators thirty seconds after it is provided to the HECW pumps. The HECW refrigerators will then begin a programmed startup process. l I l The HECW system air operated valves will upon loss ofinstrument air or power assume i con 6gurations or positions that assure continued system cooling service. 9.2.13.4 Tests and Inspection Initial testing of the system includes performance testing of the refrigerators, pumps l i l and coils for conformance with design capacity water flows and heat transfer capabilities. An integrity test is performed on the system upon completion. l The HECW System is designed for periodic pressure and functional testing to assure: (1) the structural and leaktight integrity by visual inspection of the components; 1 (2) the operability and the performance of the active components of the system; I ad (3) the operability of the system as a whole. Local display devices are provided to indicate all vital parameters required in testing and inspections. Standby features are periodically tested by initiating the transfer sequence during normal operation. The refzigerators are tested in accordance with ASHRAE Standard 30. The pumps are tested in accordance with standards of the Hydraulic Institute. ASME Section VIII and TEMA C standards apply to the heat exchangers. The cooling coils are tested in l l accortlance with ASHRAE Standard 33. 9.2.13.5 instrumentation and Alarms A regulated supply of makeup water is provided to add purified water to the surge tanks by water level controls. The chilled water pumps are controlled from the main control panel. The standby refrigerator has an interlock which automatically starts the standby refrigerator and , j pump upon failure of the operating unit,inEiix.:" ad C. O., Cf1 ! The refrigerator units can be controlled individually from the main control room by a remote manual switch. Chilled water temperature is controlled by inlet guide vanes on I l tVater Systems 9.2-33 17
, i nev. o j
. ABWR onann connanecemenorm2
%s 1 s; ' . l I
Table 9.2-8 HECW System Component Description
- l HECW Chillers Type Centrifugal hermetic l Quantity 4:x X6 1
l Capacity (Refrigerator) - five- 2.51 GJ l 8 Chilled water pump flow - five 4t r 57 m /h Supply temperature 7'C l Condenser water flow -five A:x 128 m3/h Supply temperature (max.) 45'C Condenser Shell and tube Evaporator Shell and tube HECW Water Pumps l l Quantity [3 57 m /h each
]
! Type . Centrifugal, horizontal l
- 0:;!:!:n ". hn ;..; F;- .;; :;f: g.___: xx" Divisions B and C ve two pa<=11e l pump-refrigerator units. /\
j A, C oc k e.f I CP1 l l l l l l l l 4 i i d l . I WaterSystems 9.2-58
- -- - -18 -
l l i
I } Rev.0 l . ABWR Donine coneetDecamentrier2 l Table 9.2-10 HVAC Emergency Cooling Water System Active Failure Analysis l Failure of diesel generator to start or failure Loss of one refrigerator and pump in ; l Division B or C would not permit sending of all power to a single Class 1E power 1 system bus. chilled water to the Control Room l Habitability Area HVAC System from the affected division. The other HECW division would send chilled water to the Control Room Habitability Area HVAC System which would maintain adequate cooling. In --b e d l Division A, loss ofinther]the refrigeratorg j the pump,would result in loss of cooling water flow to Division A Control Building safety-related Equipment Area HVAC System and Reactor Building safety-related ! Electrical Equipment HVAC Syr. tem. Cooling . l l of Control Room Habitability Area HVAC g I System not affected. Failure of auto pump or refrigerator signal. Same analysis as above. Same analysis as above. - Failure of a single HECW refrigerator. J Failure of a single HECW pump. Same analysis as above. Failure of HECW pump and refrigerator Same analysis as above. l room cooling. Table 9.2-11 Turbine island Auxiliary Equipment The TCW System removes heat from the following components:
= HVAC normal cooling water chillers f
- Generator stator coolers, hydrogen coolers, seal oil coolers, exciter coo!ers and i breaker coolers
- Turbine lube coolers
. Mechanical vacuum pump coolers
! . Isophase bus coolers
+ Electro-hydraulic control coolers
. Reactor feed pump and auxiliary coolers
+ Standby reactor feed pump motor coolers
. Condensate pump motor coolers
- Heater drain pump motor coolers
/
WaterSystems 9.2-60 19
Rev.0 r , ABWR oneien coneetoecanenoner2 Table 9A.6-3 Fire Hazard Analysis Equipment Data Base - Sorted by Room - Control Building (Continued) LOCATION LOCATION NUMSER A&HA SYSTEM ROOM ITEM MPL ELECT ELEY. NO. COORD. DESCRIPTION DRAWING NO. NO. OfV. LOCATION COORD 6.70 J.2 HECW REFRIGERATOR F 107E5182/0 534 200 P25-D001G 3 12300 12300 5.70 J.6 DP XMTR(FLO CONTC/F) 107E5182/0 534 201 P25-DFT007C 3 6.90 J.2 TCV: MCR CLG 107E5182/0 534 202 P25-F005C 3 12300 12300 5.70 J.4 PCV:HECW UNITS C/F 107E5182/0 534 203 P25-F012C 3 12300 6.00 J.2 FLOWIND SWITCH C 107E5182/0 534 204 P25-FIS003C 3 6.70 J.2 FLOWIND SWITCH F 107E5182/0 534 205 P25-FIS003F 3 12300 6.00 J.2 TEMP ELEM (UNIT C/F) 107E5182/0 534 206 P25-TE005C 3 12300 6.20 J.1 MCR RECIRC SUPP FAN C 107E5189/0 534 207 U41 C623C 3 12300 6.20 J.1 MCR RECIRC SUPP FAN G 107E5189/0 534 208 (!41-C623G 3 12300 4.00 K.0 COMPUTER PANELS 591 209 H11-P001' N 12300 5.30 J.5 CHEMICAL FEED TANK 107E5182/0 503 210 P25-A002 N 12300 5.30 J.2 DP XMTR(FLO CONT 107E5182/0 503 211 P25-DFT007A 1 12300 5.30 J.2 TEMP ELEM (UNIT 107E5182/0 503 212 P25-TE005A 1 12300 213 P25-C001A 1 17150 5.30 J.4 HECW PUMP A 107E5182/9 612 cF2
- 5,30 1,$ MScw PUMP 'P to7E58sa/o & # 3-J.t SA P45 CoosD 1 8785D 10 612 5.30 J.4 HECW REFRIGERATOR A 214 P25-0001A 1 17150 M E cw AEF Rt G E 4 *ls dL D "7E5182/07tSit do es2.,
- 2i+A PAS DooO e 17850 5 30 f. 4 5.50 12 PCV:HECW UNIT Ag 107E5182/0 612 215 P25-F012A 1 17150 5.30 J2 FLOW IND SWITCH A 107E5182/0 612 216 P25-F1S003A 1 17100 7(68640 /ei A - XA pas. F t % +0D t J 15'D 5 30 3t 8~ L o* ' *# 5'*'%H D 5.20 K.5 EM ELEC(A)EXH FAN A 107E5189/0 613 217 U41-C605A 1 17150 K.6 EM ELEC(A) EXH FAN E 107E5189/0 613 218 U41 C605E 1 17150 5.20 5.20 K.6 MO VALVE 107E5189/0 613 219 U41.F105A 1 17150 K.5 MCR HVAC EXH FAN C 107E5189/0 614 220 U414622C 3 17150 5.70 5.70 K.6 MCR HVAC EXH FAN G 107E5189/0 614 221 U41.C622G 3 17150 5.70 K.5 DIFF PRESS INDICATOR 107E5189/0 614 222 U41-DP1106C 3 17150 5.70 K.5 DIFF PRESS INDICATOR 107E5189/0 614 223 U41-DPl107C 3 17150 5.70 K.5 DtFF PRESS INDICATOR 107E5189/0 614 224 U41-DPl108C 3 17150 5.70 K.5 DIFF PRESS INDICATOR 107E5189/0 614 225 U41-DP1109C 3 17150 5.70 K.5 MO VALVE 107E5189/0 614 226 U41-F009C 3 17150 5.70 K.6 MO VALVE 107E5189/0 614 227 U41 F009G 3 17150 5.70 K.5 MO VALVE 107E5189/0 614 228 U41-F010C 3 17150 5.70 K.6 MO VALVE 107E5189/0 614 229 U41-F010G 3 17150 5.70 K.S MO VALVE 107E5189/0 614 230 U41-F012C 3 17150 5.70 K.5 POSmON TRANSMITTER 107E5189/0 614 231 U41-POT 105C 3 17150 K.6 POSITION TRANSMITTER 107E5189/0 614 232 U41-POT 105G 3 17150 5.70 J.3 MCR COOUNG COIL 107E518910 615 233 U41-B601C 3 17150 6.80 Fire HazardAnalysis Database 20
1 Wof e : Secken 19% P<&t.;l;sk 22Assoonev.s ev,w~ % ,cs n.r p< r et m De b %,4 s ssa. ABWR aandardsanyAneksisneverr ! (8) Reactor vessels are operated in accordance with the limitations specified in NRC license technical specifications and no such requirements are imposed on non-nuclear vessels. Based on the above considerations, it is concluded that while it is not possible to quantify the probability of RPV failure with great precision, the failure probability of an RPV rupture for the ABWR plant is so low that its explicit inclusion in this analysis would not significantly impact the results. Furthennore, the RPV failure modes that are l mechanistically plausible would produce consequences similar to the higher pmbability LOCA events because of the leak-before-break phenomenon. 1
- 19D.3.1.4.2 Loss of Main Control Area Envelope HVAC l The HVAC emergency cooling water (HECW) System delivers chilled water to the l l control building safety-related equipment area cooling coils, reactor building safety- i related electrical equipment area cooling coils, and the main control area envelope served by the control room habitability area cooling coils during shutdown of the reactor, normal operating modes, and abnormal reactor condidons. The HECW System i t consists of three mechanically separated divisions, A, B, and C. Each HECW division I
provides cooling to the control building safety-related equipment area and the reactor building safety-related electrical equipment area in its division. Also, either division B 1 l or C can independently cool the main control area envelope. Power is supplied to e i division from independent Class IE sources. C F2. we parallel A E:ac A Jdivision " of HECW consists o pum hon uni instrumentation, l and distribution piping and valves to the cooling coils. DhE= "E* =d "C" sc AJia :
; :=ept i:t rez p=ll:1 p=p> :nd r::: re;; r&n ' = r:i System i
! configurations for each division are illustrated in Figure 19D.3-1,19D.S 2 an " SD.S-3. l l ane pu,4 a a raa.gera%r ue;+ %m ew: The HECW tem is capable of removing all heat loads with four of the units
"' ** Rx an l
running an one of the four pump and refrigerator units from divisions "B" and "C"in l standby. At any given time the division with two pumps and refrigeration units in operation provides cooling to the main control area envelope. The design philosophy ; l is that if one of the refrigerators or pumps fails in this division, the standby refrigerator I will aut amatically start and provide main control room area envelope cooling while the reactor building safety-related electrical equipment area ling requirements will continue to be met by the remaining refrigerator in the ected division. an ot % c n+c.i bu:t.t.g 4=fq .cd ha ciu % ,$ w. Cooling wate r for the HECW refrigerators is provided by the corresponding division of l the Reactor Building Cooling Water (RCW) System which in turn rejects heat through the Reactor Senice Water (RSW) System to the ultimate heat sink. Each disision of the RCW and RSW consists of two parallel trains interfacmg through three heat exchangers. g RCW and RSW system design capacities are such that one RCW train, one RSW train, . i 19D.3-6 Input Osts - Amendment 31 21
1
####" I S.3 tJa k e n 4.F ,f P.33. 19D. 3. &,
ABWR mennussehnyAnewnepar s i 1 RCW/HECW- A SURGE TANK O A D/G ZONE (A) COOLING COILS M (REACTOR BUlWING) l A ESSENTIAL ELECTRICAL EQUIPMENT ROOM (A) COOLING COILS (CONTROL BUILDING) 1I m fc.ez FE HECW i -- -- q' REFRIGERATOR i II i (CONTROL BUILDING) Adsl )O HECW PUMP u l (COB TROL BUILDING) RCW+ _ __ RCW FE
~~ -- e HECW 1 l
l , O; %- REFRIGERATOR (CONTROL BUILDING) i II i l O l HECW PUMP i (CONTROL BUILDING) RCW+ RCW l l Figure 19D.3-1 HECW Division A 19D.3-18 Input Data- Amendment 31 22 I
7
#3^* * **
- S _ n ,u e,,4 ,p 4 P. I@.3 -L ABWR saadentsehnydo rsisnepar 3
. o and DC buses at different voltage levels. These buses and the onsite emergency sources
, are arranged into three AC divisions, four DC divisions and four 120V AC uninterruptable power supply (UPS) divisions designed with a high degree of independency. Fault trees were developed for each bus supplying essential loads. These trees are linked to the various other safety system fault trees. Events common in different trees are designated with identical acronyms to insure proper common cause failure treatment when the electrical power fault trees are linked to the various system fault trees. The developed fault trees are presented in Figures 19D.69 through 19D.413. Failure rates used to quantify these fault trees are presented in Table 19D.6-5. 19D.6.4.2 Service Water Systems I Essential equipment in the reactor bt icung is cooled by the Reactor Building Cooling Water (RCW) System, which consists of three divisions. Each division is a closed cooling water loop which removes heat from the RHR heat exchangers, HVAC emergency cooling water system refrigerators, diesel generators, and other equipment. Heat is discharged through the RCW heat exchangers to the Reactor Service Water (RSW) System. Each RCW division has two 50% capacity motor driven pumps and three 33.5% capacity heat exchangers. i The RSW also consists of three divisions, each of which removes heat from its j corresponding RCW heat exchangers and releases it to the UHS. Each division has two 50% capacity motor driven pumps which send UHS cooling water through the RCW heat exchangers. During normal operation, one RCW and one RSW pump in each loop in each division and two RCW heat exchangers in each division are operating. Under these conditions, sufDcient cooling capacity is available to provide seal and motor bearing cooling water for the core cooling pumps. Also, sufHcient cooling capacity is available to remove heat from the RHR heat exchangers during LOCA if at least two loops are operated with all pumps and heat exchangers. j The operating and standby pumps and heat exchangers are interchanged monthly. During accident conditions, the standby pumps and heat exchangers are put into operation to provide additional cooling capacity. M.x The HVAC Emergen oling Water (HECW) System receives cooling from the RCW System throug frigerators. This system in turn provides cooling to the three reactor building safety-related electrical equipment areas, three control building safety-related equipment areas, as well as the main control area envelope served by the control room habitability area HVAC. ( ' 19 0.6-6 Fault Trees - Amendment 32 23
4 888"'" # .r.. A9 en hp. f h se.1-6
. M ShselndSafsfyAse$aisAspert
- 4. }
ko g The HECW m is compriised of three loops. Imop A has pumgand onebqo refrigerator *ch provide cooling to the control building Division I equipment and the reactor building safety-related electrical equipment area. CP1 loops B and C have two pumps and two refngerators each. One of these four pum and its associated refrigerator is normally in standby rr.Me with the pump / refrigerators rotated in and out of service equally. Loops B and C provide cooling to the reactor building safety-related equipment areas B and C as well as the control building safety-related equipment areas B and C, respectively. The loop with both refrigerators and pumps in operation provides cooling to the ==m control area envelope.The standby refrigerator and pump in the other loop are available to cool the main control area envelope should one of the two pumps in the operadng loop fail. Each division is designed so one pump /refrigeratoris sized to provide cooling to the reactor building safety-related electrical equipment area and to the control building safety-related equipment area.
'Ihe combined RCW and RSW System fault tree for each of the three divisions is presented in Figure 19D.6-14 and applicable failure rate data are provided in Table 19D.66. The HECW System fault tree is presented in Figure 19D.&23. The
[' HECW failure rate data are included in Table 19D.66. These support system trees are combined with the various front line system and functional fault trees to evaluate core 4.. cooling and heat removal function failures. See Subsection 19.9.25 for COL license infonnation requirements. [ 190.6.4.3 instrurnentation System Each fault tree contained in this subsection represents the overall complex of instrument char nels, signal logics, and transmission networks involved in generating either a reactor pressure, reactor level, or drywell pressure signal used to cause a reactor l trip or to initiate the various ECCS Systems in the event of an emergency. Fault trees were developed for each signal in each electrical division. These trees are linked to the various other safety system fault trees. Events common to a number of trees are designated with identical acronyms to insure proper common cause failure treatment when these instrumentation trees are linked to the system fault trees. The instrumentation fault trees are presented in Egure 19D.6-15. Failure rate data used to evaluate these trees are provided in Table 19D.6-7. 19D.6.5 Reactivity Control Fault Trees 19D.6.5.1 "Oldy Control Functional Fault Tree ( System fault trees developed to determine the probability of failure to control reactivity and successfully shut down the reactor, given a demand, are presented in this 19D.6-7 Fault Trees - Amendment 34 24
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NOT E S: NO TITLE I UNLESS OTHCRwiSE HOTED. YKI [OUIPMENT NUMBERS i SHOWN ON THIS DeaCRnu CRC PREFIXED wt1H P23 4 NOTES. CONTEN15
# Q 2. UNLESS OTHERwtSE NOTED. THE POWER SUPPLY FOR ORTWC NMENT G F ROM M ESSENilu POwM.
2 HECW PUMP EAft11 l 3p 3. ~l" faxed NUuBERS IN THIS DIAGRAM INOtCATE THE SwCR f UNIIONAL NUMBERS. j 3 HECW PUMP t ,128 4 THE LOGIC OF REFRtGERATOR IS OMif FED BECAUSE ti 4 HECW PUMP 1 A 31 DEPENOS ON HARDW ARE STRUCIURE. 5 HECw REFRIGERATOR IAI COSRIS*,OR 1 6 HECW PUMP <0&E t til t 7 HtCw PUMPtB&El(2) REFERENCE DOCUuENT 8 HE CW PUMP 40&El 433 BU'l I HV AC EM RCENCY COOLING wAIER SYS P&t0 P25- 1010 9 OOttNG W A l[R t I ALVE (P2II P 21-10lO f 2 RE ACTOR BUILDING COOttNG W ATER SYS P&r0 ' HE CW Chit LED W A TER #N-OUT PRESSURE IU P21/ P 41- 1030 otrtRENCE CONTROL VMvE 3 RE ACIOR DUttDtNG COOlfNG W AIFR SYS/ RE ACTOR SERytCE W Ai[R SYS 100 , It ANNUNCI A T OR I i t t i t i , e I l MPL NO. P25-1030 f k O ; 3 P , W
.a L
FIGURE 7.3-9 HVAC EMERCENCY COOLING WATER SYSTEM 18D ISheet t of in - ! , ABVNIDCD/Tler2 mo p,.p3, _ _ _ _ _ _ _ _ _ _ _ . . _ . . . _ . - _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ . _ . _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ , . . . . . . - _ _ - . _ . - . . . . - - . . ~ . _ _ . . . . . - - - - . m__ _. ._ . __ _
s - O [ HECW PUMP (Al AUTOuATIC T j CONTROL SWtiCH Q ( RUNNING SICNAL SH 3 gg, y y REFRICERATOR tAl START ggg
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s [ OPERATIONAL SWITCH T LCP / (tN (PULL LOCK) POStisON j 00 SERVALS 0NAL MEASURES HECW PUMP (At SH 3 SH 5 USE SPECIFIC A tlON LOC A TION START 2 AUTO s [ LOCAL OPER ATIONAL Swif CH ) STOP / (IN (SiOP) POSITION j SH 3 I88 MCC
/ R/8 ESSENilAL ELEC
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- OPER A T HON NOT NEED
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- DYPASS NOT ExtSi SWCR PWR SUPPLY E xtSI 7 l OBSERV A TION NOT ExtST 1
ELECTRICAL SOL AC V vLv PWR SUPPLY DC V cv rigure F.3-9 HVAC EMERGENCY COOUNG WATER SYSTEM 880 (Sheet 2 of 11) ne " ABWR DCD/ Tier 2
. - ~ _ _ _ _ _ _ _ _. _ _ _ _ -_ - _ _ _ _- _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . _ _ _ - - _ _ . _ _ _ - _ - _ _ - _ .
LOCAL STOP ' pg l Stop _ [HECW REFRICERATOR EAl T
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Figure 7.3-9 HVAC ElfERGENCY COOUNG WATER SYSTEM WD(Shoot 3 of 1t) ABWR OCD/ Tier 2 nw. e 28**
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h W FIGURE 7.3-9 HVAC EMERCENCY COOLING WATER SYSTEM 80 (Sheet b of TO ABWR DCD/ Tier 2 ae b-*
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ON HECW REFRICER ATOR fBl. tC1. (E1 tF1 SUFFlX A CHANCES INCHING NEED (Ct% TE@ LOW LED WATER / 10 8. C.,E. F AND OTHERS ARE SlufL AR TO THAT Or THis SHEET. HOWEVEIT. REFRICER ATOR tel, tEl 15 RCW PUMP IB OR El OPE R A f TON NO T NE E D yAtyg SE AilNC OPEN SIDE AND REFRIGER ATOR (C1. tFl 15 RCW PUup (C OR F A . FORM CLOSED SOE p THERMAL EMSI BYPASS (\ SWGR PWR SUPPLY NOT E xtSi E xtS T OBSERV AllON NOT Exisi l HECW REFRIGERATOR (A) COMPRESSOR ELECTRICAL SOL. AC v g - vlv PWR SUPPLY DC V Y D FIGURE 7.3-9 HVAC EMERCENCY COOLING WATER SYSTEM SD tSheet 5 of 19 A8WR DCDRior 2 nae I'-18J
s IPU R IO- 1030 100 J e.py s RESIART TIME R OU T PU T t=t? s IPU CONIROL SwtICH twOI - ~ t = 15 s s [ SELECT SWliCHLB[ E: CONI]\ O> a*O (IN POSITIOt4 AUIO j / gg gg 6(CW HLf RCERATOC
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HECW CHILLtD WATER \ ELEC T ROPNEUM ATIC (C4-OUT PRESS r40iCAliNG CONTROLLER / [KFERENCE CONVE R TE R CLOSE CONIROL SW11CH ON HECW CHILLED WATER IN-OUT PRESSURE DIFFERENCE CONTROL VALVES (F0128. F 012Cl AND OTHERS ARE SIMILAR TO THAT OF THtS SHEET. OBSERV AllONAL ME ASURES USE $PECIFIC AllON LOCAllON HECW CHILLED WATER IN-OUT PRESSURE DIFFERENCE CONTROL VALVE A N ATOR NO. DOICAIOR LTAilON~ No chonge - 1nclu de M f OTHERS NEED INST ANT INTERRUP-ilON COUNTER MEAS NOT NEED b WN e. b e WP 5 3 NEED INCHING OPERATION NOT NEED VALVE SE ATING OPEN SOE FORM CLOSED SOE 7 THERMAL E XIS T BYPASS NOT Extsi y SWCR PWR SUPPLY E xtSi OBSERVATION HOI ExtSi AC W ELECTRICAL SOL VLV PWR SUPPLY ,0c w 3 W Figure 7}9 HVAC EMERCENCY COOLING WATER SYSTEM L30 (Sheet 10 of 1t) ne n Jet ASWR DCDITier 2
t CONIROL SWIICH I TS605A-1 MCRP EIURN CHILLED WATER TEMP
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i I l . l 3,y, o Unc.elak4 corr e cuen l o t cu e <ee -sta v . us ., as u ABWR s" aa ae- ' ossion controloceaneatmer t \ . l l l l In the high radiation mode, a positive pressure of at least 3.2 mm water gauge is maintained in the MCAE relative to the outside atmosphere. Each emergency filtration unit treats a mixture of MCAE recirculated air and outside makeup air to maintain the positive pressure with not more than 360 m8 per hour (@ one atmosphere absolute pressure,0*C) of outside air. The redundant division of the CRHA HVAC System starts on a low flow signal from j the operating emergency filtration unit. The redundant dhision is connected to an outside airintake, which is separated from the other intake by a minimum of 50m. , l Outside Smoke Mode l l When smoke detection sensors in the operating outside air intake detect smoke, a l signal will initiate MCAE air recirculation by isolating the outside air intake, closing ; the exhaust damper and stopping the exhaust fan. Smoke Remov/al M o Se The smoke removal mode is manually initiated by closing the recirculation damper E
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f' QT 7[8e*cT'68 "c7djUiti on J a- 8*^- wI*h hFbd The remaining discussion in this section is not mode-specific and applies (unless stated CP 3 otherwise) to the entire CRHA HVAC System. MCAE temperature is maintained between 21*C and 26*C, with a relative humidity between 10% and 60%, except when in the smoke removal mode. The CRHA HVAC System is classiSed as Seismic Category I. The CRHA HVAC System is located in the Control Building. i l Each of the two CRHA HVAC System divisions is powered from the respective Class 1E j division as shown on Figure 2.15.5a. In the CRHA HVAC System, independence is i provided between Class 1E dhisions, and also between the Class 1E divisions, and non-Class 1E equipment. l l l Each mechanical division of the CRHA HVAC System (Divisions B and C) is physically l separated from the other disision, except for the common ducts in the MCAE. 1 l Fire dunpers with fusible links in HVAC duct work close under air flow conditions. The CRHA HVAC System has the following displays and controls in the main control i room: (1) Controls and status indication for the active safety-related components shown on Figure 2.15.5a. 2.15.S-2 Heating, Ventilating and Air Conditioning Systems I \ l
j j y/gQ Un ofr<laSe A Cavc & c F.'b n cus rent Rev. NO.y a.s .4 ABWR s m u. Desiaa controlooeamentmer t i Hydrogen concentration is maintained at less than 2% by volume in the battery eds d bob * "' "# [UIb V h i Smoke Removal Mode The smoke removal mode. is manuallyinitiated by closing the recirculation damper, y =pp!:;i: " rt'- > ^p ';i: ::Mr: fen hy~ d=p= to allow gp3y outside air purging of the affected Control Building area. The normal operating l mode is used to remove smoke from the battery rooms. The remaining discussion in this section is not mode-specific and applies (unless stated otherwise) to the entire CBSREA HVAC System. The CBSREA HVAC System is classified as Seismic Category I, except for the non-safety-related fan coil units. The CBSREA HVAC System is located in the Control Building. Each of the three CBSREA HVAC System divisions is powered from the respective Class , l IE division as shown on Figures 2.15.5b,2.15.5c and 2.15.5d. In the CBSREA HVAC System, independence is provided between Class IE dhisions, and also between the Class IE divisions and non-Class IE equipment. Each mechanical division of the CBSREA HVAC System (Dhisions A, B and C) is l physically separated from the other dhisions. CBSREA HVAC System Division B duct l penetrations of Division IV firewalls are provided with fire dampers. Fire dampers with fusible links in HVAC duct work close under air flow conditions. The CBSREA HVAC System has the following displays and controls in the main control room: (1) Controls and status indication for the active safety-related components shown on Figures 2.15.5b,2.15.5c and 2.15.5d. l (2) Parameter displays for the instruments shown on Figures 2.15.5b,2.15.5c and 2.15.5d. I Reactor Building HVAC System The Reactor Building (R/B) HVAC System provides a controlled emironment for the l operation of equipment in the Reactor Building. The Reactor Building HVAC System consists of three independent safety-related divisions. Each dhision is composed of the folk wing systems: (1) R/B Safety-Related Equipment HVAC System. (2) R/B Safety-Related Electrical Equipment HVAC System. I I 2.15.5-4 Heating. Ventilating and Air Conditioning Systerns 2 i
Unnic3aa corce a; , I y0 ' " " " * " * ' " " l ABWR &~14 be . Desen CameralDecament(nor1 ' l The R/B Safety-Related Equipment HVAC System has the following displays and l controls in the main control room: (1) Controls and status indication for the FCUs shown on Figure 2.15.5e. The safety-related electrical equipment shown on Figure 2.115e located in the Reactor Building is qualified for a hanh environment. i R/B Safety-Related Electrical Equipmerit HVAC System The R/B Safety-Related Elecnical Equipment HVAC System provides cooling of safety-related electrical equipment areas, and consists of three independent divisions. Each ! l I l division consists of an air conditioning unit with two supply fans, and two exhaust fans. Egures 2.15.5f,2.15.5g, and 2.15.5h show the basic system configuration and scope. l The R/B Safety-Related Electrical Equipment HVAC System is classified as safety-related. Normal Operating Mode In the normal operating mode, the air conditioning unit, one supply fan, and one exhaust fan of each division operate.The exhaust fan automatically starts when the ! supply fan is started. In the areas served by the R/B Safety-Related Electrical Equipment HVAC System temperature is maintained below 40*C, exceptin the diesel generator (DG) engine p3 rooms during DG operation. , cmd M ac h nj me 4moKO r-e m ov a l
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Smoke Removal Mode E# * '" '#^ bu e P,% -E n nP'" C The smoke removalm anuallyimtiated by closing the recirculation damper, stopping the exhaust fan,' o 'ng the exhaust fan bypass damper to allow outside air purging of the affected are The normal operating mode is used to remove smoke from the DG day tank ooms. The R/B Safety-Related Electrical Equipment HVAC System is classified as Seismic Category I. The R/B Safety-Related Electrical Equipment HVAC System is located in the Reactor Building. ! Each of the three divisions of the R/B Safety-Related Electrical Equipment HVAC System is powered from the respective Class IE division as shown on Figures 2.15.5f, 2.15.5g, and 2.15.5h. In the R/B Safety-Related Electrical Equipment m'AC System, independence is provided between Class 1E divisions, and also between the Class IE divisions and non-Class IE equipment. Each mechanical division of the R/B Safety-Related Electrical Equipment m'AC System (Divisions A, B, C) is physically separated from the other dhisions. 2.15.5-6 Heating. Ventilating and Air Conditioning Systems 3
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( Emergency conditions such as a LOCA or high radiation cause an automatic changeover reducing outside air intake and to start charcoal filtering all outside air and a portion of the return air. This effectively isolates operating personnel from the emironment and from airborne contammation. Protection from direct radiation is discussed in Subsection 6.4.2.5. Detection of radioacthity is instrumented, and changeover to reduced circulation and charcoal filtedng is automatic. Redundancy ofinstrumentation and air handling , systems ensures against system failure due to single component failure. l { The above operational description is bdef. For a more detailed description of normal ! and emergency operation of the control room habitability systems, see l Subsections 9.4.1,9.5.1,9.5.3,12.3.4,6.5.1, and Chapt-r 8. l l i ( 6.4.4 Design Evoluations l 6.4.4.1 Radiolorfeel Protection The Chi /Qs used for evaluation of the control room operator dose to meet General Design Criterion 19 are presented in Subsection 15.6.5. 6.4.4.2 Smoke and Toxic Gas Protection As discussed and evaluated in Subsection 9.5.1, the use of non-combusulle construction and heat- and flame-resistant materials throughout the plant minimizes the likelihood of fire and consequential fouling of the mam control area envelope atmosphere with smoke or noxious vapor introduced in to the control room air. In the smoke removal ! mode, the purge flow through the Control Building provides three air changes per hour in order to swe atmospheric co taminants out of thga.( 3 .n coo 3 un c %n , l 54 g b .4 o %d -4w.r a *) 2 % o,A 4 p3 r g j i The main control area envelope is normally exhausted from ti circulation plenum ! byone of the exhaustfans. Smoke removalis accomplished by/ %re=5 = _a, cP3 and realigning the dampers for exhausting directly to the exhaust vent. ". ,100~ -
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l changeover is under manual control from the main control room. Operating penonnel I in the control room exercise this option in response to signals from the smoke detec. tion sensors located in the subject spaces and in the associated ductwork. Transfer of the system to the isolation mode for exterior smoke may also be initiated I manually from the control room. Local, audible alanns warn the operators to shut d.e
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bch e.k msk b,r W.S ) n.s con y c4'on w s th a du ppig M j The safety-related isolation valves at the outside air intakes are protected from cP3 ! becoming inoperable due to freezing, icing, or other emironmental conditions. l
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Upon detection of smoke in the CRHA. the operating division of the HVAC System is ; putinto smoke removal mode by the maia control re.om operators. For smoke removal, i: 25 i .; rr,25e recirculatiory' :rdddosed.H et. '.g ..? A
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9.4.1.1.5 Inspection and Testing Requirements Provisions rre made for periodic tests of the emergency filtration unit fans and filters. These tests indude measurement of differential pressure across the filter and of filter efBeiency. Connections for testing, such as injection, sampling and monitoring, are properly located so that test results are indicathe of performance. The high-efficiency particulate air (HEPA) filters of the CRHA HVAC System shall be l tested periodically with diocryl phthalate smoke (DOP). The charcoal filters will be l periodically tested with an acceptable gas for bypasses. Removal efBciency shall be at l least 95% for all forms ofiodine (elemental, organic, particulate and HI, hydrogen iodide in the influent system). Each emergency filtration division duct work outside MCAE shall be periodically tested for unfiltered inleakage in accordance with ASME N510. Each emergency filtration division shall be pedodically inspected for open maintenance access doors or detedorated seals that could lead to charcoal filter bypass. The balance of the system is proven operable by its use during normal plant operation. Portions of the system normally closed to flow can be tested to ensure operability and , integdty of the system. l i 9.4.1.1.6 Instrumentation Application One of two air conditioning unit supply fans is started manually. A high radiation signal automatically starts the emergency air filtration fan, closes the normal CRHA HVAC System air inlet dampers and closes the exhaust air dampers and stops the exhaust fan. A temperature indicating controller senses the temperature of the air leaving the emergency filtration system. The controller then modulates an electdc heating coil to maintain the leaving air temperature at a preset limit. A limit switch will cause an alarm to be actuated on high air temperature. A moisture-sensing element, working in 4 conjunction with the temperature controller, measures the relative humidity of the air entering the charcoal adsorber. I 9.4 4 Air Conditioning, Heating, Cooling and Ventilating Systems 12
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One of the safety-related electrical equipment area exhaust fans starts automatically when the air-condidoning unit supply fan is started. On a smoke alarm in a division of the Control Building safety-related electrical equipment area HVAC System, that division of the HVAC System shall be put into smoke removal mode. No other division is affected by this action. For smoke r , the recirculation duct damperis closed, d.e f- . W %-4..[p..cMan h ria; 4 '- -rr i Normal on'ce through ventilation of the httery rooms also removes smoke from the battery rooms. gp 3 Fire dampers separating electrical divisions II and IV rooms that use fusible links in HVAC ductwork will close under airflow conditions after fusible link melts. 9.4.2 Spent Fuel Pool Area HVAC System The Spent Fuel Pool Area HVAC System is part of the Reactor Building secondary containment HVAC System described in Subsection 9.4.5.1. 9.4.3 Auxilary Area HVAC System The Aunlary Area HVAC System is also pan of the Reactor Building Secondary Containment HVAC System described in Subsection 9.4.5.1. 9.4.4 Turbine Island HVAC Systern 1 The Turbine Island heating, ventilating, and air conditioning system consists of the l Turbine Building (T/B) HVAC System and the Electrical Building (E/B) HVAC l System. 9.4.4.1 Design Bases 9.4.4.1.1 Safety Design Bases j The T/B HVAC and E/B HVAC Systems do not serve or support any safetyfuncrion and have no safety design bases. l 9.4.4.1.2 Power Generation Design Bases (1) The T/B HVAC and E/B HVAC are designed to supply filtered and tempered air to all Turbine Island spaces during all modes of normal plant operation, including plant startup and shutdown. The systems are also designed to l maintain inside air temperatures above 15'C and below the following upper design limits: a General Turbine Building areas: 40*C a Condenser compartment- 43 C f Air Conditioning. Heating. Cooling and Ventilating Systems 9.4-9 13 l
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l ' l All major components are tested and inspected as separate compor.ents pdor to l installation to ensure design performance. The system is preoperationally tested in l accordance with the requirements of Chapter 14. i ! 9.4.5.3.5 instrumentation Application l The R/B Non-safety related Equipment HVAC System starts manually. 9.4.5.4 R/B Safety-Related Electrical Equipment HVAC System 9.4.5.4.1 Design Bases CP3 l l 9.4.5.4.1.1 Safety Design Bases The R/B Safety-Related Electrical Equipment HVAC System is designed to provide a controlled temperature environment to ensure the continued operation of safety- ; l related equipment under accident conditions. The rooms cooled by the R/B Safety- l Related Electrical Equipment HVAC System are maintained at positive pressure relative f l to atmosphere during normal and accident conditions. This is achieved by sizing intake fans larger than exhaust fans. 4 p a The power supplies to the HVAC systems for the R/B safety-related electrical I equipment rooms allow uninterrupted operation in the event ofloss of nonnal offsite w power. 3 t-The system and components are located in a Seismic Category I structure that are I tomado missile, and flood protected, including tomado missile barriers on intake and I 3 exhaust structures. C For compliance with code standards and regulatory guides, see Sections 3.2 and 1.8. .o
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v On a smoke alann in a division of the Reactor Building Safety-Related Electrical c Equipment HVAC System, that division of the HVAC System shall be put into smoke remon1 mode manually. No other division is affected by this action. For smoke removal,4 1 h j 0 ' the recirculation damper is closed, the exhaust fan bypass damper opened, antribe exhaust fan is stoppe Normal once through ventilation of the day tank rooms also E : removes smoke from day tank rooms. sb4<g awd-hbe 3m oh er mov a( bw ga The intake louvers are located at 15.2m above grade. The exhaust louvers are located at 13.Sm above grade. (See general arrangement layout, Figures 1.2-10 and 1.2-11.) 9.4.5.4.1.2 Power Generation Design Bases 1
- The system is designed to provide an environment with controlled temperature and humidity to ensure both the comfort and safety of plant personnel and the integrity of safety-related electrical equipment. The system is designed to facilitate periodic inspection of the principal system components.
Air Conditioning Mesting. Cooling and Ventilating Systems 9A 23 l 14
nov. o - ABWR ana6e ceanetoncanumerz a. Lc (2) Mre barder walls which are of the speaal construcdon descdbed in Subsection 9A.S.6 or of other approved construction types beanng a UL (or equal) hoel for a three-hour rating. (3) Mre doors, which are required to have a UL (or equal) label certifymg that they have been tested for a three hourvating per ASTM E152, including a hose stream test. (4) Both ends of all electdcal and piping penetrations between the divisions and between a division and a non.dmsion should be quali6ed to the same standard l and tested to ASTM E119. -- (5) Not Used (6) Mre dampen, which are required for any HVAC duct penetranng a fire barrier, must have a rating of three hours 3Ihe only 6re dampers separatm Gmsions are in the HVAC duct for secondary containment (six total . e plant anangement mmimwen fire dampen. (7) Columns and suppon beams, which are i@sd to be of remforced concrete ( ,, ' construction or enclosed or coated to provide a three4 tour rating if of steel construction. (8) Backup of the Sre barrier penetration seals by the HVAC Systems when the I HVAC Systems are operatingin the smoke removal mode. This backup feature is accomplished in the Reactor and Control Buildings by maintainmg a positive static pressure for the redundant divisional fire neas with respect to the fire area with the fire. Leakage is into the fire impacted area under sufficient static pressure to confine smoke and heat to the fire area expedencing the fire, even if there is a major mechanical failure of the penetration seal. (9) AC independent water addition (ACIWA) can be connected to the reactor building fire protection system header. SufficientMreWater pressure and flow should be avadable to perform the intended function. Refer to Subsection 5.4.7.1.1.10, AC-IndependentWater Addition. ! 9.5.1.1.4 Combustible Loading I Allowable combustible loadings for the plant were established as follows (see Appendix 9B, Subsection 9B.2.3 for additional details): (1) 1454 MJ/m of2 room area, rnanmum allowable average exposed combustible loading without an automatic fire suppression system.This is termed the normal combustible loadinglimit (NCLL). 959 Other Auxiliary Systems 15
Rev.0 -
. ABWR Desion coansoocamenerin2 A single non-safety-related HVAC System supplies normal cooling for secondary l containment in the Reactor Building. Within the Reactor Building the system is branched into three separate systems with valves and fire dampers for each branch (Subsection 9.5.5). Required emergency cooling for safety-related systems is provided i by room coolers on a divisional basis.
l i 9.5.1.1.6 Smoke Control System The smoke control system for the plant provides major features as follows: (1) Venting of fire areas to prevent undue buildup of pressure due to a fire. (2) Pressure control across the fire barders to assure that any leakage is into the fire area expedencing the fire. (3) Pressure control and purge air supply to prevent back-flow of smoke and hot gases when fire barder doors are maintained open for access for manual fire suppression activities. (4) Augmented and directed clean air supply to provide a clean air path to the fire for fire suppression personnel. (5) Smoke control by fans and systems external to the fire area expedencing the l fire. bs ' ex hau s+ erwi 3
- prov de (6) Remon1 of smoke and heat from the fire by fansgopenting% supply can, cool air. -
M am.M3 as a+ p os e4 h ol 3 (7) Ocam'; Bre dampers in the smoke remoni path.
'These features are provided by designing the HVAC Systems for the dual purpose of HVAC and smoke control. ASHRAE's " Design of Smoke Control Systems for Buildings" and NFPA's " Recommended Pactice for Smoke Control Systems" (Re rerences 9.5-3 and 9.5-4) were used as the basis for the design of the smoke control features of the combined systems.
The normal operating modes of the HVAC Systems are shown in Figures 9.4-1 through 9.4-6. The pressure at the input of an air handling unit is held at atmospheric pressure by a ducted, direct supply from outside cmdthrough ehm s a bag type filter. 9 .+ke The systems are designed so the division of air flow to the r s within an i HVAC/ fire area is determined by the supply ducting and ' djustable volume ! dampen. The d.12 ':::2. 7 :: : E r k ~, L . L ir p'- 3:::2 - -ii -t
... A . dju- " - +;; ;-:';...y a 6 . 'j - - ;:rr afi: x n-.; :s i;-. homuug $
g ;;i.. .".j u'lns ii 2 ^;. r .eh- :: '" p-e prim arih. sr.r., - 77 5,.r , L ;; ,;,;',, Other Auxiliary Systems 9.5-11 16
Asw.# [ M DsI4sdestelDemmes0Tlerf the-- *[ e
~
flow -4 # rooms ' the tal vary ris ' to the ping -[=- = = '--3c supply of/ ~ ~ n fan. Ifa is in a area, dual peradj to w ethe a oi.d system a by , i=g path to 4 atmosp *
, = of vol damper
- the 'l=da= 4 ten d The a== __ also of
=d,= duct block ~ - !=?a of imsti p This the in fire cing the to to e on = an J - '- '----- A x x ' , '- "-- M_. He HVAC Systems in the fire areas not experiencing a fire continue to operate in their normal fashion so that the pressure in theotherfireareasremainsa k _' -- ' g, _
~
^ ';S C it-:stivevalue. 4 This assures that airleakage through any openings in the fire baniers surrounding the fire is to the fire. CP3 1
The magnitude of the differential pressure which must he maintained across a fire barrier to provide adequate smoke control varies with the intensity of the fire and the room height. For this reason, it is a COL Heeme information requirement (S=*-:--F--- 9.5.15.10) that the rapmed r tialpressurevalue for each bamerbe calculated during the detailed design phasq the HVAC Systems be da i-nadto provide the required r -f NormaBy the di5erential pressure would not have to be more than about #mm of water, and it most likely would be less. -
\s.4 faHVA =:--gin ~ nar--wade is yy;7-,p i'ue reg differ tialy. p-:there s, co optio available the de+=i14- igner. may fire '
be w-- specify on,bo d-da/ fans a be run each area not 'en ' the thisis not , it then be n to otor e dam inpface man le j rs in the ""' - 1= ' - to - g 0 7 in the e i
+
areas no /---T = g _ return '
=-g a fire. is an CO license
- rmation at
\
j (Subsecti 9.5.15. thatthe be le d-*-d g de ~ l
' _ ' , , - , _ _, i :. .'."." E ^ - - L. ' - ',, f :: r------ IGM 5 r --
,'Ed that
%c'apability be confirmed ciarmg r -uposnonal testinJg _
Entry to a fire is gained from an =di= raat fire area which by dengn is at a positive ; pressure with respect to the area experiencing the fire. The pressure differential is sufficient to provide adequate velocity G-vugh the open door to carry the combusdon products back into the zone of the fire. He flow duuush the open door into the area of the fire and out the area of the fire's - h==r duct system is maintained by the positive
- - c'i:In !:=
' ^'
_,. - .: " nc. .
" ~
pressure _,%.e #_ of _.-the non4 ire y-s-- a:..c_ n24_ .t ysm4.. = ._.ec... ,_ . m__ _ _ _.:.t _... .u. e_ m - e_ _ . . _ . . '
= n _ .t _i_ .u.
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ' ~ ' ~ ~ " ~ ~
~Z and j,now,e le3wenovat4M o yyn e ro aGcW d e. In'aj+M 'O re a re a .
9.5-12 Other Auxiliery Systems
' ~
17
l 1 l
- nov. o ,
ACIW 5.ip,c ins serier b re (.h aj T j to gc u) t 2d;2"-- l C/ -^^ C RG :-d i.- -#. i; F;; i r i ^; i; ; :: ; L E d [,.. , L. '"i ::: =}f p.
=__ _ 2-- . .a...__
cd.. :.1; f.s; cf -;Mx ': -_p;:_ _fx:r __i . : . s_. m __ _- - - _ _ _ :: i; ._;;;m S; _ _i n - .xx _ .u5 :
!f { ; chb;15. It gives a tenab e environment from to k. ;
.c.E *O UI Since th AC Sys are man htched over once-through syste ga j*
~
fire ere is no ct mirm smoke from r to room within the area. There
- ay be so eakage normalHV and other r openingsin the
]fE vd5 "g
walls. e venting e fire
'ded by the d thus min' tricted exhaust syste smoke leakage to r revents pressurization adjacent to the fire. y
.2 c g ue to vent
{d y The C supply and fire area expe ust systems are d cing a Bre, regardi ed so that they will co of the intensity or == . ie of the fire. w E 5 yzo Exceptwi ' e Reactor Buildin ondary containmen ere are no fire go 5 ' in the la C Svstema for the R etor or Control bnE as. This is possibi use
, h ,'O pere are HVAC penetrations of building internal walls between safety related fire areas.seaba 2: S; '- p;n ;.x ;;pd fx h_d =J.'_C d::r,,
"li j ,c J Des &ad's a s s*n ne l j" l
In order to maintain the objective of smoke and heat removal during a fire situation, g, the HVAC supply and exhaust duct openings in the exterior walls of the Reactor building do not have Sre dampers. The walls are designated as three-hour fire barriers
, ~*.,32 'ti g g2 : and would normally require Sre dampers for HVAC duct penetrations. Fire dampers could close due to heat from an internal fire, however. Internal fires are a more serious g ,g g, i E threat to the plant than external fires.
l:2 li E
- .g 4
- CP 3 '
g C, j Omission of the fire dampers in the supply ducts is deemed acceptable because: , n i
.w c 'E " (1) Each HVAC/ fire area has a separate intake structure.
g .$ $2 ,
,ggj 1 (2) The intake structures are dispersed around the perirneters of the buildings.
6Eob t' 5 g 6 n. (3) Not Used l co l
.@ E" '$ .ta @" (4) Isolation valves are provided and could be manually closed should there be a ;
$!!E challenge due to an external fire.
, _'Ec .o g5 - .m \
p;; ,~ ~o 7 (5) Each intake serves one fire area and, therefore, one division only except for
@ga@ the control room. The two redundant divisions are in separate fire areas. The l .6 d 3 control room fire area is separate from all other fire areas and the safe j ,
shutdown function is backed up by the remote shutdown panel. j j DkIO Omission of the Sre dampers in the exhaust ducts is deemed acceptable because: I (1) Each HVAC/ fire area has a separate exhaust. } Other Auxiliary Systems 9.5-13 l 18 l
r 1 l
. nov. o A B MfR anainn coneetoecamenener2 t .
Table 9A.6-2 Fire Hazard Analysis Equipment Database Sorted by Room - Reactor Building (Continued) Lassekm Leestsen team Elest Elev. N wnber Alphe system Roorn ! l No. MPL No Div. Loeotion Coord. Coord. Desenpelen Drawing No. 2331 U41-8202B 1 27200 6.8 A.8 COOL COIL ELEC EQ(A) 107E5189M 612 2332 U41-8202A 1 27200 6.5 A.8 COOL COIL ELEC EQ(A) 107E5180/0 612 2333 U41-F005A 1 27200 6.4 A.5 MO VALVE 107E511ND 613 i 1 I i 2334 P54.A001A 1 23500 6.2 B.2 N2 STORAGE BOTTLE 107E5128/0 613 l 2335 P54-A001C 1 23500 6.2 B.2 N2 STORAGE BOTTLE 107E5128/0 613 . I 2336 . P54-A001E 1 23500 6.2 B.2 N2 STORAGE BOTTLE 107E5118/0 613 l l 6.2 B.2 N2 STORAGE DOTTLE 107E5128/0 613 2337 P54-A001G 1 23500 ] 6.2 B.2 N2 STORAGE BOTTLE 107E5128m 613 2338 P54-A001J 1 23500 6.2 B.2 N2 STORAGE BOTTLE 107E5128/0 613 2339 P54-A001L 1 23500 l 6.2 B.2 N2 STORAGE BOTTLE 107E5128/0 613 l 2340 P54-A001N 1 23500 23500 6.2 N2 STORAGE BOTTLE 107E5128/0 613 l 2341 P54-A0010 1 B.2 2342 P54-A001S 1 23500 6.2 B.2 N2 STORAGE BOTTLE 107E5128/0 613 2343 P54-A001U 1 23500 6.2 B.2 N2 STORAGE BOTTLE 107EC128/0 613 2344 P54.F003A 1 23500 6.2 B.2 MO GLOBE VALVE 107E5128/0 613 2345 P54-F012A 1 23500 6.2 B.2 MO GLOBE VALVE 107E5128/0 613 ; 2346 P54-PfS001A 1 23500 6.2 B.2 PRESS IND SWITCH 107E5128/0 613 ( DG(A) HVAC EXH FAN A 107E5189/0 613 ^C b 3 2347 U41-C202A 1 23500 6.4 B.2 6.4 ILS DG(A) HVAC EXH FAN E 107E5189/0 613 2348 U41-C202E 1 23500 4 cf 2 - MO VALVE 107E5189/0 613 2349 U41-F006A 1 23500 6.4 B.5 2350 R24 MCC A310 N 23500 6.3 C.0 MCC A310- R/B 107E5072/0 613 b jert 2351 R43-C201A' 23500 6.6 B.8 DG AIR COMPRE:iSOR A SSAR FIG 9.5-8 613 "A" 1 2352 R43-C202A* 1 23500 6.9 B.8 DG AIR COMPRESSOR A SSAR FIG 9.5-8 613 2353 D21-RE007 N 23500 5.2 B.0 AREA RAD DETECTOR 299X701-171/0 615 N 23500 5.3 C.3 SELECT SWITCH 107E6043/0 615 2354 T31-SSAD51 N 23500 5.3 C.3 SELECT SWITCH 107E6043/0 615 2355 T31-SSA053 N 5.3 C.4 TEMP INDICATOR 107E6043/0 615 2356 T31-Tl051 23500 23500 5.3 C.3 TEMP INDICATOR 107E6043/0 615 2357 T31-Tl053 N 23500 5.3 C.3 TEMP TRANSMITTER 107E6043/0 615 2358 T31-TTQ51 N 5.3 C.3 TEMP TRANSMITTER 107E6043/D 615 2359 T31-TT053 N 23500 2360 U41-C103 N 23500 5.4 C.1 PCV PURGE SUPPLY FAN 107E5189/0 615 616 I 2361 U41-F004C 3 29000 5.8 B.8 MOVALVE 107E5189/0 5.8 B.8 MOVALVE 107E5189/0 616 2362 U41f101C 3 29000 616
# i 2363 T31-r731 1 23500 5.8 C.8 SO VALVE 107E6043/0 l
l PRESSURETRANSMITTER 107E6043/0 616 ,. 2364 T31-PT054 N 23500 5.8 C.8 l Fire Hazard Analysis Database 9A.6-78 19
l
- j
- nov. o 1 ABWR odira coneoloocamtmer2
*l .
Table 9A.6-2 Fire Hazard Analysis l Equipment Database Sorted by Room - Reactor Building (Continued) l l Laoston Loostion Bact Elev. Nwnber Alpha System Room hem No. MPL No Div. Lacetion Coord. CoonL Desenpuon Dre m ne No. N 23500 2.3 D.6 TEMP SWITCH 107E6016/0 622 2432 C41-TIS 006 2433 U41-C104 N 23500 2.3 E.7 PCV PURGE EXHAUST 107E5189/0 623
/ FAN 2434 R43-LS395B' 2 23500 1.3 E.9 EVEL SWITCH SSAR FIG 9.5-6 624 2 F.2 COOL COIL.ELEC EO (B) 107E5189/0 663 2435 U41-B2048 27200 1.2 2 27200 1.5 F.2 COOL COLL.ELEC EO (B) 107E5189/0 663 2436 U41-8204F 2 27200 1.6 F.3 MO VALVE 107E5189/0 663 j 2437 U41-F005B DG(B) HVAC EXH FAN F 107E5189/0 625 l 2438 U41-C206F 2 23500 1.8 E.7 Add- ~2439 U41-F006B 2 23500 1.6 E.5 MO VALVE 107E5189/0 625 g
G s.'F 2440 R43-C201B' 2 23500 1.1 E.2 DG AIR COMPRESSOR B SSAR FIG 9.54 625 2441 R43-C202B' 2 23500 1.3 E.2 DG AIR COMPRESSOR B SSAR FIG 9.5-8 625 2 23500 E.4 DG(B) HVAC EXH FAN B 107E5189/0 625 2442 U41-C205B 1.8 N 23500 1.8 D.5 MCC B310 R/B 107E5072/0 625 2443 R24 MCC B310 2444 R43-A005C' 3 23500 6.5 F.8 FUEL OIL DAY TANK SSAR FIG 9.5-6 630 ([.
~
2445 R43-LS395C' 3 23500 6.7 E.9 LEVEL SWITCH SSAR FIG 9.54 632 3 6.8 F.2 COOL ColLELEC EO (C) 107E5189/0 673 2446 U41-8206G 27200 3 27200 6.5 F.2 COOL CO!L.ELEC EO (C) 107E5189/0 673 2447 U41-8206C 6.3 F.1 CAMS GAS CYL RACK A 107E5139/1 633 2448 H22-PO44A* 1 23500 3 27200 6.4 F.3 MO VALVE 107E5189/0 673 J449 U41-F005C N 23500 6.3 E.5 MCC C310 - R/B 107E5072/D 633 2450 R24 MCC C310 2451 R43-C201C' 3 23500 6.6 E.2 DG AIR COMPRESSOR C SSAR FIG 9.5-8 633 L3 c.f t-2452 R43-C202C' 3 23500 6.6 E.4 DG AIR COMPRESSOR C SSAR FIG 9.5-8 633 "A" 2453 R10-C001E' N 23500 6.3 D.5 RIP ASD OUTPUT XFMR 638 2454 R10-C001B' N 23500 6.3 C.7 RIP ASD OUTPUT XFMR 638 E.4 ISI ROOM FCU B 107E5189/0 639 2455 U414134B N 23500 5.5 2 23500 1.8 A.4 N2 STORAGE BOTTE 107E5128/0 640 2456 P54-A001B 2 23500 1.8 A.4 N2 STORAGE BOTTLE 107E5128/0 640 2457 P54-A001D 2 23500 A.4 N2 STORAGE BOTTLE 107E5128/0 640 2458 P54-A001F 1.8 23500 1.8 A.4 N2 STORAGE BOTTLE 107E5128/0 640 2459 P54-A001H 2 2 A4 N2 STORAGE BOTTLE 107E5128/0 640 2460 P54-A001K 23500 1.8 23500 1.8 A.4 N2 STORAGE BOTTLE 107E5128/0 640 2461 P54-A001M 2 1.8 A.4 N2 STORAGE BOTTLE 107E5128/0 640 2462 P54-A001P 2 23500 23500 1.8 A.4 N2 STORAGE BOTTLE 107E5128/0 640 2463 P54-A001R 2
$ A.4 N2 STORAGE BOTTLE 107E5128/0 640
\ 2464 P54-A001T 2 23500 1.8 2465 P54-A001V 2 23500 1.8 A.4 N2 STORAGE BOTTLE 107E5128/0 640 Rre Hazard Analysis Database 9A.641 20
Insert "A" for Table 9A.6-2, Pages 9A.6-78 and -81 Addition of Smoke Removal Fan in R/B S/R Electrical Eauinment HVAC (At (B) and (C) 2348a U41-C210A N 23500 6.4 B.5 SREE HVAC Smoke Removal Fan A 107E5189/0 613 2438a U41-C211B N 23500 1.8 E.7 SREE HVAC Smoke Removal Fan B 107E5189/0 625 2449a U41-C212C N 23500 6.3 E.5 SREE HVAC Smoke Removal Fan C 107E5189/0 633 t b i a 2 '- w
~
mm . i 09 +D>
~
h
i
~
\
Rev.O ABWR ouie coneoioocameria2 19 1
*s l Table 9A.6-3 Fire Hazard Analysis Equipment Data Base-Sorted by Room -
Control Building (Continued) LOCADON LOCADON ITEM MPL ELECT ELEV. NUMBER ALPHA SYSTEM ROOM NO. NO. DIV. LOCATION COORD COORD. DESCRIPTION DRAWING NO. 200 P25-D001G 3 12300 6.70 J.2 HECW REFRIGERATOR F 107E5182/0 534 201 P25-DPT007C 3 12300 5.70 J.6 DP XMTR (FLO CONT C/F) 107E5182/0 534 202 P25-F005C 3 12300 6.90 J.2 TCV: MCR CLG 107E5132/0 534 203 P25-F012C 3 12300 5.70 J.4 PCV: HECW UNITS C/F 107E5182/0 534 j 204 P25-FIS003C 3 12300 6.00 J.2 FLOW IND SWITCH C 107E5182A 534 205 P25-FIS003F 3 12300 6.70 J.2 FLOWIND SWITCH F 107E5182/0 534 206 P25-TE005C 3 12300 6.00 J.2 TEMP EMM (UNIT C/F) 107E5182/0 534 207 U41-C623C 3 12300 6.20 J.1 MCR REORC SUPP FAN C 107E5188/0 534 208 U41-CS23G 3 12300 6.20 J.1 MCR RECIRC SUPP FAN G 107E5188/0 534 ! 209 H11-P001' N 12300 4.00 K.0 COMPUTER PANELS 591 210 P25-A002 N 12300 5.30 J.5 CHEMICAL FEEDTANK 107E5182/0 593 211 P25-DPT007A 1 12300 5.30 J.2 DP XMTR (FLO CONT A) 107E5182/0 593 212 P25-TE005A 1 12300 5.30 J.2 TEMP ELEM (UNIT A) 107E5182/0 593 213 P25-C001A 1 17150 5.30 J.4 HECW PUMP A 107E5182/0 612 214 P25-D001A 1 17150 5.30 JA HECW REFRIGERATOR A 107E5182/0 612 215 P25-F012A 1 17150 5.50 J.2 PCV: HECW UNIT A 107E5182/0 612 216 P25-FIS003A 1 17150 5.30 J.2 FLOWIND SWITCH A 107E5182/0 612 217 U41 C605A 1 17150 5.20 K.5 EM EEC (A) EXH FAN A 107E5189/0 613 218 U41-C605E 1 17150 5.20 K.6 EM ELEC(A) EXH FAN E 107E5189/0 613
' '2
- 219 Ud* "T # "' MO E' * ^'55
- S 5** .'
220 U41-C622C 3 17150 5.70 K.5 MCR HVAC EXH FAN C 107E5189/0 614 221 U41-C622G 3 17150 5.70 K.6 MCR HVAC EXH FAN G 107E5189/0 614 222 U41-DP1106C 3 17150 5.70 K.5 DIFF PRESS INDICATOR 107E5189/0 614 j C ?3 1 s 223 U41-DP1107C 3 17150 5.70 K.5 D FF PRESS INDICATOR 107E5189/0 614 224 U41-DP1108C 3 17150 5.70 K.5 DIFF PRESS INDICATOR 107E5189/0 614 s 225 U41-DP1109C 3 17150 5.70 K.5 DIFF PPESS INDICATOR 107E5189/0 614 226 U41-F009C 3 17150 5.70 K.5 MOVALVE 107E5189/0 614 227 U41-F009G 3 17150 5.70 K.6 MO VALVE 107E5189/0 614 228 U41-F010C 3 17150 5.70 K.5 MO VALVE 107E5189/0 614 229 U41-F010G 3 17150 5.70 K.6 MOVALVE 107E5189/0 614 y( b ylau. win 0.70 J)e le t Ce cl ** )YO7 VMVC '07E51 % 010 , 230 -U41 "012C 0 *50 231 U41-POT 105C 3 17150 5.70 K.5 POSITION TRANSMITTER 107E5189/0 614 232 U41-POT 105G 3 17150 5.70 K.6 POSITION TRANSMITTER 107E5189/0 614 [t 233 U41-B601C 3 17150 6.80 J.3 MCR COOUNG COIL 107E5189/0 615 Fire Hazard Analysis Databasa 9A.6-102 22
_ _ . . ...-a mv. o ABWR ancien con 8,Iommartra2 l l . I I { Table 9A.6-3 Fire Hazard Analysis Equipment Data Base- Sorted by Room - Control Building (Continued) LOCADON LOCADON ELECT EEV. NUMBER ALPHA SYSTEM ROOM ITEM MPL NO. DIV. LOCATION COORD. COORD DESCRIP110N DRAWING NO. NO. 17150 1.80 J.1 MO VALVE 107E5180/0 621 268 U41-F000B 2 2 17150 1.80 J.1 MO VALVE 107E5189M 621 288 U41-F009F l 17150 1.50 J.1 MO VALVE 107E5189/0 621 j 270 U41-F011B 2 17150 1.50 J.1 MOISTURE ELEMENT 107E51895 621 271 U41-ME104B 2 17150 1.50 J.1 TEMP ELEMENT 107E5189M 621 272 U41.TE103B 2 17150 2.80 J.4 HECW PUMP B 107E5182/0 623 273 P25-C0018 2 17150 2.80 J.8 HECW PUMP E 107E51824 623 274 P25-C001E 2 17150 2.80 J.4 HECW REFRIGERATOR B 107E51822 623 275 P25-00018 2 17150 2.80 J.B HECW REFRIGERATOR E 107E51824 623 l 276 P25-0001E 2 2.30 J.2 DP XMTR (FLO CC J ' **.) 107E5182/0 623 j 277 P25-DFT007B 2 17150 17150 2.50 J.2 PCV: HECW UNITS B/E 107E5182/0 623 ! 278 P25-F012B 2 2.80 J.4 FLOWIND SWITCH B 107E5182/0 623 279 P25-FIS003B 2 17150 2 17150 2.80 J.8 FLOWIND SWITCH E 107E5182/0 623 ! 280 P25-FIS003E 2 17150 2.80 J.4 TEMP ELEM (UNIT 8/E) 107E5182/0 623 281 P25-TE005B 17150 1.70 K.8 TCA C/B ELEC RM B 107E5182/J 624 282 P25-F0168 2 l ESS EQUIP RM COOL COIL 107E5189/0 624 283 U41-8604B 2 17150 1.70 K.8 284 U41-8604F 2 17150 1.70 K.8 ESS EQUIP RM C60L CO!L 107E51894 624 17150 1.80 K.5 EM ELEC (B)SUPP FAN B 107E5189/0 624 285 U41-C606B 2 i 2 17150 1.80 K.6 EM ELEC (B) SUPP FAN F 107E5189/0 624 286 U41-C606F 287 U41-DP11118 2 17150 1.80 K.8 DIFF PRESS INDICATOR 107E5189/0 624 f 17150 1.80 K.8 MO VALVE 107E5189/0 624 288 U41-F104B 2 2 17150 1.80 L.1 TEMP ELEMENT 107E5189/0 624 289 U41-TE110B 17150 2.00 K.6 TEMP ELEMENT 107E5189/0 624 1 290 U41.TE112B 2 17150 2.20 K.5 EM ELEC (B) EXH FAN B 107E5189/0 625 291 U41-C607B 2 17150 2.20 K.6 EM ELEC (B) EXH FAN F 107E5189/0 625 292 U41-C607F 2
-. . . . . ~ . .
. . . . - . - . , ,4 293 - . . . . . . . . .
Jv 17150 2.20 K.5 TEMP ELEMENT 107E5189/0 625 1-294 U41.TE113B 2 0*b 17150 2.70 K.5 MCR HVAC EXH FAN B 107E5189/0 626 295 U41.C602B 2 b 296 U41.C602F 2 17150 2.70 K.6 MCR HVAC EXH FAN F 107E5189/0 626 sy 297 U41-F010B 2 17150 2.70 K.5 MO VALVE 107E5189/0 626 f 298 = ron: 2 ~n 2.= = "c ver mee r ce ,- 17150 2.70 K.5 POSITION TRANSMITTER 107E5189/0 626 299 U41-POT 105B 2 17150 6.20 K.5 EM ELEC (C) EXH FAN C 107E5189/0 631 [ 300 U41-C609C 3 ] 17150 6.20 K.6 EM ELEC (C) EXH FAN G 107E5189/0 631 . 301 U41.C609G 3 i t Fire Hazard Analysis Database 9A.6 104 23 I
Rev o ABWR o die ecm etoecame n rierz (. 1, : Table 9A.6-3 Fire Hazard Analysis Equipment Deta Base-Sorted by Room - .4 ) Control Building (Continued) 3 ". LOCAnON tOCanON 8, e*, ITEM WL ELECT ELEV. NUMBER ALMIA SYSTEM ROOM 1, NO. NO. DIV. LOCATION COORD. COORD. DESCRPTION DRAIMNG NO. w Ct 302 '#1'"*0;C : "' 50 0.20 : "O"".'." 07;;-- ; ::1 ya 303 Ud I-DP1111C 3 17150 5.80 K.8 DIFF PRESS INDICATOR 107E5189/0 653 304 8A1-F104C 3 17150 5.80 K.8 MOVALVE 107E5189/0 653 M U41-TE110C 3 17150 5.90 L1 TEMP ELEMENT 107E5189/0 853 CP3 1
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% Figure 3.2p Control Building Radiation Zone Map for Full Power Operations, Section B-B %
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( C < 50 psym D < 250 pSym g
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- I.
y Figure 3.2v Control Building Radiation Zone Map for Full Power Operation, Floor 2F-Elevation 17150 mm h,
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.. ABWR oe: ion controloocaneattrier2 Table of Contents (Continued) 9A.4.2.3.23 Elevator (Rm No. 337) . . . .. . .. . . . .. . 9A.4-412 9A.4.2.4 Floor Four El 7900mm. ... .. . . . . . . . . . . . . . . . 9A.4-413 f.. . . .. . . . . 9A.4-413 l 9A.4.2.4.1 Control 9A.4.2.5 Floor Five El 12300mmRoom . Complex. . . . .. . .[.. . . ... . .. .. ... 9A.4 417 l 9A 4.2.5.1 Control Room HVAC "C" Exhaust Duct Chase 7 (Rm No. 522) ...... .. .. .. . . . .. .. .. . . ... . .... ... . 9A.4-417 i 9A.4.2.5.2 HVAC "A" Supply (Rm Nos. 511,512 and 513) = = 9A.4-419 l 9A.4.2.5.3 HVAC "C" Supply (Rm Nos. 531,532 and 533) = = 9A.4-421 l l 9A.4.2.5.4 Stairwell Landing (Rm No. 505) ...... . . . . . . . . . . .. 9A.4-423 )
9A.4.2.5.5 Chiller Unit "C" (Rm No. 534). . . . . . . .. . . .. .. 9A.44 2T-9A.4.2.5.6 Recirc Internal Pump MG Sets and Control Panels (Rm Nos. 501,502,503 and 504) . . . .. . 9A.4-427 l 9A.4.2.5.7 Computer Room (Rm No. 591) . .. . . .. 9A.4-429 I 9A.4.2.5.8 Passageway (Rm No. 521) . . . . .. . . . .. .. 9A.4-431 9A.4.2.5.9 Not Used . . .. .... . . . . .. . . . . . . . . . . . . .. . .. 9A.4-433 9A.4.2.5.10 Passageway (Rm No. 592) . . . ..g... . . . . . 9A.4-433 9A.4.2.5.11 Passageways (Rm No. 59 ..... . .. 9A.4-435 9A.4.2.5.12 Centrol Room HVAC " ", Exhaust Duct Chase i (Rm No. 595) ..... .. . . ... . . . . .. . . . . 9A.4-437 CP4 :
9A.4.2.5.13 Passageway (Rm No. 506) . . . . . . . .. 9A.4-438 9A.4.2.6 Floor Six El 17150mm.. ... . . . .. . 9A.4-440 9A.4.2.6.1 Control Room HVAC Supply "B" (Rm No. 621) . . 9A.4-440 9A.4.2.6.2 Passageway and Room (Rm No. 622 and 662) . . 9A.4-442 9A.4.2.6.3 Chiller Unit "B" (Rm No. 623) . .. . . . . 9A.4-444 9A.4.2.6.4 HVAC "B" Supply and Exhaust (Rm Nos. 624,625, 627,661, and 664)= . . . . . . . . . . . . ... . 9A.4-446 '
l 9A.4.2.6.5 HVAC "A" Intake Duct and Exhaustp Nos. 613, 617,618 and 619).. . . . . . . . . . . . = .... ..... . 9A.4-448 9A.4.2.6.6 Control Room HVAC Exhaust * )
7 4 20,029,ouJ 003-) ~....... . " (Rm Nos. 62p2..
. . . . . . . . . . . . . . . 9A.4-450 9A.4.2.6.7 Chiller Unit "A" (Rm No. 612) . . . . . . . . . 9A.4-452 9A.4.2.6.8 Control Room HVAC Supply "C" (Rm No. 615).. . .. 9A.4-454 9A.4.2.6.9 Passageway and Room (Rm Nos. 611 and 652) ... .. . . 9A.4-456 f 9A.4.2.6.10 Control Room HVAC Exhaust "B" (Rm Nos. 6g 61 S a.;d 55 !).a.. .. .. .. . .. .. .$. 9... ... . . .. . . 9A.4-458 9A.4.2.6.11 HVAC "C" Intake Duct and Exhaust (Rm Nos. 631, 632,633,634,651, and 653) . .... . . . . . . . 9A.4-460 9A.4.3 Turbine Building - . . . . . . . . . . . . . . . . . . . . . = 9A.4-462 9A.4.3.1 Floor One El 5.3m.. . . . . . . . . . . . . . .. .. . 9A.4-462 9A.4.3.1.1 Floor One (Except Fire Areas FT 1501-FT1503)... .. . 9A.4-462 9A.4.3.1.2 Air Compressors and Dryer Area (Rm No.111) . .. .. . .. 9A.4-466 9A.4.3.1.3 Stair Tower #1 (Rm No. I14) ... ....... .. . .. . . . . .. ... 9A.4-467 9A.4.3.1.4 Stair Tower #2 (Rm No.122) .. ... .. . . . . . . 9A.4-469 l
j 9A.4.3.2 Floor Two El 12.Sm . .. . . . . . . . . . .. .. . .. 9A.4-470 9A.4.3.2.1 Floor Two (Except Fire Areas FT-1501, FT 2500-FT2505) .. ... . . . . . . . . . . . . . . 9A.4-470 i
9A.0-vill Table of Contents l 5
nov. o ABWR assip,cesareta =7ier i
conduitin the raised floor areas. Cable contained in conduit or enclosed trays
! are not considered to coatribute to the combustible loading for the room.
The divisional panels a .e physicallyseparated as much as practical and located l
above the divisional e'.ectrical equipment rooms. The cabling from the divisional elecuical equipment rooms will be routed to the Safety System Logic Control (SSLC) cabinets with Divisions I and III on one side of the operator area and Divisions II and IV located on the opposite side of the operator area.
There is a suspended ceiling but only cables associated with lighting and the fire alarm system are routed above the false ceiling. The cables are in conduit.
[ Paper within the control room complex is required to be stored in approved containers (file cabinets, cabinets, waste baskets) except when in use.
l SAA.2.5 Floor Five El 12300 mm B j 9AA.2.5.1 Control Room HVAC " " Exhaust Duct Chase (Rm No. 522) l l (1) Fire Area-FC49tt 42.2.0
.s<
(2) Equipment: See Table 9A.63 y4 Safety-Relased Provides Core Cooling Yes,Df/ A No l (S) Radioactive Material Present-None.
I (4) Qualification of Fire Barriers-Rm No. 522 is defined as a vertical section of HVAC chase extending from the ceiling of the control room, formed by the l floor located at the 12300 mm elevation, to the floor of Rm No. 629 located at i
the 17150 mm elevation. All four walls are designated as fire barriers and are ;
of three hour fire-resistive concrete constmction. Access to Rm No. 522 from the 12300 mm level is provided by a three hour, fire-resistive removable panel. f (5) Combustibles Present-(NCLL Applies)
{
l Mre Landmg TotalHeat of Type Combustion (MJ) i Cable in trays 2 2 j 727 MJ/m NCIL (727 MJ/m
, maximum average) applies Analysis 9A.4-417 6
-y-, ,
w--ss
r ,
l Ilev. 0 l
.. ABWR oesiaa coneetsecumentiner2 (6) Detection Provided-Class A Supervised POC detection system in the room i and manual pull alarm station at 1.62-J.60.
(7) Suppression Available:
(
Type Locadon/Actuadon Standpipe and hose reel 4.00-K.95 & 1.6 -J.5/ Manual ABC hand extinguishen 4.0 - K.95 & 1.6 -J.5/ Manual l
(8) Fire Protection Design Criteria Employed:
(a) The function is located in a fire area which is separate from fire areas providing alternate means of performing the safety or shutdown function.
(b) Fire detection and suppression capability is provided and accessible.
I (c) Fire stops are provided for cable tray and piping penetrations through designated barriers. .
(9) Consequences of Fire-Postulated fire assumes loss of the function. Alternate means is provide (' by control room HVAC "( c CP4 ,
Smoke control is by the normal HVAC System funcdoning in the smoke !
control mode. Refer to 9.5.1.1.6 for additional information.
(10) Consequences of Fire Suppression-Suppression extinguishes the fire. Refer to Secdon 3.4, " Water Level (Hood) Design," for the drain system.
(11) Design Criteria Used for Protection Against Inadvenent Operation, Careless Operation or Rupture of the Suppression System:
(a) Refer to Section 3.4, " Water Level (Flood) Design," for the drain system.
(b) Location of the manual suppression system in an area external to the room containing the safety-related equipment (12) Fire Containment orInhibiting Methods Employed:
(a) The functions are located in a separate fire-resistive enclosure.
(b) The means of fire detection, suppression and alarming are provided and accessible.
i I
I Analysis 9A.4-418 7
! l Rev. o ABWR annien cearntoocamarmer2 C l 9A.4.2.5.12 Control Room HVAC " " Exhaust Duct Chase (Rm No. 595) l (1) Fire Area-FC42ee- 43 io 3
(2) Equipment See Table 9A.6
- cP4 Safety.Related Provides Core Cooling Yes,k'D3 No, See Remarks. 1 (S) Radioactive Material Present-None.
(4) Qualification of Fire Barriers-Rm No. 595 is deSned as a verdcal secdon of HVAC chase extending from the ceiling of the control room, formed by the floor at the 12300 mm elevation, to the 17150 mm elevation. Walls common to Rm No. 512 (FC1110), Rm No. 532 (FCIS10) Rm No. 593 (FCIS10) and Rm No. 506 (FC5110) are designated fire barriers and are of three hour fire-resisdve concrete construcdon. Access to Rm No. 595 is provided by a removable panel.
, (5) Combustibles Present-(NCLL Applies) t 1
Fire L-dbg Total Heat of i
Type Combustion (MJ) 2 2 None 727 MJ/m NCLL (727 MJ/m maximum average) applies (6) Detecdon Provided-Class A Supervised POC detection system in the room and manual pull alarm station at 6.50J.75.
l (7) Suppression Available:
Type Locadon/ Actuation 1
1 Standpipe and hose reel 4.0 -J.1 & 6.60-J.67 on the 17150 l level / Manual ABC hand extinguishers 4.0-J.1 & 6.60-J.67/ Manual l
(8) Fire Protection Design Criteria Employed:
(a) The funcdon is located in a fire-resistive enclosure.
! (b) Fire detecdon and suppression capability is provided and accessible.
l Analysis 9A4417 8
' 3 1
Rev.O ABWR ouissu conedDocumenuner2 l
(9) Consequences of Fire-Postulated fire assumes loss of the function. alternate means is provided by control room HVAC "
p Smoke control is by the normal HVAC System functioning in the smoke control mode. Refer to 9.5.1.1.6 for additional information.
(10) Consequences of Fire Suppression-Suppression extinguishes the fire. Refer to Section 3.4, " Water Level (Flood) Design," for the drain system.
[ (11) Design Criteria Used for Protection Against Inadvertent Operation, Careless Operation or Rupture of the Suppression System.
l (a) Location of the manual suppression system in an area external to the j room containing the safety-related equipment i
(b) ANSI B31.1 standpipe (rupture unlikely)
(12) Fire Containment orInhibiting Methods Employed:
l (a) The functions are located in a separate fire-resistive enclosure.
l (b) The means offire detection, suppression and alarming are provided and i accessible.
(c) Fire stops are provided for cable tray and piping penetrations through rated fire barriers.
(13) Remarks-Quantities of cable may be so small that they will be in conduit i rather than cable tray.
l 9A.4.2.5.13 Passageway (Rm No. 506)
(1) Fire Area-FC5110 (2) Equipment: See Table 9A.6-3 Safety-Related Provides Core Cooling No No (3) Radioactive Material Present-None.
(4) Qual!Scation of Fire Barriers-All walls of this passageway are designated fire barriers and are of three hour fire-resistive concrete construction. The ceiling 4
is common to fire areas FC4310, FC1210, FC1110, FC1310, FC4220 and the steam tunnel above and is of three hour fire-resistive concrete construction.
The floor is common to fire area FC4910 below and is also of three hour fire-9A.4-438 Analysis 9
^
l r
l Rev.0
.. ABWR cairn canroscuamentmer2 (10) Consequences of Fire Suppression-Suppression extinguishes the fire. Refer j to Section S.4, " Water Level (Mood) Design," for the drain sptem.
(11) Design Criteria Used for Protection Against Inadvertent Operation, Careless Operation or Rupture of the Suppression System:
(a) Refer to Section S.4, " Water Level (Flood) Design," for the drain system.
l (b) Provision of raised supports for the equipment l (c) location of manual suppression system in an area external to the room containing the safety-related equipment (d) ANSI B31.1 standpipe (rupture unlikely)
(12) Fire Containment or Inhibiting Methods Employed:
(a) The functions are located in a separate fire-resistive enclosure.
l (b) The means of detection, suppression and alarming are provided and i accessible.
(c) Fire stops are provided for cable tray and piping penetrations through rated-fire barriers.
(IS) Remarks-This equipmentis also required to function to support equipment l required for remote shutdown and therefore is in a fire area separate from the control room and its HVAC equipment.
The exhaust fans do not provide any cooling function. They only serve a purge function which is not necessary to the cooling function of the HVAC System.
B 9A.4.2.6.6 Control Room HVAC Exhaust "[" (Rm No . 62%629 and 66))
(1) Fire Area-FC49te-42.% [ _
(2) Equipment See Table 9A.6-3 Safety-Related Prosides Core Cooling w
Yes, No l
q (3) Radioactive Material Pres nt-None.
(4Aalification of Fire Barri- :rs-The building exterior wall cc.T.T.en w Pc '!c3
~ ~ ' nd t earn tunngall & cer.r :: P= ':a C20,625, S2? r d 553 4 N re bar iefor hree fFour fire-resistive concrete construction. Thc ;-d l
. ;;rio. .;" ~ '^ 1djnc , P- ~ m 2M w vi uu ee nour L v A 9A 4 450 Analysis 10
l I
l .-
Rev.O ABWR oasion controsoocumenvrier2 i
l \ l y - .s m.mm wum ucuun.The common interiorwalls between Rm Nos. 6 27 7 020,-02G, G;0 00 and 663 are in the same fire area and are not fire barriers.
The ceiling of this fire area forms a building exterior boundary and is of three l hour fire-resistive cong construction. The exhaust duct through the l ceiling in Rm No.499 does not have a fire damper. See Subsection 9.5.1.1.6 l
for a discussion of this design feature. A section of the floor common to fire area FC1210 and FC5010 below,is also of three hour fire-resistive concrete construction. Access ge CR HVAC Exhaust area is provided from Rm No.
622 through Rm No.Mr./._ ~ ,'un ou. ou5 o u "r '?n SSi ;..d 02 0
- f. .. "....% .002. m __- . "2 ' :_.52^,CCC .d 0% L..; m - a hiananah a (5) Combustibles Present-(NCI1 Applies) cP4 i
Hre L-Wg Total Heat of Type Combustion (MJ)
Cable in trays 2 2 727 MJ/m NCLL (727 MJ/m maximum average) applies (6) Detection Provided-Class A Supervised POC detection system in the fire area l and manual pull alarm station at 1.42-J.67.
(7) Suppression Available:
Type Location / Actuation i
l Standpipe and hose reel 1.37-J.67/ Manual ABC hand extinguishers 1.42-J.67 and 1.30-E.55/ Manual (8) Fire Protection Design Criteria Employed:
(a) The function is located in a fire area which is separate from fire areas providing alternate means of performing the safety or shutdown function.
l (b) Fire detection and suppression capability is provided and accessible.
(c) Fire stops are provided for cable tray and piping penetrations through designated fire barriers.
(9) Consequences of Fire-Postulated fire assumes loss of the function, but continued operation of the exhaust fans are not required for the equipment and systems served. If the CR HVAC "B" or "C" are placed in the smoke removal mode the control room should remain habitable.
Analysis 9A4-451 l <
! l 11
l l
Rev.o ABWR assiercannrersecumentmarz
\..
(9) Consequences of Fire-Postulated fire assumes loss of function. Even though access to rooms 612,636,631,634 and 651 are not possible, the equipment in these rooms are functional (they are in a different fire area). Alternate means
- is provided by CRHVAC "B".
(10) Consequences of Fire Suppression-Suppression extinguishes the fire. Refer
! to Section 3.4, " Water Level (Hood) Design," for the drain system.
l (11) Design Criteria Used for Protection Against Inadvertent Operation, Careless Operation or Rupture of the Suppression System:
1 (a) Refer to Section S.4, " Water level (Flood) Design," for the drain sptem.
(b) ANSI BSI.1 standpipe (rupture unlikely)
(12) Fire Containment or Inhibidng Methods Employed-(a) The functions are located in a fire-resistive enclosure.
(b) The means of detection, suppression and alarming are provided and
! accessible.
(c) Fire stops are provided for cable tray and piping penetrations through rated fire barriers.
{
(13) Remarks-safety-related cooling for multiple divisions is provided by redundant systems. The equipment on level 17150 in this fire area provides one division of cooling for the multi-divisional control room.
C 9A.4.2.6.10 Control Room HVAC Exhaust "/" (Rm Nos. 614)99themf1564- _
AStG l (1) Fire Area-FC4N !
(2) Equipment: See Table 9A.6-3 CP4 l l
Safety-Related Provides Core Cooling Yesh3 No, See Remarks.
(3) Radioactive Material Present-None.
(4) Qualification of Fire Baniers-All walls in this area are interior walls. The walls common to fire areg FC1110=d T^1^ f=d are designated as fire barriers and are of three hour fire-resistive concrete construction. The remaining interior walls are not fire barriers. The ceiling is a building exterior wall and is also of three hour fire-resistive concrete construction. The floor is common to 9A4468 Analysis 12 l
1 1
.= l Rev. o ABWR Desinncomratoecanenttrier2 l
I
\
1 adjacent fire area FC1310 below,is of three hour fire-resistive concrete constmction. Access to the CR HVAC "C" exhaust area is provided from Rm No.6s& 631. .
(5) Combustibles Present-(NCLL Applies)
CP 4 1 Fire L~Ag Total Heat of Type Combustion (MJ) 2 2 Cable in trays 727 MJ/m NCLL (727 MJ/m maximum average) applies I l l
(6) Detection Provided-Class A Supervised POC detection system in the fire area l l and manual pull alarm station at 6.70J.67.
(7) Suppression Available:
l l Type Locadon/Actuadon l
Standpipe and hose reel 6.60J.67/ Manual I l
l ABC hand extinguishers 6.60J.67 and 6.70-K.55/ Manual l (8) Fire Protection Design Criteria Employed:
(a) The function is located in a fire area which is separate from fire areas providing alternate means of performing the safety or shutdown function.
(b) Fire detection and suppression capability is provided and accessible.
(c) Fire stops are provided for cable tray and piping penetrations through designated fire barriers.
(9) Consequences of Fire-Postulated fire assumes loss of the function, but l continued operation of the exhaust fans is not required for the equipment l and systems served. If the control room HVAC is manually switched to the smoke removal mode the control room should remain habitable.
Smoke control is by the normal HVAC System functioning in the smoke i control mode. Refer to 9.5.1.1.6 for addidonal information.
(10) Consequences of Fire Suppression-Suppression extinguishes the fire. Refer to Section 3.4, " Water Level (Flood) Design," for the drain system.
Analysic 9A.449 13
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CHANGE PACKAGE NO. 5 Miscellaneous Tier I and Tier 2 Changes i
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l (2) The specified division storage tank discharge valve is opened. j (3) The specified division injection pump is started.
(4) The reactor water deanup isolation valves are closed.
Both divisions of the SLC System are automatically initiated during an ATWS condition I by safety system and logic contro! (SSLC) logic. With the storage tank at minimum level and both pumps operating, the system is designed to inject the minimum required boron solution.
Each SLC System pump has an interlock which prevents operation if both the test tank outlet valve and the pump suction valve are dosed.
l The SLC System provides borated water to the reactor core to compensate for the l various reactivity effects. These effects are xenon decay, elimination of steam voids, l
~
changing water density due to the reduction in water temperature, Doppler effect in uranium, changes in neutron leakage, and changes in control rod worth. To meet this i objective, it is necessary to inject a quantity of boron which produces a minimum concentradon of 850 parts per million (ppm) by weight of natural boron in the reactor l core at 20*C. To allow for potential leakage and imperfect mixing in the reactor system, ,
an additional approximately 25% (220 ppm) is added to the above requirement, resulting in a total requirement of greater than or equal to 1070 ppm. The required concentration is thus achieved in a mass of water equal to the sum of the mass of water in the RPV at normal water level (equal to or less than 455 x 108 kg) plus the mass of water in the RPV shutdown cooling piping (equal to or less than 130 x 108 kg). The quantity of boron solution contained in the storage tank above the pump suction shutofflevel provides the required concentration of 1070 ppm when injected into the reactor.
g cp5 The SLC System pumps have su icient net positive suction head (NPSH) available at the pump.The SLCSystem pu ps are designed to produce discharge pressure to inject the solution into the reactor w en the reactor is at pressure conditions corresponding to the system relief valve (10.7 MPaG),which is above peak ATWS pressure in the RPV.
SLC System components required for RPV injecdon are dassified as Seismic Category I.
Figure 2.2.4 shows the ASME Code dass for the SLC System piping and components.
The SLC System is located in the Reactor Building. The storage tank, test water tank, the two positive displacement pumps, and associated valving are located in the secondary containment on the floor elevation below the operating floor.
Each of the two SLC System divisions is powered from the respective Class IE dhision as shown on Figure 2.2.4. The power supplied to one motor-operated injection valve.
l l 2.2.4-2 Standby Liquid Control System 1
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ABWR ouien caneetoocumentmer1
. 1 HNCW HVAC HVAC HNCW FROM SURGE TANK NNS NNS TCW U COOLING LOADS l
l HNCW NNS - REACTOR BUILDING HVAC SYSTEM
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( NOTES:
- 1. THE INBOARD ISOLATION VALVE IS POWERED FROM CLASS 1E DIVISION !!, AND THE OUTBOARD ISOLATION VALVES ARE POWERED FROM CLASS 1 E DIVISION 1.
Figure 2.11.5 HVAC Normal Cooling Water System 2.11.5-2 HVAC Normal Cooling Water System 2
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"(Jeelal<A ce<<ceRan ABWR "" Qou controwocareuunner1 Except for the secondary containment isolation dampers, the R/B Secondary Containment HVAC System is classified as non-safety-related.
l l Normal Operating Mode In the normal operating mode, two supply fans and two exhaust fans operate. The l
supply fans operate on'y when the exhaust fans are operating.
The R/B Secondary Containment HVAC System maintains a negative pressure in
, the secondary containment relative to the outside atmospherc.
1 i
( The R/B Secondary Containment HVAC System isolation dampers are closed upon j l receipt of an isolation signal from the Leak Detection System (LDS) or a signal l indicating loss of secondary containmen xhaust fans.
" CP5 Smoke Removal Mode (ju bklrr3 md C
The smoke removal mode is manually initiated by starting the standby exhaust and )
supply fans, opening the exhaust filter unit bypass dampers, and partially closing i
exhaust dampers for divisions not affected by fire.
The R/B Secondary Containment HVAC System penetrations of secondary containment and isolation dampers are classified as Seismic Category I. The R/B Secondary Containment HVAC System is located in the Reactor Building, except for some of the R/B secondary containment HVAC supply and exhaust air components !
which are located in the Turbine Building. .
l l
Each R/B Secondary Containment HVAC System isolation damper requiring electrical power is powered from the Class IE division, as shown on Figure 2.15.5j. In the R/B Secondary Containment HVAC System, independence is provided between Class IE l
- divisions, and also between Class IE divisions and non-Class IE equipment.
1 Fire dampers with fusible links in HVAC duct work close under air flow conditions.
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The R/B Secondary Containment HVAC System has the following displays and controls in the main control room:
l (1) Control and status indication for the active components shown on Figure 2.15.5j.
(2) Parameter displays for the instruments shown on Figure 2.15.5j.
l The exhaust duct secondary containment isolation dampers are located in the l
secondary containment and qualified for a harsh emironment.
4 2.15.S-8 Heating. Ventilating and Air Conditioning Systems l
. Elev. o ABWR oesign controsaicum:avrier1 The pneumatically operated secondary containment isolation dampers, shown on Figure 2.15.5j, fail to the closed position in the event ofloss of pneumatic pressure or loss of electrical power to the valve actuating solenoids.
R/B Primary Containment Supply / Exhaust System The R/B Primary Containment Supply / Exhaust System removes inert atmosphere and provides air for prunary containment prior to personnel entry, and consists of a supply i j fan, a filter unit, and an exhaust fan as shown on Figure 2.15.5j. ]
l The R/B Pdmary Containment Supply / Exhaust System is classified as non-safety-l related. The R/B Primary Containment Supply / Exhaust System is located in the secondary containment R/B Main Steam Tunnel HVAC System l The R/B Main Steam Tunnel HVAC System provides cooling to the main steam tunnel l and consists of two FCUs. Each FCU has two fans. The FCUs are started manually.
l The R/B Main Steam Tunnel HVAC System is classified as non-safety-related. The R/B Main Steam Tunnel HVAC System is located in the Reactor Building.
CP5 l
s l R/B Non-Safety-Related Equipment HVAC System The R/B Non-Safety-Related Equipment HVAC System provides coo ng to the non-safety-related equipment rooms.There are six f2n cell mit,2n d_ feu. air handling units in the system.gach offooling coil,amffar() oc d b rNer as y @E -
consish The R/B Non-Safety-Related Equipment HVAC System is classified as non-safety-l related, and is located in the Reactor Building.
Reactor internal Pump ASD HVAC System
, The Reactor Internal Pump ASD HVAC System provides cooling to the RIP ASD power panels. The system consists of a two recirculating air conditioning units with cooling coils and four supply fans.
l l The RIP ASD HVAC System is classified as non-safety-related, and is located in the Reactor Building.
Turbine Island HVAC System l
The Turbine Island HVAC System provides heating, cooling, and ventilation for the Turbine Island. The Turbine Island HVAC System consists of the following non-safety-related systems.
(1) Turbine Building (T/B) HVAC System.
(2) Electrical Building (E/B) HVAC System.
Heating, Ventilating and Air Conditioning Systems 2.15.5-9 4
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SOLENOID VALVES ARE POWERED BY TS E CLASS 1EDMSONL11ENDMD ISCLATONDMESOLEf0DVALVES 9 NEIVWEFEDBYQASS1EOMSDNL M
, y Figure 2.15.5j Reactor Building Secondary Containment HVAC System ;
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$, Table 2.15.5f Reactor Building Secondary Containment HVAC System b t ID k Inspections, Tests, Analyses and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria
- 1. The basic configuration of the R/B 1. Inspections of the as-built system will be 1. The as-built R/B Secondary Containment Secondary Containment HVAC System is conducted. HVAC System conforms with the basic as shown on Figure 2.15.5j. configuration shown on Figure 2.15.5).
- 2. The R/B Secondary Containment HVAC 2. Tests will be conducted on the R/B 2. The R/B Secondary Containment HVAC System maintains a negative pressure in Secondary Containment HVAC System in System maintains a negative pressure in the secondary containment relative to the the normal mode of operation. the secondary containment relative to the outside atmosphere. outside atmosphere.
- 3. The R/B Secondary Containment HVAC 3. Tests will be conducted on the R/B 3. Upon receipt of a simulated signal, System isolation dampers are closed Secondary Containment HVAC System isolation dampers are automatica!!y upon receipt of an isolation signal from using simulated LDS isolation and loss of closed.
the LDS, or signalindicating loss of secondary containment supply and secondary containmen xhaust fans. exhaust fans signals.
4 The smoke removal m e is manually 4. Tests will be conducted in the smoke 4. On manualinitiation of smoke removal ip inTated by starting th standby exhaust and supply fans, opert ing the exhaust removal mode. mode the following occurs: (
- a. The standby exhaust fan starts.
filte r unit bypass damq !ers, and partially closing the exhaust da pers for divisions b. The standby supply fan starts.
not affected by fire. eg c. The filter unit bypass damper opens.
9 '
- d. The exhaust dampers of divisions not
{p affected by fire partially close to a predetermined position.
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- e. The measured air flow rate and the pressure in the ducts are at least equal @
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% removal analysis.
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- Motte/ ,
@l n
/
1**2 e33,
.,s ,
,CP6 a a000 Mg* CLASS INSMUMENT 1E pg : 3-
}
l b,,_,,/ l DIV 'V ;gi p 270*
,' I g g
[8 e mort.;: ,. .-
s s000 mm b g. d ' ' *' d il ,,J 1w g
ps(B)\'.. i',s,C) ,l
@ ~
*. c 10500 mm
* ** **) -
8 "
a v
. .... N5 . ...
c
~
lx% C/C x xx WA
~ ~
OG(B) DG(C)
, FCS(B) FCS(C) 4
@y ...................................... t- ,
w
+
1300 mm w 180' l
FULL POWER /5HUTDOWN AM OPERATION (SSv/h) 3 ;
As6 B < 10 c < s0 D < 250 E <1000 - -
F 21000 Figure 3.2i Reactor Building Radiation Zone Map for Full Power and Shutdown Operations, Floor 1F-Elevation 12300 mm 3.2 10
*adiation Protection i 10 1
l 4
nov. o ~
ABWR oenira ceaueroocannetmas l .
( -
l I Hatch Opening s ,
l or s/
/\
! s %
l Secondary
! Removable block % a
! wall BW contamment a barrierforR/B and .
MCAE for C/B l
(Note 2), or ea dia4*" CP5 ;
gone bo un d a'j Sliding door Stairway
[_ D U
_f
(- x --
l i
1 I
l I
Sump pit
- Typical floor designation: !
I
BSF-Basement,3rd floor t
l NOTES: l
- 1. Swing of door can be either way.
- 2. Divisional and secondary containment baniers and MCAE are fire baniers unless specified otherwise.
i
- 3. "** Denotes watertight door.
Control and Instnunentation Cables: Fiber-optic - - ,
1 i
Mdc * ** ' "~ " I I rek ta s v y~ <
l 1.14' (-r. e < 1) . I Fiber-optic or -------
' metallic Appendix A-5 Legend for Figures I
11
nov. o ABWR ouien coneeronauertraz
( List of Tables (Continued)
Table 9.4-4g HVAC System Component Descriptions-Non. Safety-Related Fans . ............. 9.4-47 Table 9.4-4h HVAC System Component Descriptions-Non. Safety-Related Elters.. .... .... 9.4-47 Table 9.4-4i HVAC System Component Descriptions-Non-Safety-Relate}}